rREVrouS , GVI 4

V

Table of Contents

I) Licensing-Checklist

Tru Waste Retrieval Project Richland WA

FF-01 Diffuse and Fugative (~U 1440; NOC 1047)

Licensing File

[ DN6 TD ~/\JE, j

rREVrouS , G"VI 4<?'~ fl)OC '6'o4-

~: fV1 1440 rJOC tof;).

2) Other Applicable Documentation (Emails, reports, c·alculations, etc.) 3) Informal Draft EV License

a) Licensee Comments on Informal Draft b) R_esolution of CoITll1)eJJ_ts

4) 28 Day Draft a) Licensee Acceptance b) F(A[S ti:Speas·e·aR8 mcpla.A·ati611 ~fcity iiotiticatiun tiine tequrremenr-

5) Final License

1

LICENSING CHECKLIST (Rev. 2)

Please initial boxes, as appropriate, rather than placitig a cheCk mark in the box

()1'16-~-orJt ~~.,.s : ~ ~~

RAES date received -~"'-/LA~...,....- and IM# assigned 1.-6414?51 N~ ·. rvcx:., \<Y\-a ..;;.->-- E:t.,t 1440

Erit!!red i_nto RAES Tracking/RDTT -~i/.t"---,_I '!-'--I _. Complet_eness Review dµe _ _,A/<KJf'-'A-~_--

To HP3 (responsible for fa<;1]ity) for assignment: ~--'--,_-... )'-"W=~=----------,--

To assigned HP2: __ :fP~~f _________ _

Add draft Table of Contents and separator pages to file.

Conduct completeness review using "Completeness Review Checklist" and draft "Completeness Notification" letter witldn 20 days of RAES date received. Discuss any concems/is_sues with HP3 during this 20 day period.

ffj~\~ Place '"Completeness Review Checklist'' in license file and prepare draft "Completeness Determination" letter. Letter must go out v,ithin 30 days of RAES date received.

• If application is incomplete, you may need to repeat this (and prior) step(s). • If application complete, assign NOC ID and EU ID, as appropriate. Do NOT obsolete 'old' NOC,

EU, etc. before the new final, approved, license is issued (you may have to exclude old from AOP for printing purposes).

ffl .,\'f- Forward license file and draft "Comp]etenes_s Detenninatiori" lett_er t_o HP3 for review. (If 28-day draft ,- has already been reviewed by licensee and HP3 and is ready to go out at the 30 day mark, you may

combine completeness and 28-day draft.)

HP3 - work wi_th HP2 to resolve any commen_ts the_n forward license file and draft "Completeness Determination" letter to HSC for review,

HSC - work with HP3 to resolve any comments then forward draft "Completeness Determination" letter to AA3 for finalization (HSC will update RAES Trac_king/RDTT upon transmittal and will note the 28-Day Draft Due Date, below, upon returning file to you). You now have 60 days to issue the official 28-Day Draft Approval letter.

28-Day Draft Du_e Date: ff (See next step, immediately.) -~~---

~i Is it necessary to send the 20-Day City Notification? Ify!!s, prepare ASAP and forward to HP3 for T review (follow same process as above for letter issuance [HP3 -> HSC -> AA3]). HSC will update

RAES Tracking/RDTT upon transmittal and will notify you of20-Day Comment Due Date, below, upon returning the file to you).

• USDOE-RL H_anford Siteis e_xempt from this requirement. • If RAEL is part of a Materials or Waste license, the responsibility falls on them to notify the city.

We issue these notifications for hew licenses or renewals ohly; we do not issue them for modifications.

20-Day Comment Due Date: ff ------------

(see page 2)

Page 1 of 2 All associated document templates can be found on zhe S: Dn·ve ar: .S:\EPH\Dara\RP _A!R\RAES\licensing Docs

Within 40 days ff of completeness determined, complete thorough review of application and draft license. Any EU specific condition·s niiist have justification/basis documented in the 'explanation' section of the database. Discuss any concerns/issues with HP3 during this 40 day period. Also, have HSC do an informal review of the li_c~nse for consist.ency before sendi_l).g to the licensee. ·

HSC Informal License Review

Send informal draft license to licensee for review, ailowing them a week to 10 days to get commen\s back to you. Be sure to include a 'due date'.

Upon receipt of response from licensee, resolve any comments/iss11~s/conce_rns right away and fina_lize the draft license and transmittal letter (28°day Draft). At least 3-5 days before 28-Day Draft.Due Date, send license file, draft transrni_nal letter, and draft license to HP.3 for final review.

HP3 approves and forwards license file and draft letter to HSC for review. HSC reviews and forwards to AA3 for finalization (HSC will hold file until licensee receives 28-day draft).

Upon licensee receipt of28-day draft, HSC will update RAES Tracking/ROTT, verify database concurrence, and return license file to HP2 with due date for licensee response or· final issuance of license.

Firial Due Date:~

Once licensee has accepted, or the 28 days has expired (no nuire than 2-3 days before), obtain an approval number (AIR#) from AA3 and prepare final license and "Final Approval" letter. Send license file (be sitre table of contents provides for final le1terllicense), final trarisminal letter, and final l_i_cense t_o HP3 for final review.

HP3 approves and forwards to HSC for review. HSC forwards to AA3 for finalization.

malizes:

Add final letter( s)

Update RAES Tracking/ROTT

Verify database concurrence

Update Licensee List

Add final file to database 'in box' to be entered/scanned

Page.2 of 2 All associated document templates can be found on the S: Drive at: S:\EPH\Data\RP _AIR\RAES\Licensing Docs

2

, I

Frazier, Thomas_ (DOH)

From: Sent: To: Cc: Su_bJe_ct_:

Kaldor, Reed A <Reed_A_Kal<[email protected]> Wednesday, October 12, 2016 4:34 PM Sc_hmidt. John W (DOH) Faust, Eric T; Carleo, Frank J; Frazier, Thomas (D.OH)

RE: A_EI Nunibers

Yes, I started working on them. I should be able to have them to Tom_ tomorrow m9rning.

From: Schmidt, John W (DOH) [mailto:[email protected]]

Sent: Wednesday, October 12, 2016 3:05_ PM To: Kaldor, Reed A <[email protected]>

Cc: Faust, Eric T <[email protected]>; Carleo, Frank J <[email protected]>; Frazier, Thomas DOH <_thomas.fra"[email protected]>

Su_bjl!ct_: RE: A_EI Numbers

I inissed coping Tom©

From_: Schmidt, Jo_hn W (DOH) Sent: Wednesday, October 12, 2016 3:0·3 PM

To: 'Kaldor, Reed A' ;<Reed A [email protected]> Cc: 'Faust, Eric T' <[email protected]>; 'Carleo, Frank J' <Frank J [email protected]~v> Subject: AEI Numbers - · - ·

Reed,

' Did you make any progress on the AEI numbers. Tom is close to issuing the TRU Retrieval Licenses and needs the AEI for

the EU 486 D/F replacement. Thanks

1

i=razier,_Thomas (D.OH)_

From: .Sent: To_: Cc: Subject:

I missed coping Tom©

From: Schmidt, John W (DOH)

Schmidt, John W (DOH) Wednesday, October 12, 2016 3:05 PM . Kaldor, Re_ed A 'Faust, Eric T'; Carleo, Frank J; Frazier, Thomas (DOH)

RE: AEJ Numbers

Sent: Wedne·sday, October 12, 2016 3:03 PM

To: 'Kaid or, Re_ed A' <[email protected]> Cc: 'Faust, Eric T' <:[email protected]>; 'Carleo, Frank J' <[email protected]> Subject: AEI Numbers

Reed,

Di_d you make any progress on the AEI numbers. Tom is dose to issuing the TRU Retrieval Licenses and needs the AEI for the.EU 486 D/F replacement. Thanks

1

I 2

(4)

DOE/RL-2o01-57, REV. 5

The owner or operator has received prior approval from EPA. [40 CFR 61,93(d)addcd at 67 FR 57167, Sept. 9, 2002]

3 Response: Prior" apiircival from WDOH for the PES system is re_quested herein._

4 Quality Assurance Requirements Related to Sample Sy"stem Inspections, Sample ua·ndling, ~nd 5 Sample Analysis

6 The sample handling, and sample analyses would comply with the CHPRC-00189, Appendix I, CHPRC 7 Quality Assurance Project Plan for Radioactive Air Emissions Measuremen"t. [Note: This w·ould incl_ude 8 laboratory analysis/identification of radioisotopes which contribute I 0% or more of the potential 9 emissions]. Since ail the radionuclides are represented by Am-241 +Progeny for alpha and

IO Cs-l 37+Progeny for beta/gamma these radionuclides represent all those that could contribute greater than I I 10 percent oft),e potential to emit TEDE t_o the MEI.

12 ,. 10 Annual Possessii>n Quantity

13 Regulato_ry Requirei11em: Indicate the annual possession quantity (APQ)fiif eachrad_ioiwclid_e. WAC 14 246-247-U0AppendixA (10). ·

15 The annual possession quantities for the radionuclides 'is entirely represented by Am-241 +Progeny for 16 alpha emitters and Cs-137+ Progeny for beta emitters. The annual possession quantities associated with I 7 each emission unit are listed in Table I.

..

28

--, -Vr (f ( fu; €,.,....,~lr J~ DOE/RL-2001-57, REV. 5

117.,,v:..:r--..s ~ V ' ' Table 1. · Estimated Emissions for TRU R trieval Project

Averag8. 'cu

_COntalner"

• . , . . . . , ... , " .... , ,,, , . , , , I ... . . . . . • . · Diffuse· and' Fugitive·Emissions Stagirig/Handling, of-Vented Containers.~.••.-·

' ' --- ~.....:.._.·,,. ' .... · •.. ~--.><-. -,.

' ','''•

_ C~ritair'lersf. v~arc

• ,,,'" •c' ,,., :

••. --~PQ' ,.·.· .. :'(Cl/yr)'·'/,·

1 ~BeptahaEEmm,ttttetersrs @yProg@ .

~-137-+Pt~

1.3E+o0

1.9E+o1

1!5E+04

1!5E+04

.' . ·-· .. ,. .

1.9E+04

2.9E+05

3.0E+05

2.0E-09 ~~~~)) 3 8E-05 4.7E+o0 1.8E-04 :-8E-04

2.0E-09 1~ 5.7E-04 8.7E-02 5.0E-05

( j _Radionuclide

/ Alpha Emitters

I I

AsS-~mec1 , -· Isotope

9.0E+o3

9.0E+o3

4.3E-07

2,2E-05 ·

2,2E-05-- - ----

29

'6.IE-04 61E'{)4 2.JE-04 ~~

, 1.0E+OO

1.0E+00

__ . _____ 2.2E~

4.3E-07

2:2E-05

2.2E-05

·.-,·Unit oOse ,_ 'ullabat'ei:f .. _Abate.d'\ · ~ •.Fa"ctor· · _:-Dose'-·. · , _ Dose 'd

.. (mrem/CI) -: (mrem/yr) '(mrem/y'/_ -

4.7E+00

8.7E-02

2.1E'06

1·.9E-06

3.9E-06

,, 2.1E-06

II 1 .9E-08

II 3.97f>6

1

J

. DOE/RL-2001-57, REV. 5

Table 1' Estimated Emissions for TRU Retrieval Project

Radionucllde

Alpha Emitters

Beta Emitters

Subtotal

Assumed Isotope

Am-141

APQ(CI); ...

2.5E+OO

3.8E+01

, : RerC~e · - . Fraction

1.0E-03

1.0E-03

. unabated _AbateCI'/, ... ; tfJ:',i> .. · ,f;:-:.)

·2.SE-03 2.5E-03

3.8E--02 3.BE-02

.'Unit Dose ·Factor

· . . (rrirem/CI)

4.7E+OO

a:?E-02

4.0E+01 L.OE-02 4.0E-02 --- ·,

Radio n~cllde: · Assi.imed · Isotope

., ... ;, AVeragG·

Cl/ Co~tainer ·

Alpha Emilters Am-241+Progeny 1.3E+00

Beta Emitters Cs-137 1.9E+o1:

Subtotal

2.5E+01

2:5E+01

3.1E+01

4.7E+02

5.0E+02

.OE-03 3.1E-C2

.OE-03 4:7E-C1

5:0E,c1

1.6E-05

2.3E-04

2.5E-04

4.7E+OO

8.7E-02

... lf!!_gilive.Emlssioris .:'- lnstaliatlo~\oi,!'l.u~fil® <>r_Ejuivalent t:ifie°raJ ~_!!_!_~~ Dart or FRP Systems) - -- . . ' ' "

@)~:: ·. Assumed .. c1, · . -.'c~,~~~~~-~

Isotope ·cOiltalner·~ · '-·:,veiaf";.>

[A~ 1.3E+OO 4.2E+03 2<1.1~rogeny

~y 1.9E+01 4.2E+03

5.3E+03

7.9E+04

8.4E+04

' . JL I I• I ,,-

:/_:~;~~~!t~ ··. ~--· .. (containers·,.:.

~: per,)'ear :'. __ ; · 60 inln/' ·. ···:

. : drum) · '·

4.BE-01

. •·; _:·.',)j

1.0E-Q3

'\. \ 96E-1)~

. Abated: ·,:.urlifDcise > ·:PTE:-·:- '"-<·Factor · · (Cl/yrf- ' : (mrem/CI)

3.0E-07 4.7E-«!O

4.SE-06°·

4.BE-06

8.2E-02

Unabated . · Abated

1 Dose - Dose

·.(mrem/yr) ... (mrem/yr)

1.2E-02

3.3E-03

1.5E;<J2

'1.5E-01

4.1E-02

__ · urli1bat8d -·Dose

(mrem/yr)

2.BE-03

7.BE-04

3.GE,03

1.2E-02

3.3E-03

1.SE-02

Abated Dose

(mrem/yr)

7.4E-05

2.0E-05 •· -·· ·

9.4F-05~

--'Abated ,_-_. ·.oosc.

1

'.mrem/yr~- • I 1.4E-OJ

3.9E-07 . ·

1.BE-06

0

i-

Radionucllde

Alpha Emitters

Bela Emitters

Subtotal

Radionuclide

Alpha Emillers

Beta Emitters

Subtotal

0 ~

Assumed Isotope

Am-241+Progeny ..

Cs-137+Progeny

ASsi.Jmed Isotope

· Assllmed . -Isotope

DOE/RL-2001-57.REV. 5

Table 1.

c -IJ )!u / ; - 2 Estimated Emissions ~r-rfiu etrieval Project /1_,f)C..../ U 1

( _;

·· .. . ,. ._-- .. _ .. -: Ii ; -· -<· _:APQ (Co) , ·

8.3E+03

1.6E+03

9.9E+03

8.3E+03

1.6E+03

9.9E+03

/. -,

8.JE1;00·'" -. . . 1:0E-03 . 1.6E+OO 7.9E~

• 9.9E+00 4.9E-03

" 1.0E-03 l! .37~8.3E+OO

1.0E-03 fis~1.6E+OO

,9.9Et00 9.9E+OO

.. ~i:.;g;iive-Emissici,;-~1rom:Ex~~-vatlon (Con minatlon·oeiected)~:Li '' ... -. " . ; . ----- . ---s . -Average Estimated _

·Concenfra- ,Soil· · ·:>./S~u··· :.:5011- .,-· · ·· · lion (dpm/ . -Concentra- ·.: :<Volume:·_:_ i:oenslly --~:·~,_t_ '.· .. ·. , ··.-.-. , 100 cm') _ . Hon (pCUg)': .:_ '(m'/yr)'i: ,;.'.:(glm')? '•'J'APQ(Cif

1.0E+02 2.0E+02 3.0E+02

5.0E+03 1.4E+03 3.0E+02

1.6E+06

1.6E+06

31

-9.6E-02

6.6E-01

7.6E-01

... B!f-;02

4.7E+OO •

8.7E-02

,Abated . Dos ·:. , ·:, Dose .

3.9E+01 ,

1.4E-01

Amrem!yr~

2.0E-02 ~+

2.0E-02

:- Abatl!d ·_,r .-Dose

. :·/mrem/yr) ·_

3:9E+01

1.4E-01-.

~+01

/

R'adionuclide

Alpha Emitters

Beta Emitters

Subtotal

Radionuclide

Alp~a Emitters

Beta Emitters

Subtotal

Radionuclide

Alp~a Emitters

Beta Emitters

Subtotal

DOE/RL-2001-57, REV. 5

Table 1. Estimated:Emlssions for TRU' etrieval Project

1Diffu:'e/Fugltive Emjs8ionscf~o111:Excavati_or,:(Higher __ Cor,tamihation :t1vel,· Controls' R~ul~d) ·

-.'Soll;'· - --, Vo1um8 / .. "

; (rn'1Yrl > ·. :Average . Estii"iiated: ':,:"-:;';t1% of ' .. ::.:, .> - - C - d • •• , • • • ••• •• >ii ./'.-~::,,-.· ?>i,~~te'd:·. · -i~~~~ <lJOitDOs~··:- Unab~i~l_ ... Abated R;,eas·e·· . ,,P"fE·;·':.:,':·,: ·-PTE· : .. Factor· < ;.:Dose- ,.,:- Dose

_, .AssumBd

Jsotope

. ·. oncentra- ·, - -Soil _-. ·· contamin·;. 'i'_::,soil_,_ .. ,._;-·; ·.: . __ u

1o0n0

(cdmp\"1, _.c~ric~ntra-

1', : .. :)~

1at(C?n

1' :.~/-.; .. , ·,·;_.o __ (e

9_:n,m_s~tyl _,.;_'.~.:-·

: Uon (pCVg _ ", eve),,-_;,- _

2.0E+03 4.3E+03 3.0E+OO 1.6E+06

1.0E+05 2.BE+04 3.0E+00 1.6E+06

AsSurri8.d Isotope

·\\i~!i~-~;l(:·--.·_;·Avera9e_.: ··;:.·::.{ffl3IYI') :·:.-: Concentra- Estlinate~I .·, :_'·~·:::{0.1_% .. oi -·

·_uon--·. -·sou:·.,··: ··::contarri1~· ,'(dj:jm/100 .. ,: ·cor1centra:.-(.:' i· .. na~lori ,:

,cm!)'.- · _-_Uon (pCUg) -,_ ''level)'_- _

Am- 2.8E+04 5.7E+04 ·3.0E-01 1.6E+06 241 +Progeny

Cs-137 +Progeny 5.0E+S 1.4E+05 3.0E-01 1.6E+06

Assumed· . Isotope

Am-241+ProgenY

Cs-1J7+PRogeny ·

32

•,AP_ Q __ .-(CI) / · : Frac:Uon '"' ;(Ci/yr)' - "0

(Ciiyrf-" (mrern/CI) (mremlyr) -• (mrern/yrj ..-·--2.0E-02

1.3E-01

1.5E-01

1.0E-03 4.7E+OO

8.7E 002

1.SE-04

9.5E-05

1.2E-05

1'.1E-04

::,_.u-_,"3bat8d ·. ·''Abated_-:,._ :Unit Dos& ,:lJOabcited .·.·, R81ea50"/ · PTE~_- , PTE· .. ·r' /Factor .: Dose·-

APQ(Cif- . racUon _ _ 'j<;i/yr)~:(Ci/yr) _ ·'(miern/CI)' - (mrern/yr)

2.7E-02

6.6E-02

9.3E-02

1.0E-03

1.0E-03

2.7E-05

6.6E-05

9.3E-05

.. ) ; . :;. .

4.7E+00

8.7E-02-

1.3E-04

5.SE-06

UE-04

-.:'.:,,_~; R-'~ie}a; __

5i:e:.·._/_-~·,uilabated · ----Abated Unit Dose· .-Uri3bated

. - P,TE · <~·> .. PTE '.-~ - · .. ·.factor, .. ·- _Dose:_-·· i'/APQ(Ci)?.'c- iacilon·- ·(Cl/yr)':' -.; (CUyi), - - (mrern/CI)': (mremlyr) . _. '. .- . .- . . . ' .. ..-.:: . '_, . .

1.4E-01

8.6E-01

1.0E+OO

1.0E-03

1.0E-03

1.0E-03

1.4E-04

8.6E-04

1.0E-03

4.7E+00

8.7E-02

6.7E-04

7.SE-05·

7.5E-04

9.SE-05

1.2E-05

.1.1E--04

, . Abated .. Dose -(mrern/yr) -

1.3E-04

5.SE-06

1.3E-04

; . Abated Dose."

_(m'rem/yr)

6.7E-04

7.SE-05

7.SE-04

DOE/RL-2001-57, REV. 5

Table 1. Estimated·Emissions for TRU f etrieval Project

- -·· .· .. >,;:, ·.un~bated Abate0

d.' ·., ·unit Dose ·Unabated :. Abated Assumed . ,. - ... Rftlease ':PTE 'yPTE·· ··;·.Factor _. Dose . . ~Dose

APi:i 1c;>' : : .. Radionucllde Isotope ._;.·· Fiactlon·: · · · (Cl/yr) · -(Cl/yr) (nirimi/CI) (mi'em/yr) (mrem/y_r)

Alpha Emitters Am-241 +Progeny 2.9E-03 1,0E+OO ,. ~ 9Eo03 --; 1.4E-06 4.7E+OO 1.JE-02 6.7E-06

Beta Emitters Cs-137+Progeny 1.7E-02 1.0E+OO ~~'02 ) 8.6E-06 8.7E-02 1.5E-03 7.SE-07

Subtotal 2.0E-02 2.0E-02 1.0E-05 1.5E-02 7.SE-06

a. All alpha emitters are conservaLively represented as Am-241 +Progeny and all beta/gamma emitters ~re conservaLively represented as Cs-137+Progeny.

b. Average Ci/container from,DOE/RL-2000-34 Rev O Table 1 and DOE/RL-93-15, Rev. 0. Table 2-1

c. DOE/Rl-2001-57, Rev O Table 1

d. Ci/yr=Average Ci/container• Containers /yr

e . .Washington State Department of Health (WDOH) has agreed to a potenLial emissions release fracti, n of 2E-09 for closed containers vented with Nucfil" or equivalent filters, otherwise 40 CFR 61 AppendixD values apply

f. PTE (Ci/yr) =APQ (Ci/yr)o[WAC 246,247-030(21 )(a) Release Factor for liquids or particulate solids].

g._DOE/RL-2006-29, Rev 1, Calculating Potential-to-Emil Radiotogicaf Releases and Doses. Table 4-8 for 200-West Area, effective release height <40 m for onsite MEI.

h. APQ for PES is taken from SWITS data for the trench inventory.

i. pCl/gm values are derived from HNF-2418; Soil Contamination Standards forProteclion of Personne, Tables 2, 3,and 4.

j. No reduclion or emissions due to abatement Is shown because the numeric efficiencies of abatemen control measures utilized.for open air activities have not been ~ endorsed'by approval authoriLies,

NucFil® is a registered trademark of Nuclear Filler Technology, Inc., Lakewood, Colorado.

APO

OVS2

FRP

HVU MDVS

= annuaI·p9ssession quantity •

= Orum Ve~ting System 2

= fiberglass reinforced plywood

= high:effic:iency particulate air {HEPA)- filtered vacuum unit

= Mobile Drum Venting System

33

NGR

PTE

PES

SWITS

VES

= ext generation retrieval

= otential-t~mit

= lortable Enclosure System

= )olid Waste lnfornation and Tracking System

· = apor extraction system

DOE/RL-2001-57, REV. 5

13.3 Vapor Extraction System

2 It is assumed that there is a potential to have two degraded drums within the trench for the basis of the 3 APQ, since only a portion of the trench is vented at any given time. Using a releas.e frachon of l E-03 for 4 particulates, the predicted release rate (unabated) for the VES without any emissions control equipment is 5 4.0E-02 Ci/yr as shown in Table l. The predict.ed release rate (abated) wit.h emiss.i,ons co.ntrol equipment 6 is the same as unabated. The predicted release rates for the representative radionuclides Am,241 +Progeny 7· an.d Cs-137+Progeny are '!S foilows:

Predicted PTE without any emissions control equipment

Predicted PTE

Aril-24l+Progeny

Am-with emissions 24i+Progeny control equipment

2.5E-03 Ci/yr Cs-l37+Progeny

2.5E-03 Ci/yr Cs-l 37+Progeny

8 13,4 Next Generation Retrieval (Point Source Dart or Overpack)

3 .. BE-02 Ci/yr

3.BE-02 Ci/yr

9 The venting system associated with NGR containment will have a rc:placeable HEPA filter rated at a 10 minimum of99.95% removal efficiency. This system wiil be.used for retrieval and repackaging ofup to 11 250 potentially d~graded containers.· Using a ;elease fraction of i .OE-03 · for particulates, the predicted 12 release rate (unabated) wiihout any emissions control equipment from the PES is 5.0E-01 Ci/yr. The 13 predicted release rate (abated) with emissions control equipment is 2.5E-04 Ci/yr. However, this assumes 14 the powered filtration system is used 100% of the time for abatement. The relative amount of emissions 15 abatement using the NGR contairiment system is not predicted since it will only be us.ed when con.trol 16 conditions discussed in Section 6.4.3 are met. However, to support conservative estimates while.allowing 17 for operational flexibiiity, any unfiltered fugitive/diffuse emissions (during exhauste.r non-operntion) from 18 the NGR containment system or PES are accounted for by the estimates shown in Section 13.7 below. 19 The predicted release rates for the representative radionuclides Am-24.l +Progeny and Cs-137+Progency 20 are as follows:

Predicted PTE without any emissions coritrol equipment

Predicted PTE

Am-241 +Progeny

Am-with emissions 24l+Progeiiy control equipment

3. lE-02 Ci/yr cs,J37+Progeny 4.7E-Ol Ci/yr

1.6E-05 Ci/yr Cs-137+Progeny 2.3E-04 Ci/yr

21 13.5 Installation of Nucfil or Equivalent Filters (Diffuse/Fugitive Dart or FRP 22 Systems)

23 A maximum of 4,200 containers will have installation ofNucfil or equivalent filters using the Dart or 24 FRP Sys.terns. A conservative time estimate for pressure release during each installation is 1 hour. Using a 25 release fraction of 1.0 E-3 for particulates and a time factor of 4.8E-Ol (60 minutes per container 26 multiplied by 4,200 containers and divided.by 526,000 minutes per year), the predicted release rate 27 (unabated) from using the Dart or FRP System for installation ofNucfil or equivalent filters without any

36

DOE/RL-2001-57, REV. 5

emissions control equipment is 9.6E-03 Ci/year as shown in Table I. Following installation of the Nucfil 2 or equivalent filter, the emissions are routed through the HEPA-type Nucfil or equivalent filter (certified 3 99.97% removal efficiency); therefore, the predicted release rate (abated) with emissions control 4 equipment is 4.8E-06 Ci/year as shown in Table 1. The pred_icted release rates for the representative 5 radionuclides Am-241 +Progeny and Cs-137+Progeny are as follows:

Predicted PTE Am- 6.0E-04 Ci/yr Cs-137+Progeny 9 .OE-03 Ci/yr without any 241 +Progeriy emissions control equipment

Predicted PTE Am- 3.0E-07 Ci/yr Cs-137+Progeny 4.5E-06 Ci/yr with emissions 24l+Progeny control equipment

6 13.6 NGR Containment System or PES (Point Source)

7 The venting system associated with NGR containment or PES will have a replac_eable HEPA filter rated at 8 a minimum of 99 .95% removal efficiency. This system will be used for retrieval and repackaging of 9 degraded containers. Using a release fraction of l .OE-03 for particul_ates, the predicted release rate

---~l"-'O (unabated)..without.an)'-emissions.control-equipment-from-the-~RS-is-9..-9&+.00-Cit;,a;-']:he-predicted1--------l l release rate (abated) with emissions control equipment is 4.9E-03 Ci/yr. However, this assumes the 12 powered filtration system is U:sed I 00% of the time for abatement. The relative amount of emissions 13 abatement using the NGR conJainmcnt system or PES is not predicted since they will only be used when 14 control conditions discussed in Section 6.4.3 are met. However, to support conservative estimates while 15 allowing for operational flexibility, any unfiltered fugitive/diffuse emissions (during exhauster 16 non-operation) from the NGR containment system or PES are accounted for by the estimates shown in 17 Section 13 .7 below. The predicted release rates for the representative radionuclides Am-241 +Progeny and 18 Cs-13-7+Progency are as follows:

Predicted PTE Am- 8.3E+OO CJ/yr Cs-I 37+Progeny 1.6E+OO Ci/yr without any 24 !+Progeny emissions control equipment

Predictecl PTE Am- 4.2E-03 Ci/yr Cs-I 37+Progeriy 7.9E-04 Ci/yr with emissions 241 +Progeny con_trol equipment

19 13.7 NGR Containment System or PES (Diffuse/Fugitive)

20 Containers will be processed without active ventilation but will use the controls described in Section 6.0. 21 Containment will be imposed when the limits as described in Section 6.4.3 are reac_hed. Because it is not 22 known what percentage of the PTE will occur as point source or diffuse/fugitive, calculations are 23 provided assuming that each method will be used I 00% of the time. A facility log will be required to 24 document usage of each. Using a release fraction of l .OE-03 for particulates, the predicted fugitive/diffuse 25 release rates (iinabated) from the NGR Containment structure or PES containment structure without any 26 emissions control equipment is 9.9E+OO Ci/yr. The predicted release ratc·(abated) with emissions control 27 equip_ment is assumed to be the same as predicted unabated release rates. The predicted release rates for 28 the representative radionuclidcs Am-24l+Progeny and Cs-137+Progeny are as follows: ·

37

NOTIFICATION OF PERMIT MODIFICATION REQUEST TO THt U.S. ENVIRONMENTAL PROTECTION AGENCY, REGION 10,

THE TRIBES, AND AFFECTED STATES

Attached is a request by theU.S. Department of Energy to modify the Hanford Site Air Operating Penrut (AOP). This form serves a:s notification to the EPA, tribes, and affected states per WAC 173-401-72_5.

Air Operatine Permit Number: 00-05-006 Renewal I Source: U.S. Deoartment ofEner<>v, Hanford Site Mailing Address: Physical Address:

Richland, WA 99352 Richland, WA 99352

Brief Description: This proposed Revision 5 addresses the.addition of three n~w emission units associated with TRU retriev:al activities. These new emission points cover operation of a vapor extraction System (VES), a n_ext geiietatiC?:~ .retri~val (NGR) containment system, and a portable enclosure system (PES). Due to the low pote~ial to emit, the YES will be considered a minor erriisSion pOint with associated cliffus_e/fugitive emissions. The NGR containment system and pES will be co·nsidered major emission Points inv~IVing-s'ome.ass~ciatcd diffuse/fugitive emissions as well. In addition to the three new emission unit~, this revision also addresses new or increased diffuse/fugitive sources to include w.iste repackaging, size reduction, in-situ grouting, and additional staging and Dart venting. Staging arid Dart venting will increase by 3,200 containers per year. Increasing the number ofc_ontainers to be darted b)' 3;200/yr changes the estirii"ated potential emissions for the staging an_d dart venting activities. The cstima.ted potential (unabated and ab~t~d) eff~ctive dose due to staging emissions is 2.-JE-04 mrem/yr TEDE to the MEI. Th~ ~stimatcd potential (unabated) effective dose due to Dart Venting is 3.6E-03 mrem/yr TEDE to the MEI. The estimated potential (abated) effective dose due to fugitive/diffuse emissions for Dart Venting is l.8E-06 mrem/yr TEDE to the MEI.. Three new emission units will be added to the TRU project and the estimated p9~ential em_i_ssions are as foi]ows: The estimated potentia_l_ (unabated and_ abated) effective dose du<0 to fugitive/diffuse emissions for the YES is L_5_E-02 rnrem/yr TE.DE to tjie MEI. The estimated potential (unabated) effective dose due to use of the NGR is I .9E-0l rnrem/yr TEDE to the MEI. The estimated potential abated effective dose due to the use of the NGR is 9.4E-05 mrem/yrTEDE to the MEI. The estimated (unabated) effective dose due to use of the PES is 3.9E+0! mrem/yr TEDE the MEL The NGR and PES operations will assure high efficiency particulate air (HEPA} filtration of the cxha_ust. However, the relatiVe amourit of the project rCqUiri_ng us~·oft_he PES is not known, hence no credit is taken for ai,:atemcnt liy the PES HEPA filters. The estimated potential ~bated effective dose for the PES is therefore listed as being the same as unabated.

Contact Name: Phon_e: M. S. Collins (509) 376-6536 Title: U.S. Department ofEner<>v FOR ECOLOGYUSE ONLY Application Number Date Received

Ecology Con tac_t - .

Date of Publication in Permit Reeister Public Comment Period Ends

3

Frazier, Thomas (DOH)

From: Sent: To·:

Cc:

Kaldor, Reed A < [email protected]> Thursday, October 13, 2016 10:31 AM Frazier, Thoriias (DOH) -

Subject: Faust, Eric T; Carleo, Frank J; Schmidt, John W (DOH); Homan, Nancy A; Fritz, Gary RE: AErNumbers

Tom-

As mentioned on the phone, we already have AEI numbers in our database for these units/NOCs. We want to retain the current nomenclature. As such, here are the AEI numbers for you to use.

AEI Number: 200 Area Diffuse/Fugitive - TRU Retrieval (currently NOc.(804) AEI Nu-riiber": 200 Area Diffuse/Fugitive - IDF (curr"ently NOC 713) AEI Numb_er: 200 Area Diffuse/Fugitive -C_leaning Ra_d Contaminated lieh:icles (c_urrently NOC 849)

Let.me k·now if you need any additional information.

Reed

Fron,_: Schmidt, Joh_n W (DOH) [mailto_:[email protected]] Sent: Thursday, October 13, 2016 9:08 AM To:Kaldor, Reed A <[email protected]> Cc: Faust, Eri_c T <[email protected]>; Ca_rleo, Fra_nkJ <[email protected]>; Frazier, Th_omas DOH <[email protected]> Subject:.Re: AEI Numbers

Thank you ... ! think they are the only t_hing Tom is waiting on for TRU retrieval

Sent froni my iPhone

On Oct 12, 2016, at 4:33 PM, Kaldor, Reed A <Reed A [email protected]> wrote:

Yes, I started viorking on them. I should be able _to have them to To"m tomorrow morning.

From: Schmidt, John W(DOH)[mailto:[email protected]] Sent: Wednesday, October 12, 2016 3:05 PM To: Kaldor, Reed A <Reed A [email protected]> Cc: Faust, Eric T <[email protected]>; Carleo, Frank J <Frank J [email protected]>; Frazier, Thomas DOH <[email protected]> Subject: RE: AEI Numbers

I missed coping Tom©

From: Schmidt, John W (DOH) Sent: Wedn:esda"y, October 12, 2016 3:03_ PM To: 'Kaldor, Reed A' <Reed A [email protected]>

Cc: 'Faust, Eric T' <[email protected]>; 'Carleo, Frank J' <Frank J [email protected]> Subject: AEI Numbers ·

Reed,

Did you ma_ke a_ny progress on t_he AEI numbers. Tom is close to issuing the TRU Retrieval Licenses and needs the AEI for the EU 486 D/Freplacement. Thanks

·'

2

r

Frazier, Thomas (D.OH)

From: Sent: To: Cc:

Carleo, Frank J <[email protected]> Thursday, October 20, 2016 4:11 prv, Frazier, Thomas (DOH); Faust, Eric T Schmidt, John W (OOH)

\

Subject: . RE: Review of license for T°i~U Waste Retrieval Diffuse and Fugitive Operation NOC 1042 EU 1440

Tom and Eric,

The purposed changes look fine. I only see one minor issue with Condition 30 within your proposed document being a duplicate of Condition 29. Looking at the current version cif the NOC (that is in the FF-01 now) I n_oticed t_hatCondit_ion 27 has been taken out. Was this condition_ supposed to go in plac_e of the duplicate on your proposed version? See belOl!J for a copy/paste of the wording of both.

Condition 27 from the Curren_t NOC wi_th_in the FF-OJ:

CONTA_MINATJON CONTROL - Soi/surveys during TRU retrieval During excavation activities for retrieval, excluding activities associated with reni_ova_l of soil overburden, radioactive contamination monitoring for diffase andfagitive emissions will consist of soil surveys at least hourl,v for both alpha and beta/gamma contaminati_on during TRU Waste R_etrieval operations. (WAC 246-247-040(5) and WAC 246-247-060(5))

Condition 29 and30 within your proposed version:

29. CONT AMINATJON CONTROL - limits to trigger further airbom_e controls . Radiological field survey monitoring will use set points for removable surface contamination levels of> I 000 dpm/100 cm"2 betalga_mmt1 and >20 dpm/100 cm"2 a_lpha to trigger the need to further evaluate airborne controls or eyaluatefurther preparation of materials for release. (WAC 246-247-040(5) and WAC 246-247-060(5))

30. CONTAMINATION CONTROL -Limits to trigger further airbome controls )

Radiological field survey monitoring will use set points for removable surface contamination levels of> I 000 dpm/100 cm"2 beta/ganima and >_20 dpm/100 cm"2 alpha to trigger the need to farther evaluate airborne controls or evaluate further preparation of materials for release .. (WAC 246-247-040(5) a'nd WAC 246-247-060(5))

Frank

Fron,_: Frazie_r, Thoma_s (D0H) [m_ailto:Thomas:[email protected]] Sent: Thursday, October 20, 2016 2:19 PM To: Faust, Eric T <[email protected]>

. Cc_:_ Carl_eo, Fra_n_k J <[email protected]>; Schmidt, John <[email protected]> Subject: Review of license for TRU Waste Retrieval Diffuse arid Fugitive Operation NOC 1042 EU 1440

Eric, here is the rough draft for the license for th_e TRU Waste Retrieval Diffuse and Fugitive operation (NOC 1042, EU 1440) for your review. Once we have your comments back on this license and have incorporated them as appropriate; we will send it along with the other six (1035 to 1040) 28 Day Drafts TRU Waste Retriev·aI licenses.

Thanks,

1

Tom

I

2

Frazier, Thomas (DOH)

From: Sent: To: Cc: Su_bject_:

Faust, Eric T <[email protected]> Thursday, Octo_ber 20, 2016 2:23 PM Frazier, Thomas (DOH) · Ca"rleo, Frank J; Schmidt, John W (DOH) RE: Review of license for TRU Waste Retrieval Diffuse and Fugitive Operation NOC 1042

EU 1440

Thank you Tom, we win try and get y'ail a response before nextThursda:y.

Thanks again, Eric

From: Frazier, Thomas(DOH)[mailto:[email protected]] Sent: Thursday, October 20, 2016 2:19 PM To·: Faust, Eric T <Eri_c._Faust@rl_.d_oe.gov>

Cc: Carleo, Frank J <[email protected]>; Schmidt, John <[email protected]> Subject:.Review of license for TRU Waste Retrieval Diffu·se and Fugitive Operation NOC 1042 EU 1440

Eric, here isthe rough draft for the license for the TRU Waste Retrieval Diffuse and Fugitive operation (NOC 1042, EU 1440) for your review. Once we.have your comments back on this licen·se and have incorporated them as appropriate;

we will send it alongwith the other six (1035 to 1040) 28 Day Drafts TRU Wast_e Retrieva_l licenses.

Thanks,

Tom

1

Emission Unit ID: 1440 n 200W 200 Area Diff~~e-TRU Re(rieval 200 Area Diffuse/F~tlve-TRU Retrieval This is a MAJOR. FUGITl~oim SOW't:e emission unit.

TRU Waste Retrieval

Abatement Technolog:y BAR.CT WAC 246-247-040(3), 040(4)

state only enforceable: WAC 246-247-010(4), 040(5), 060(5)

Zone or Ai"ea Ab.at~m_e.nt Techriolog"y ~dd_ition_al Description

Monit9ring R_equ.i,re.ments state enforceable: WAC 246-247-040(5), 060(5),.and federally enforceable:40 CFR 61 subpart H

Federal and State Regulatory

Monitoring and Testing Require1:11ents

Radionuclides Requiring Measurement

Sampling Freque_~~Y-

):; 40 CFR 61, Appendix B Method 114

Each radionuclide that could contribute greater than l 0% of the pciteritial-to-emit TEDE to the MEI, great.er than 0..J mrem/yr pote:r:itial-1_0-eijiit TEDE to the ME_!. or greater than 25% of the TEDE to the MEI, after controls.

Per the sitewid_e an:ib_ien_t moni~()ri_i:ig l)TOgra:e.

Sanipling Requirements

Additio_nal ~e_qui_rem_en_ts

Per the sitewide ambient monitoring progra)ti)amples will be colic monitoring stat_iov Cl

Se_i.: S~t_ion 5 of the genl!ral conditions in this licC!iisc for additional infomirition.

Additional monitoring or sampling requirements established by this License will be listed in the Conditions and Limitations section, if applicable.

Op~r~_t_ional St_ati(s

This Emission Unit has 1 active Notice(s) of Construction.

Project Title Approval# Date Approved NOC_ID

TRU Waste Retrieval Diffuse and Fugitive Operation (Replaces NOC 804) Nm Approved

Conditions (state only enforce·able: WAC 246-247-040(5), 060(5) if not specified)

1) The total ab.ated emission limit for this Notice of Construction is limited to 3.90E+Ol mrem/year to the Ma~imally Exposed Individual (WAC 246-247-040(5)).

1042

2) This approval applies to those addition_al acJivities described.belo'-Y. No a4,dition_a1 activities Or varia_t_ions on the approved activities that constitute a "modification" to the emission unit, as defined in WAC 246-247-030(16), may be conducted.

Transuranic waste retrieval involves the processes for removing and dispositioiling buried suspect transuranic mixed low-level radioactive waste (hereafter called TRU waste) from Hanford Site burial trenches for storage or d:ispcis_al at other approved locatio.ns. Dispositioning is the orderly administration and handling of waste (including contaminated soil) from the low level burial grounds to place it in approved storage or disposa.l status. The handling includes such actions as: packaging, labeling and tracking waste; venting, assaying, and staging waste·; inspecting wa:ste and was_te s_t_agi_ng areas; sarnpling/characteri.zing/designating wast · ng arrangements for the transfer of waste; completing necessary paperwork· and erfonning r ·· . ogical and/ industri_al.hygiene surveys. Two containment systems · associated with this appro One is Emission Unit 1327, Next Generation Retrieval (NGR) and, the ot or t e retrieva_l oflarge containers and is referred to as Emission Unit 1322, -Portable Enclosure System (PES). These emission units win be used when retrieval a<::t_ivit_i_e_s ex_ceed EU 486: 200 Area diffuse and fugitive contamination limits. In addition there are 3 types of drum venting systems and HEPA-filtered Vacutirit Units (HVU) used with thes_e venting systems and also during excavation and retrieval.

Page 1 of 8 for EU_ID 1440

owmg em1ssmn units for a de_tailed description of additiona_l controls/conditions and limits under this ap roval ·

!\.5. Hf PA Vacuums i:1-486-- 208 Area Diffuse/ Fugitive; Operation of the Transuranic Waste Retrieval Project

EU 755 Mobile Drum Venting Systein (Active Ventilation) (MDVS) EU 756 Mobile Drum Venting System (Passive Ventilation) (MDVS) EU I 181 Categorical Drum Venting System 2 (DVS2) EU 1322 Portable Enclosure System# I (PES) EU 1326 Vapor Extraction System (VES) EU 1327 Next Generation Retrieval (NGR)

3) The PTE for this project as determined under WAC 246-247-030(2 I)(a-e) [as specified in the application] is 3.90E+0l rnrem/year. Approved are the associated potential release rates (Curies/year) of:

Alpha - 0 8.3_0E+OO Liquid/Particulate Solid WAC 246-247-030(21)(a) Alpha retlease rate bas:Sd on Am-241 + Prog·eny. It is reco·gnii:ed that other radionuclides may be pi"es8nt in very limitecl quantities. Release rate ro"r the operation of NGR COntainment system and p'orlable endos·ure s}'Stem (PES). see Condilion Release rates: NRG con.tainmeni System ,Eln'd portable e·nciosure system PES. ·

Alpha - 0 3.BOE-05 Soli_d WAC 246-247-030(21 )(e) Release rate bas"ed 6n Am-241 +Progeny.It is recognized that other radionudides may be present in very limited quarititiE!s. Release rate for· staging/handlin"g vented containe·rs. See Condition Release rates: Sta"ging of ve·nted Coritainers.. ·

Alpha - 0 6.00E-04 Liquid/Particulate Solid WAC 246-247-030(21 )(e) Alpha release rate ba"sed on Am-241 + Progeny. It is recognize·d that other radionuclldes may be present in very limited quariti_ties. Release rate for ins_tallat6ion of Nucfil filters using th·e Dart System. See conditio·n Release Rates: Dart an·d Other Venting Systems

Alpha - O 9.60E-05 Liquid/Particulate Solid WAC 246-247-030(21 )(a) Alpha release rate based on Am-241 + Progeny. It is recognized that other radionuclides may be present in very limited qua·ntities. Release rate for ex·cavation of s·oil (co-ntamination detected). See COndition: Release Rates: Excavation and Retrieval of Coiltaine"rs. .

Alpha - 0 2.00E-05 Liquid/Particulate Solid WAC 246-247-030(21 )(a) Alpha release rate based on Am-241. It is recognized that other radionuclides may be present in very limited quantities. Release rate for excavation of soil (Higher contamination level, controls required). See ·condition: Release Rates: Excavation and Retrieval of Contairi"ers.

Alpha - 0 2.?0E-05 Liquid/Particulate Solid WAC 246-247-030(21)(a) Alpha release rate based on Am-241 + Progeny. It is recognized that other radionuclides may be present in very limited quantities. Release rate for excavation of soil (notification level). See condition: Release Rates: Excavation and Retrieval of Containers.

B/G-0 1.60E+OO Liquid/Particulate Solid WAC 246-247-030(21 )(a) Beta/Gamma release rate based on Cs-137 + Progeny. It is recognized that other radionuclides may be present in very limited quantities. Release rate for the operation of NGR containment system and portable enelosure system (PES). See Condition Release rates: NRG containment System and portable enclosure system PES.

B/G O O 9.00E-03 Liquid/Particulate Solid WAC 246-247-030(21)(0) Beta/Gamma release rate based on Cs-137 + Progeny. It is recognized that other radionuclides may be present in very limited quantities. Release rate for installation of Nucfil filters using the Dart System. See condition Release Rates: Dart and Other Venting Systems

B/G -0 5.?0E-04 Liquid/Particulate Solid WAC 246-247-030(21 )(e) Release rate based on Cs-13? +Progeny. It is recognized that other radionucl(des may be p,:es~nt in very lim_ited quantities. Release rate for staging/handling vented containers. See Condition Release rates: Stagir:ig of Vented Containers ..

B/G-0 6.60E-04 Liquid/Particulate Solid WAC 246-247-030(21 )(a) Beta/Gamma .release rate based on Cs-137 + Proger:,y. II is recognized that other radionuclides may be present in very limited quantities. Release rate for excavation of soil (contamination detected). See condition: Release Rates: Excavation and Retrieval of Containers.

B/G -0 1.30E-04 Liquid/Particulate Solid WAC 246-247-030(21 )(a) Beta/Gamma release rate based on Cs-137 + Progeny. It is recognized that other radionuclides may be present in very limited quantities. Release rate for excavation of soil (Higher contamination level, controls required) .. See condition: Release Rates: Excavation and Retrieval of Containers.

BIG -0 6.60E-05 Liquid/Particulate Solid WAC 246-247-030(21)(a) Beta/Gamma release rate based on Cs-1-37 + Progeny. It is recognized that other radionudides may be present in very limited quantities. Release rate for excavation of soil (notification level). See condition: Release Rates: Excavation and Retrieval of Containers.

The radioactive isotopes identified for this emission unit are (no quantities specified}:


4)

J J

Am - 241

Cs - 137

Pu - 241

U -238

Am - 243

Eu - 152

Sr-90

Cf -252

Eu - 154

U -234

Cm - 244

Pu - 238

U -235

Cs - 134

Pu - 239/240

U -236

The potential release rates described in this Condition were used to determine control technologies·and monitoring requirements for this approval. DOE rriust notify the Department of a "modification" to the emission unit, as defined in WAC 246-247-030(16). DOE must notify the Department of any changes to a NESHAP major emission unit when a speci_fic isotope is newly identified as con_tributing greater than I 0% of the potential TEDE to the MEI, or greater than 25% of the TEDE to the MEI after controls. (WAC 246-247-110(9)) DOE must notify the Department of any changes to potential release rates as required by state or federal regulations including changes that would constitute a.significant modification to t_he Air Operating Permit under WAC 173-401-725(4). Notice win be provided according to the particular regulation under which notification is required. If the applicable regulation(s) does not address rriaiin_er and type of notification, DOE will provide the Department with advance written notice by letter or electronic mail but not solely by copies of documents.

CONTAMINATION MONITORING - Routine Boundary surveys would be performed in addition to radiological control air monitoring and !;ield surveys performed during the work and end-of-shift activities. Routine on-going contamination surveys of all contaminated areas would occur weekly. (WAC 246-247-040(5), WAC 246-247-060(5), WAC 246-247-075(8))

CONTAMINATION CONTROL- Dust.suppressants Dust control or suppressants such as wa'ter, fixatives, atomized misting, covers, windscreens, or weather enclosures will be used as necessary to minimize airborne contamination as determined by the Radiological Control organization. (WAC 246-247-040(5) and WAC 246-247-060(5))

CONTAMINATION CONTROL- End o!:.shift or Jl!gh ~inds Spoil piles containing radiologically conra"rriinatecfsoil 520 dpm/100cm"2 alpha or> 1000dpm/100cm"2 beta/gamma will be segregated to the extent practicable from the nonradiologically contaminated soil. Containerizing spoils for disposal may be performed. Dust controls such as water, fixatives, or covers will be applied at the end of each shift or when sustained or predicted wind speeds are >20mph. The fixatives or other dust controls will not be required when the contaminated items are frozen, or it is.snowing, or other freezing precipitation is falling and predicted wind speeds are <20mph (WAC 246-247-040(5) and WAC 246-247-060(5))

PROCESS DESCRIPTION,. EXCAVATION AND RETRIEVAL OF CONTAINERS ~'NO+ Q. ( l C.G. P> This approval.applies to these additional activities described below. No additional activities or variations on the approved activities that constitute a "modification" to the emission unit, as defined in WAC 246-247-030(16), may be conducted.

Work will be performed in accordance with as low as reasonably achievable (ALARA) requirements as determined by the Radiological Control organization. One type of configuration is a V notched trench, containers in some trenches may not.have been stacked or placed in any orderly manner for burial. The specific steps or approach to uncovering the containers will vary according to the configu,ation of t_he trench to be uncovered, the type of containers to be retrieved, the proximity of nearby renches or fences, the designated lo.cation of the spoils pile, the planned extent of the soil removal, and other onsiderations.

Work to be performed within some trenches may be performed within a weather resistant structure(s) that will be re-. locatable along the trench. Weather enclosiires are effectively used for similar rem_ediation activities a_t other U.S.

Department of Energy (DOE) sites and.in general industrial use .. Experience during retrieval activities has shown at operational efficiencies can be improved if the operations are protected from impacts due to weather such as

wind-, rain, snow, and temperature extremes. The use of a weather resistant endosure could allow a mo_re effective recovery from events involving degraded containers and potential contamination.spreads.

rior to and duri_ng overburden remova_l, subsurface surveys such as ground penetrating radar, electromagnetic

-J·nductance, and magnetometer are performed. These surveys provide information regarding container depth, configuration, type, and condition. They may also identify and locate underground obstructions.

i) · The overburden soil will be removed to expose the was_te con_tai_ne_rs. Excavation equipmen_t will be chosen to £lO' effectively remove soil and retrieve the waste containers while minimizing damage to the containers. Excavation

activities will be monitored to identify contamination that might be present and to implement controls to minimize emissions.


The most efficient methodology for removing the Uncontaminated overburden from the containers will include the maximum use of conventional methods such as excavators, backhoes, front end loaders, brooms (boom mounted), or manual digging with shovels and similar hand tools. To excavate contaminated soil, hand tools predominantly will be used. Remotely-operated vehicles may be used to minimize personnel exposure in areas where high radiological and/or chemical hazards are discovered or anticipated. High efficiency particulate air (HEPA) fil~

be used for soil excavation for this application. Spot contaminat10n removal will be done in c.cordance with the HEPA filtered vacuum umt (HVU) NOC (DOE/RL 97 50, Radioactive Air Emissions Notice fConstruction fo?l=rEPA.riltered Voeuurn Radiwctive Air Emissilln u.,;1s, as Jlfiended). Within the V Notched

trenches, it is more likely that the use ofa HEPA-filtered vacuum to remove larger quantities of soil from the top surface of b.uried containers and soil materials in the interstices surrounding containers will be employed. Any use

'¾f the sitewide HVU will be performed under the NOC applicable to the unit. An estimated 300 cubic meters of soil at contamination detection levels occupies the void spaces between the

~ontainers buried in the trenches. Excavation activities will be controlled closely. Heavy equipment,.hand tools,.light equipment, or HVUs will be used to complete the soil removal operations and to access and remove the plastic and plywood materials covering the containers. All containers will be inspected to verify integrity. The container inspection will consist of a visual examination to

~

e. term. ine if there are.significant indications of corrosion, holes, dents or other. visual deformities. All containers ould be moved, turned, or otherwise relocated (manually or with powered equipment, slings, clamps, or ppropriate rigging) to facilitate an adequate visual inspection.

The exposed containers will also be visually inspected and surveyed for contamination. Externally contaminated containers will have fixative applied or will be deco~ted Caotaio,:; ma also be bagged or overpacked as needed. Overpacking. means placing cm!lai~in a larger closed container. Bulging or oten ially pressurized containers will be vented as descnbed-('"n-,e_ROCESS DESCRIPTION: VENTING OF CONTAINER . Severely degraded containers will be repackaged-t>F-in:s.i~uted. Repackaging means tra · g the contents of a degraded container into a new container or containers. The entire contents of 1lie container will not be sorted but · ill be placed into the new container or containers through the use of slings, clamshell excavators, manual la.bor, or the best available method that minimizes potential emissions.

epackaging may include size reduction. Size r_educing, cutting or disassembling material and equipment may be equired to ensure perso·nnel safety and/or more economical waste packaging. The process wiil include mechanical utting techniques such as low speed sawing, drilling, snipping, and shearing. The process will also include

bending and crimping to preclude the need for cutting operations where possible. · Containers niay include but are not limited to drums, metal boxes, concrete boxes, fiberglass rei.nforced boxes,

~

ulverts, and sealed gloveboxes. n-situ grouting will involve grouting around and/or throughout the waste, such that the entire waste container can

be removed as a monolith. Retrieval activities will include appropriate disposition of small amounts of incidental . contaminated soil (e.g., containerized or fixed in place). Larger areas ofccintamination could be fixed and the area

posted as. required by the Radiological Control organization for.late. r disp.osition. Bulle tran. sfer of contaminated soils for disposal also could occur. Some containers will be assayed and, if they assay as TRU waste, they may be further examined to determine whether they contain items prohibited from disposal at the Waste Isolation Pilot Plant (W[PP). Any prohibited items will be removed at a later date. Unvented TRU waste containers may be staged for venting in the burial grounds or may be moved to the Central Waste Complex (CWC) or another treatment, storage or disposal (TSO) ite for venting.

A number of retrieved containers are in good condition but are not vented. Although not technically meeting the definition of 'sealed' containers, Washington Sta.le Department of Health (WDOH) has reco ed these as closed containers such that potential emissions from these non vented con~s oeed oat he ia lud so far as potential emissions specific to wa~ng,emoval-from.~es:-Once vented, the containers are nc u calculating release rate n NOC 486 OCESS DESCRIPTION: STAGING OF RETRIEV D CONTAIN for staging and handling_iipcr$0ns. n · ·mum of 15,200 vented contain of waste wi managed duringthe peak years of this project Containers may he staged in the burial grounds pending further processing or transfer. Waste containers are

~~~~~~;red retrieved once transferred .to an approved TSO faci.lity. r ~C~ 2~~~~°10(5) and WAC 246-247-

8) PROCESS DESCRCPTION: VENTING OF CONTAINERS r +JD (J.}J C.W.: ..1-J This approval applies to these additional activities described below. No additional activities or variations on the


11

approved activities that constitute a "modification" to the emission unit, as defined in WAC 246-247-030(16), may be conducted.

' work will be performed to meet ALARA practices and will be conducted according to applicable operating

ocedures, radiological control procedures, and radiological work permit (RWP's). nt filters will continue to be installed in designated containers via one of the drum venting systems described in

this process description. These systems will ensure personnel and environmental protection. The methodology wi]l require penetrating the container and insening a vent. Penetration of the lid will be accomplished by either drilling through the lid or puncturing the lid with a filter dan (using Dan System). Container venting systems are described) in the following text. Designate .. d drums slated for venting will be vented with the Mobi.le Drum Vent.ing System (MDVS), Drum Venting System 2 (DVS2), or other venting methods .. (WAC 246-247-040(5) and WAC 246-247-

060(5)) If. l A- I)':, ABATEMENT TECHNOLOGY.-EXCA VA TION AND RETRIEVAL OF CONTAINER~ N l}Y UM The administrative control points set in this emission unit for contamination, as monitored by standard radiological field instrumentation, will be used to bound emissions based on current efficiencies of typical RadCon field contamination instri.lments.

The controls listed within this approval apply to TRU Waste Retrieval Project open activities. (WAC 246-247-040(5) and WAC 246-247-060(5))

RELEASE RA TES.ST AGING OF VENTED CONTAINERS

cavation and retrieval

A maximum of 15,200 vented containers of waste (including TRU waste containers, containers that are not designated as TRU waste, and those which could be retrieved with vents in place) will be retrieved per year. Once vented, the containers will be staged with the other retrieved containers for fonher handling, resulting in the staging/storage of a maximum of 15,200 vented containers per year at the LLBG. Using a release fraction of 2.0 E-09 for fugitive emissions from vented containers (as used in Radioactive Air Emissions Notice of Construction Application for the Waste Receiving and Processing Facility, DOE/RL 2000 34), the predicted release rate from the staging of vented containers without any emissions control equipment is 6.1 E-04 Ci/yr, with 3.SE-05 Ci/yr

ttributed to Am-24 I +Progeny (representing total alpha) and 5.7E-04 Ci/yr attributed to Cs-I 37+Progeny repres.enting total beta/gamma). No cred\t is taken for abatem.en_t; therefore, the.pred.icted abated release rntes are

asswned to be the same as the predicted unabated release rates. (WAC 246-247-040(5) and WAC 246-247-060(5))

RELEASE RA TES.-EXCA VA TION AND RETRIEVAL OF CONTAINERS/ C-" ~ To determine the corresponding soil concentration in picocurie~ per gram of individ?ai'i'.adion,_;;;lides, conversion factors, as developed in HNF 2418, Soil Contamination Standar·ds for Protection of Personnel were used. The average soil density was assumed to be 98 pounds per cubic foot. The beta gamma contributing radionuclides were assumed to be represented by Cesium I 37+Progeny and the alpha contributing radionuclides were assumed to be represented by Am 24 I +Progeny (predominant alpha contributing radionuclide in the soil is unknown; therefore, a sumption of Am 241+Progeny will produce the most conservative dose consequence). The respective volumes of

mamina.ted soil (i.e., 300 mA3, 3 mA3, and 0.3 mA3) at the three contamination levels are considered as released ---.:ruring manual excavation, using a release fraction of 1.0 E-3.

12)

e estimated 300 m3 of soil in contact with the containers is assumed to be contaminated at detectable levels (100 pm/100 cm2 alpha and 5,000 dpm/100 cm2 beta/gamma direct readings based on past operations and the pilot

clig). A smaller perc.emage (I%) of the contaminated so{! (i.e., 3 m:i), i.s assumed to be conta.minated at higher levels (2,000 dpm/100 cm2 alpha and 100,000 dpm/100 cm2 beta/gamma). Contamination at notification levels (28,000 dpm/100 cm2 alpha and 500,000 dpm/100 cm2 beta/gamma) is not expected. However, as a contingency planning estimate, 0.1 % of the contaminated soil (i.e,, 0.3 m3) is assumed to be contaminated at notification levels (WAC 246-247-040(5) and WAC 246-247-060(5)) /" _ -· II / RELEASE RA TES:. DART AND OTHER VENTING SYSTEMV-~ 1 •-..--

A maximum of 4,200 containers per year will have installation ofNucfil® or equivalent filters using the Dan or FRP Systems. A conservative time estimate for pressure release during each installation is l hour. Using a release fraction of 1.0 E-3 for paniculates and a time factor of 4.8E-0 l (60 minutes per container multiplied by 4,200 containers and divided by 526,000 minutes per year), the predicted release rate (unabated) from using the Dan or FRP System for installation of Nucfil or equivalent filters·without any emissions control equipment is 9.6E-03 Ci/year. Following installation of the Nucfil or equivalent filter, the emissions are routed through the HEPA-type Nucfil or equivalent filter (cenified 99.97% removal efficiency); therefore, the pre.dieted release rate (abated) with emissions control equipment is 4.SE-06 Ci/year. The predicted release rates for the representative radionuclides Am-241 +Progeny and Cs-137+Progeny are as follows:

Page 5 of 8 for EUjD 1440

I 3)

14)

15)

6)

17)

I 8)

Unabated PTE; Am-24l+Progeny 6.0E-04 Ci/yr Abated PTE; Am-241 +Progeny 3.0E-07 Ci/y (WAC 246-247-040(5) and WAC 246-247-06(1(5))

Cs-137+Progeny Cs- I 3 ?+Progeny

9.0E-03 Ci/yr 4.5E-06 Ci/yr

OH NOTIFICATION - Implementing PES or NGR.s:B,lltainment ring high hazard work activities, removable surface c&ntamination is maintained less than 2,000,000 dpm/100 "2 alpha and/or less than 4 rad/hr/100 cm"2 b.eta-gamma, limited to a I ft"2 area. For an allowed incre.ase in

contaminated area footprint of 4 ft"2 the limiting condition for removable contamination will be 500,000 dpm/100 cm"2 alpha and or lrad/hr/100 cm"2 beta-gamma. Exceeding any of these contamination limits will require work to stop, and notification to Operation and RadCon management in accordance with the RWP. Notification to WDOH via email or the established procedures in the Environmental Notification program will be required. For work to continue above any of these limiting radiological conditions, the NGR containment system or the PES and commensurate controls will b.e implemented. The NGR containment or PE_S exhaust system will be utilized to minimize the potential for contamination spreads outside of posted radiological areas. (WAC 246-247-040(5) and

AC 246-247-060(5))

WDOH NOTIFICATION -Transition to)!igh ]lazard J!OrkJlackage uring medium hazard work activities, removable coiriamination will be maintained less than 20,000 dpm/100 "2 alpha and/or less than 1,000,000 dpm/100cm"2 beta-gamma and the removable contamination area limited to

ft"2. Exceeding these limits will require work to stop, and notification to Operation and RadCon management in accordance with RWP. Notification to WDOH via email or the established procedures in the Environmental Notification program will be required. For work to continue above these limiting radiological conditions, the highhazard work package and associated controls shall be implemented. (WAC 246-247-040(5) and WAC 246-247-060(5))

WDOH NOTIFICATION - Drum vent.failure The department shall be notified fu eihail or the established procedures in the Environmental Notification program within 24 hours of all drum vents that fail to be installed properly and smears show >2,000 dpm/100 cm"2 alpha or >100,000 dpm/100 cm"2 beta/gamma removable contamination (an example ofa "failure" is a pressure release that blows past the seat of the boot or a deflagration). (WAC 246-24 7-040(5) and WAC 246-247-060(5))

WDOH NOTIFICATION - Loss ol;.c9ntainment WDOH will be notified per WAC !46-247-080(5) via email or the established procedures in the Environmental Notification program if a loss of containment occurs (dropping, spilling, puncturing a container, or otherwise encountering loss of integrity where contamination escapes containment), which exceeds 100,000 dpm/100 cm"2 beta/gamma or 2,000 dpm/100 cm"2 alpha removable contamination. (WAC 246-247-040(5) and WAC 246-247-060(5))

WDOH NOTIFICATION_-. Transition to .E¢' jlawrd ~ignation . . . Dunng so_,1 removal act1v,ues, 1f direct contarfimallon readings for the general area 1s greater than 28,000 dpm/100 cm2 alpha or greater than 500,000 dpm/100 cm2 beta-gamma, work will stop, the environmental compliance officer, RadCon Management and WDOH will be notified via email or the established procedures in the Environmental Notification program, and the controls listed immediately below, implemented. Once notifications have been made and the following controls implemented, work may resume under high hazard designation: a.. Soil will be wetted prior to soil removal; and soil will be maintained damp during soil removal. b. General area workplace air sampling will be performed. ( AC 246-247-040(5) and WAC 246-247-060(5))

TERNATNE APPROVAL - Unabated;Sll1issions Th potential unabated dose rate from manual excavation is 7.5 E-4 mrem/year. No credit is taken for abatement; the fore, the abated emissions are assumed as the unabated emissions. Although fixatives and similar controls will bee ployed for the higher contamination level and notification level contamination, no credit is being taken for ab ment; therefore, the abated dose rate is the unabated dose rate. (WAC 246-247-040(5), WAC 246-247-

( ),_WAC 246-247-075(4))

l 9) AL CT APROV AL - Container_)}andling . ··- _ Th roe_ andlin!l, of abnganal or severely d~ed containers as described.i~Ciss DESCRIPTION:_.

-- E· CAVA TION AND RETRIEVAt-0F-BQNIA rNF.Rs:--¥1ir bagging, ove_rpackmg, pl_acmg degraded outer ontainer contents into replacement containers or in-situ grouting is approved as meeting ALARACT, and these

· processes and associated records and procedures will be subject to inspection upon request by the department. (WAC 246-247-040(5) and WAC 246-247-060(5))

20) ALTERNATIVE APPROVAL- WDOH NOTIFICATION-Administrative Control on Emissions

Page 6 of 8 for EU_lD 1440

WDOH accepts the method proposed for calculating the estimated dose with the limitation that the annual release of the sum of the fractions of the curies released/annual release cannot exceed a value of I for alpha/beta plus gamma release. The limit on annual release shall not excee.d 2.1 E-2 Ci/year using Am-241 +Das a representative for alpha calculations and 1.15 E0 Ci/year using Cs-l 37+D as a representative for Gamma calculations, collected at a point not to exceed IO meters from the work area of disturbed material. WDOH will be notified when the sum of

/

he fractions reaches a value of 0_._8 representing 0 .. 08 mRe_m/year to the MEI, and a_dditional .controls w_il_l .be nitiated to ensure that the dose to the MEI does not exceed 0.1 mRem/year. Workplace air sampling will be

conducted when performing work.

CONTAMINATION CONTROL - Limits to initiate NGR or PES A ence to contamination limits in the i~diate work location for medium and high-hazard wo·rk will help

23)

24)

.25)

26)

27)

28)

29)

30)

31)

sur.l. that the work area airborne radioactivity limits (i.e., I .0E-09 µCi/ml for alpha emitters and 2E-06 µCi/ml for et_a-gaIIll11a eminers) are not ex_ceeded. (WAC 246-247-040(5) and WAC 246-247-060(5))

CONTAMINATION DOCUMENTATION - Exposed_g,ackages During repackaging activities (i.e., when transferring tire contents of a degraded container into a,;1ew container or c ntainers) an operations log will be kept noting conditions of the transferred contents/package'jf. RadCon will enerate and retain radiological records documenting air sample results and rern·ovable contamina_t_ion conditions

tluring retrieval of each container. (WAC246-247-040(5) and WAC 246-247-060(5))

CONTAMINATION CONTROL - Function,:b.eck.!l)isters and zyrayers Aro ized misters an_d fixative sprayers wffl be function checkea at the work site prior to commencing work

ties. (WAC 246-247-040(5) and WAC 246-247-060(5))

MINA TION CONTROL - NGR/PES activities Acri · ies done under confin_ement structur~ of PES and NGR will be considered to be diffuse and fugitive

ti ties uni,ss under active ventilation conditi6§):WAC 246-247-040(5) and WAC 246-247-060(5))

CONT A_M}NATION CONTROL - So~cavatio11JJ.ear c_ontainers Manual methods or HVU wifl be us€d. to excavate ;;;i inclose proximity to containers. (WAC 246-24 7-040(5) an~WA 246-247-060(5)) CON !NATION CONTROL -Transporting ~asteJ!.<lckages R 10logical contamination and dose rate monitoring will be conducted prior to transporting any waste containers. All waste will be contained as appropriate for transport. Covers such as tarps or plastic will be placed over deteriorated coatainers at the end of each shift. These practices of monitoring, container integrity inspections, and placem of_covers·will ensure good contamination control practices are observed during package handling activitie , soil removal (e_x_du<:ling overburden removal) and overpacking activities and when placing degraded

ntainer contents into replacement containers. (WAC 246-247-040(5) and WAC 246-247-060(5))

CO AMIN A TION CONTROL O Bulwansfer of C,QJ1.taminate<!..soil T soil surface will be wetted prior to bulk transfersof contamffiated soil. (WAC 246-247-040(5) and WAC 246-247-060(5))

!NATION CONTROL - Wind,_§Peed armed outside (excavation anc!Tor container retrieval) will stop if average wind speeds exceed 11 mph

e work and Contamination Area or Airborne Radioactivity Area conditions exist. (WAC 246-247-040(5) ~c 246-247-060(5))

T AMINA TION CONTROL - Limits to..triggerjj.lrthet.airborne g>ritrols Riidiologica field survey monitoring will useset points forremovab1e surface contamination levels of> I 000 dpm/100 c "2 beta/gamma and >20 dpm/100 cm"2 alpha to trigger the need to further evaluate airborne controls or evaluat further preparation of materials for release. (WAC 246-247-040(5) and WAC 246-247-060(5))

CO,l'ff.Prl\11NATION CONTROL - Soiljllrveys,9llring TRU~trieval During excavation activities for retrieval, excludmg activitiera'ssociated with removal of soil overburden, radioactive contamination monitoring for diffuse and fugitive emissio"ns will consist of soil surveys at least hourly for bo~h al ha and beta/gamma contamina.tion during TRU Waste Retrieval operations. (WAC246-247-040(5) and WAC -46-247-060(5))

CONT !NATION CONTROL - Removables,,ntaminatio~rvey Both a and beta-gamma contamination field surveys shall be performed for all removable contamination surveys, prior to aDd during soil removal (excluding overburden removal) and overpacking activities and when placing degraded outer container contents into replacement containers. Alpha surveys shall be performed for direct readings of container surfaces. Beta/gamma direct readin~ may be influenced by container contents, so are not as


useful an_d are not requi_red. (WAC 2_46-247-040(5) •9:<I WAC246-24'7-060(5))

32) CONTAMINATION CONTROL - Fixatives Fixatives or other controls will be employed if removable contamination levels exceed 100,000 dpm/100 cmA2 beta/gamma or exceed 2,0-00 dpm/100 cmA2 alpha. (WAC 246,247-040(5) and WAC 246-247,060(5))

33) CONTAM}NATJON SAM_PI,J_NG-ARA Workplace air sampling at the work site perimeter (011 all four sides of the work location) and do\viiwind of the container work location will be conducted when performing work in an Airborne Radiological Area, providing early incii_c_atio_n of potemi_a_l eleva_t_ion in work site pe,jmeter ai_rborne radioactivity. (WAC 246-247-040(5), WAC 246-247-060(5), WAC 246-247-075(8))

Page 8 of 8 for EU~ID 1440

4

.. , ...... ., .. , ... ,,.,,_,, ,.,.., 1,".'

DUPLICATE STATE OF WASHINGTON

DEPARTMENT OF HEALTH OFFICE OF RADIATION PROTECTION

309 Bradley Blvd., Suite 201 • Richland, Was/iington 99352 TDD-Relay Service: 1-800.,813-6188

Novemper 17, 2016

. .

CERTIFIED MAIL 7015 0640 0007 5050 7838

Mr. Doug Shoop, Manager United S~ Department of~gy Richland Operations Office ·· P.O. Box.550, MSIN.: AS-14 Richland, Washington 99352

Re: 28-Day DraftApproval of Notice ofConstruction (NOC) 1042

AIR16-IU0 NOC1042

Reference: Em.ail (LB# 4751), from John Sclu:nidt (WDOH) to Multiple USDOE Staff, ''NOC Consoli_datjon", dated Jµne 30, 2016.

Mr. Shoop:

As per t,l)e refe~nce email, we have worked with your staff to make changes to move the Nbcs lind/or Emission Units (EUs) associ'.~ with t,his license ~m \l o~-19-mariy, (o a ofie-to-on.e relationship. We appreciate your cooperation:and willingness to support·our future database needs aiid to iiiake license actions more efficient and cost effective 1Jlovii).g fo_I'Wll.I'g. - . . .

Pursuant to Cb_ap~r 246-247 of the Washington Administrative Code (WAC), the update wiiibe approved according to the enclosed License for:

TRU WlllSte 1~,etrievill Diffuse and Fugitive Operation (EU 1440; NOC1042)

(previously EU 486, NOC 804)

The Washington State Department of Health (DOH) considers the conditions,. controls, monitoring requiren:ierrts, and limitations ofth:e License integral to approval of your liJiplicatfoil.

This approval shall take effect, and a firull 11-pprovlll lettc;r iSS11¢, ~-eig}!t (2:8) deys aft~ you receive this Jetter, unless you apply for an adjudicative proceeding, as de.sctfbed below.

If you accept the conditiolis and lfo1itations of this approval.and do not wish to apply foi an a4judicatjve p);'Oceed_ing, but wish to proceed 'iiilde'r this,approval before the 28 days have

Publi_c Health - Always Working for a Safe:r and Heal_thier Washington

@,e., .. 0

_,· r ·Mr. Doug Shoop · November 17,2016

Page2ofJ

AIR i6-ill0

elapsed, please notify us in i.yriting and the DOH will issue a fuaj. lq)pl:'Oval I~~- Your notfoe shou,ld be mailed or·fmq.:d to_:

DOH ~ Office of Radiation Protection Radioactive Air ~_s1ons Section 309 Bradley Blvd., Suite 201 Richl_llll_d, Was1$gto11 98352 FAX: (509) 946-0876

If there are concerns with the condltions and limitations of the approval, pl~e notify the DOH. If attempts to resolve the concerns fail, the DOH will deny your app_Ji_catim;1 aI_ld you m_ay contest the conditions 311d lj1",it;i#ons of !µis· approval, within 28 days of receipt, by filing the enclosed Request for Adjudicative Proceeding or·a document providing substantially the same information with the DOH, Adjudicative Service Unit (ASU), in a manner that.shows proof of service O!I the ASU. TheASU's address'is:

DOH - Ad'udicative Service Unit u... ... . .. . .. 310 Israel Road SE P.O. Box 47879 Olympia, Washington 98504-78.79

You must include a copy oftJ:iis. ~val wi~ your appHcatioi;i. FIL.,:NG SHALL NOT BE DEEMED COMPl.,E'Ul UNTIL 1HE ADJUDICATIVE SERVICE UNiT ACTUALLY RECEIVES YOUR APPLIC::ATiON.

If you ha:ve any questions regardmg this approval, please contact Mr. Thomas Frazier at [email protected], by pl)one, a,t (509) 946-0774.

;;J;!~ P. John Martell, Manager Radioactive Air Emissioils Section

Enclosures: I. Condi.ti~ aI_ld Limitations for EU 1440 (NOC 1042) 2. Request for Adjudicative Proceedings

cc: ( see next page)

Mr. Doug Shoop November 17, 2016 Page 3 of3

cc: Ruth Allen, WRPS Matthew Barnett, PNNL LjlYll,YIII !:lauder, Ecology Shawna Berven; WDOH Lucinda.Borneman, WRPS L~ Bostic, BNI Friliik Carleo, C:HPRC Cliff Clark, USDOE-RL Jac.k Donnelly, WRPS D~s Faulk, EPA Eric Faust, USDOE0RL Tom Frazier, WDOH Gary Fri~. M~A Philjp Gent, Ecology Daniel Heuston, Ecology Reed Kaldor, MSA Paui Karschnia, CHPRC Ed MacAlister, USDOE-RL Jiµ! McAµley, EPA Val_arie P~; Ecology John Schmidt, WDOH JeffVoogd, WRPS Davis Zhen, EPA Environmei:rtal P~rtal RAES Tracking: Line 16-191, EU 1440; NOC 1!)42

AIR16-1110

Emission Unit ·w: 1440

200W 200 Area Dlffil.se/Fugltlve-TRU Retrieval 100 Area Diffose/Foejtive-:TRURetrieval '(his ts a MAJO)... -F\JqnJ\'E, ~poi;nt source~ ~t

~-u·wa.ve ~~al

Aba~men't T~chnology BARct WAC 246-247-040(3), 040(4)

~~t~ only enforce:a._t~I~: \,:VA{;; 24fl-'.;!47-01 Q( 4 ). 04<l@, 060(5)

Abatemnt Tedmology

Monitoring.Requirements state enforceaple: WAC.246-247-040(5). 06Q(5). and federally enfciri:ilable:: 40 CFR 61 subpart H Fedual 1111d State· Monitorillg 1111d Testing Radlonuclides Requiring S_11111p_llng ~to!}' ... _ . ~men~. Me~eniill! Freqn~

- - - -- .. WAC 246-247-07S[ZJ 4() CFR 61, ApP.O:ndix. B Each radionuclide.that could Per th_e sit~wi!fe

M!'(h~ 114 co[\tribuie greaier tl\an i°O¾ ambii;nt monitoring of the potential-to-emit TEDE program. to the MEI, greater than 0.1 mrem/yr potential-to-emit TEDE to the MEI, or grcalCr than 25% of the TED.E to the MEI, after controls.

$•mpllng Reqniremenb Per the sitewide ambient monitoring program. samples-will be collecied from the existing near-facility · mo.ni.~ stations.

Additional Requlronients Sec: Sa.:ticm S oftbc ema1 conditions i-u this license far additional mfcrmation.

AddiU"!"a) ,j,qnlla(lng o.r s,ampfing ~ulnlm~ es_ta~U~ by lhts Uc:iense ~II ~ list~ in the Condl~iis and LlmllaUons aec;tklil, ff appiic;!ble.

Operational StalllB

Tl:!.~ ~jssj~)'.I Unit has 1 l(ctjve Not)!=!!(s) °" Cc>~lon.

Project Title Approval# DateApproved NOC,JD TilU Waste Retrieval Difli.ise and Fugitive Operation (Replaces NOC 804) Not Approve¢

Con~it}oni; (st;rt~ only el)forcea:bte: WA~ 246-~47-~(5), 060(5) i_f "9' sp~"1!1!i) 1) The total.abated emission limit for this Notice of Construction is limited to 3.90E+-Ol mrem/year to the

Maximaliy Exposed Individual (WAC 24~247-040(5)).

1042

2) This approval applies to those additional activities described below. No additional activities or variati_ons on the ajjpr'oved acrivi,ti_i:s tl;mt g;,tistib¥e a ",:i!odifi,;ation" to t_be e:ri:iissio)) unjt, Ii§ defi),~ in WAC246-247-030(Ili), may be·conducted. · ·

Tn(nsiirajric '-'ilsl!' re_trieval ilivo_lvc;,; ili.i' l'"cl~ for !=living a.n!l dlspos_i_tjoning buped suspect ttansuranic mixed low-level radioactive waste (hereafter ci!.lled TRU waste) from Hanford Si_te burial ~ch.es for stol'l!ge or disposal at other approved locations. Dispositioning is the orderly •drninistn\lion and handling of waste (including contaminated soil) from the low level burial grounds to place it in approved storage or disposal status. Toe baild)ing iµcJµdes such actiofis as: packaging, la)lelirig and tra,cki,,g waste; venting, assaying, and staging waste; inspecting waste·and waste staging areas; sampling/characterizing/designating waste; making ~ts fo.~ i\ie ~(~ of waste; ~mP.leting ~ papc;rwoz:k; ;u:id perforIDl/!g raifiofogi~ a,n!l/or industrial hygiene surveys.

~ the foBowing ernissitin units fora detail~ description of add1tiorial CQntrol_s/ctinditions andiilriits u;n~ this approval: EU 455 HEPA Vacuums EU 486 ioo Arca Diffii§CI' Fugitive; Operation oftbe Trarisur.in_ic Waste Retii.eval Project

Page 1 cf8forE\J_ID 1440

EU755 EtJ'7S6 EU I 181 EU 1322 EU (3_2!i EU 1327

Mo.bile Drum Venting Systein (Active Ventilation) (MDVS) Mobile Drum Venting System (Passive Ventilation) (MDVS) Categorical Drum Venting System 2 (DVS2) Portable Eii:clos;iie System #I (PES) Vapor Extraction System (VES) Next Generation Renieval (NGR)

3) The PTE for this project as determined under WAC 246-247-030(2i)(a-e) [as specified in the application] is 3.90E-+-OI ll)remfy~. Appro;e<I an: the associated poiential release rates (Ciiries/yi:ar) of: ·

Alpha - 0 8.30E+OO Liquid/Particulate Solid WAC 246'247-030(21)(a) Alpha ralosse rate baseo ori Am-241 • Progeny. I1 ls recog,lzed that other radionudides niay tie present in ve,y limited quanlltlas. Roi...., rate lot tho operation of NGR containment aystom and PQltlllllo oriclOS!JfO ayston\ {PES). See Ccrialtion Release i'ato;: NRG caritaln'mlint Systorri and portable eri'cloSun, ays1o·m PES. . _

Alpha - 0 3.SOE-05 Solid WAC 246'247,030(21 )(e) Release rate based en Arn-241 + Progeny. It Is recognized that other radlcnudldes may be present In very limited quantities. Release rato fer staglnghlandllng vented containers. See Ccndltlcn Retoeso rates: Stiigti,g of Vented Ccntalners.. ·

Alpha, O 8.00E-04 Liquid/Particulate Soiid WAC 246-247-030(21 )(e) Alpha n,laase rate based en Am-241 • Progeny. It Is recognized that ctl'ler ra<lianuclldes may be pn,sent In wry limited quantities. Re~se ra19 foi lnsiallat6Icn cf Nudil filters using tlie Dart System. See cicndltlcn Release Rates: Dart and Other Venting System,

Alpha -. 0 9.SOE-05 Liquid/Particul$ Solid WAC 246-247-030(21 )(a) Alpha n,leue rate based on Am-241 + Progeny. It is racognlzed 111st Other radlonudldes may be pn,sent In veiy limited quantiUes, Release rate for eia:avatlon cf soil (contamlnatlon detected). See condition: Release Rates: Excavation and Retrieval of Ccntolnsrs.

Alpha-0 2.66i:-0s Liquid/Particulate Solid ''iiAC 24&-247-030(21)(8) Alpha ralGase rate based on Am-241. It is racognlzad ll1at Other radlonudides may be prasent In very limited quantlties. Release rate for UCSvatlon of soll (Higher a:intainlnado·n 18Vel, controls required). see· con"dltlc"r1: Release Rates: Excavation and Retrieval of Canialrieiil.

Alpha - 0 ·2. 70E,05 Uquid/Particulate,Solid WAC 24&-247-030(21 )(a) Alpha release rate b3S:8d on ~241 + Progeny. It Is recogr'Ued tl'\at other radionUdk:Ses may be present In very ll~ted quanUtles. Release rate for excavation cf aoll (notlflcatlon leWII). See condition: Retosse Rates: .Excavation and Relrteval of Containers.

BIG - 0 1.60E+OO Liquid/Particulate.Solid WAC 246-247-030(21)(a) Beta/Gemma release rate based on C&-137 + Progeny. It ls recognized that other radlcnuciides mey ba pn,sent In very Urntted quantltles. Release rate for the operation of NGR ci>ntalnment syslllm and portable ei\cJosura system (PES), See Condition Release raieS: NRG c:ontalnm8n(Syslem anct·portabte enclcis\lA:t &Y',tflm PES. .

BIG O O 9.o<iE-03 Liquid/Particulate Solid WAC 24&-247-030(21)(e) _B8111/Garnma niteasa rate baSed on Cs-.137 + Pmgeny. It Is n,a,gnlmd 111st other radlonudldes may be prasent In very limited quanllties, Release rate for lnstal1allcn cf Nudll filters using the Dan System. See condition Release Rants: Dart and Other VentJng,Systams

BIG O O 5.70E-04 Liquid/Particulate.Solid WAC.246-247-030(21)(e) Release rate based on Cs-t:i7 • ·Prggany . It is n,cognized ll1at otner ra<llonudldes may be pn,sent In very limited quantities. Release rate for staging/handling vented containers. See Concltlon Release rates: Staging of verited Ccntulner& ..

BIG - 0 6.60E-04 Liquid/Particulate SoUd wAc 246-247:.030(21 )(a) .. Be)a1Gemrna .. rsIease .. ra1e baoed o,:i es-1:3_1 • Progeny. 1\ Is rscogntze,l' ihat '?1111!1'. raoloruJdldes_may be·ll"!Sent _In vary limited quantities. Release reto fl>r excavation of soil (contamlnBtlon datBcled~ See amdttlmt Release Rates: Excolllltlon and Relrievat' c/ Ccntalnera.

13/G -0 1.30E:-04 Liquid/Particulate·Solid WAC-246:-247:030(21 )(a) BetaJGanima rvlea·se rate baseCI on C.137 + P~. It Is recognized tha.t other raclionudides may be ~sent in very llmlied quantities. ·Raleaae niie 1cr·excaviition cf soif (Hlgllet contamination level, controls required). $ea oond!Uon: Re1'eese Rates:"EXC3Yat10tl &net Rebilr.VB'i"ot"eoritainers. · · ·· - · · · -

BIG - 0 6.6.0E-05 Liquid/Particulate Solid WAC 246-247-030(21 Ka) Beta/Gamma.ralease rate ba,ed on Cs-1.37 + P,_ny. It Is ,:e.cognlzed 111at other radionuclides may be pn,sent In very J!miiaci quant1~. R~ raie ·1or·axcavat1on ot'sou·cnoilfl_caifun 1.,,.1). See condition: Release ijiies: exi:avauon aru:1 Retrieval of Contalnertl.

The radioactive isotopes identified for this eniission unit are (rio qwll)_ti_ties spe1,ifj_ed):

Am -241 Am -243 Cf- 252 Cm - 244 C.s -134

Cs - 137 Eu - fs~ ~-u - 154 Pu - _238 Pu - 2_391240

Pu a 241 Sr-90 U-234 U-2~ l)-2~

Page 2 of 8 for EU_l,D 1440

U-238

The potential release rates descri~ in this Condition were used to determine control technologies and monitoring requirements for this app_roval. DOE must notify the Department ofa "modification" to the emission unit,-as defined in WAC 246-247-030(16). DOE must notify the Department of any changes to~ N"ESHA]' major emission ilnit wh~n a spe¢_ifi_c isotope.i~ <i~ly i_d_eµtj_l_ied as contributing greater than 10% of the p_otentialTEDE to the MEI, or greater than 25% of the TEDE to the MEI after controls. (WAC246-247-110(9)) DOE must notify the Department of any changes to potential release rates as required by state:or federal regulations including•changes that would constitate a significant modification to the Air Operati_ng Pi;rmit iindlir WAC I 73401-7~5(4). Notice wi)_l be providel:I a!<C()rdl;:,g to the particular.regillatfo_n iinder which notification is required. If the applicable rcgu)ation(s) does not address manner and type of notification, DOE will provide the Department with advance written notice by letter or electronic mail but not solely by copies of documents.

4) CONTAMINATION f>4OJIIITORJNG - Ro_utine B_oiindary·s~eys would be performed in addition to radiological control air monitoring and field surveys performed during the work and end-of-shift activities. Routine on-going con~ination s~eys of all cor:i~_~t~d a=.s woul_d o"cc!!r wee_l_cly. (WAC 246-247-040(5), WAC 246-247-060(S), WAC 246-247-075(8))

5) CONT AMINATlON CONTROL- Dust Suppressants Dust control or suppressants s_uch as water; fixatives, atomized misting, covers, windscreens, or weath~ en~losures will be used as necessary to minii;nlze airbclme co_r:i_t,anJ:ii)a_ti_on as de_temiined _by tl)e· Ra_diol\lgii:aJ C<in_irol orgaiii:i'.litfon. (WA(; 246-247-040(5) and WAC 246-247-060(5)) ·

6) CONTAMINATION CONTROL- End of Shift or High Wmds Spoil piles containing radiologically contaminated soii >20 dpm/lOOcl)l"i a)ph~ or> IOOCJc!p,:n/l00cm"i fieWgai11In_a_ wi)i be segr:egatel:I to the.extent prac_ti_cable from the noniadiologically contaminated soil. Containerizing spoils for disposal may be performed.Dust controls such as water, fixatives;.or'covers·will be applied at the end of each shift or when sustained or predicted wind speeds are >20mph. The fix:atives or oth~ dust controls wil_l not be required when t)!e contariiiruitel:I items are frozen, or' it is snowing, or other-freezing precipitation is falling and predicted wind speeds are <20rnph (WAC 246-247-040(5) and WAC 246-247-060(5))

7) PROCESS DESCRIPTION: Excavation and Retrieval ofContainern This approval applies to _the,se.adpiticin;tl ll!'/.iviti'°" descn,1,¢ below. N_o additfol)ll) activities 9rvariiltioris on the approved activities that c_onstitute a "modification" .to the emission unit, as defined in WAC 246°247-030( 16), may be conducted.

Work will be performed in accordance with as. low as reasonably achievable (ALARA) requirements as determined by the Radiological Control organization. -One type of configuration is a V n:Otched t;rench, con~n~s (o scil)'.IC t;renches may not have~ stackeid or·placed ii, any orderly manner for burial. The specific steps or approach to uncovering.the containas will vary.according to the configuration of the trench to be uncovered, the type of containers to be renieved, the proximity of nearby trenches or fences, the designated l_oca_tion of tJ:,_e spoils pil_e, tile pl,an;I)_ed c;xt¢nt o_f tlie soil n$ovill, ai_l_d otlier c:Ol'lsjderation_s.

Work t<> be performed within some trenches may be performed within a weather resis_tant stru~s) that wifi be relocatable along the trench. Wea¢~ enclosun.;s ¥C-efi:ectively used fcir s_imilar rcm_ediation actjvities at other U.S. Depait(l)_en1 of Ene[rgy (DOE) sites and in general industrial use. Experience during retrieval activities has shown that operational efficiencies can .be improved if the operations are protected from impacts due to weather such as wind, rain, snow, and temperature extremes. The use of a w1e1tlier resistant Cli~l6S:ure cow.d allow a l)'.!Clre effe<;_tive recovery (ro:m evc;nts (ovolvilig degi;lded con_ta\ilers and potential contamination spreads.

Prior to and during overburden removal, subsurfa_ce surveys su_c\t !IS gro~\I ~_t;ra_tjng ~a\lai, e_l_ectrom:agne_tjc (o)!uctance, and.magil_etometer lire perfoniled. These surveys provide information regarding container depth, configuration, type; and condition. They may also identify-and locate underground obstructions.

The ove$1rdeo soil will be removed to expose the waste containers. Excavation equipment will be chosen to effectively remove soil and retrieve the waste containers while minimizing damage to the ~µ,in_e:rs. Excavatj<:ir:i activities will be n;,oajto~ to identify contamiiiati<iil that might be present and to-implement controls to minimize emissions. The mo_st effici_ent methodology for removing the uocon_taminated overburden_ from th~ c<:in)a.i.n¢.i:s will i~clii~:tl)e

Pa;e 3 al 8 /or EU_IO 1440

maxiniiuil use of<:Qnveritic/,:i_al (11~ods such .. coicavatoi's, bru:khoes, fiim) ~d load_ers, brooin• (boom moiirl!e_(I}, or ~ual digging with shovels and similar hand tools. To excavate contaminated soil, hand tools predominantly wi_U be used. Remotely.-OpCr&ted vehicles may be used to minimize persolll)_el eltposure i_11 areas where high radiological arid/or chC1]lic,al hazards are discovered or antic_ipated. High eff).~ency particulate air (H_EPA) filtered vacuums inay be used for soil excavation for this application. Spot contamination reinolial wiU be done in accordance with the HEPA.filtered vacuum unit (HVU) NOC (DOE/RL 97 SO, Radioactive Air Emissions Notice of ConstrUction for HEPA Filtered Vacuum Radioactive Air Emission Units, as amended). Within the V Notched trenches, it is more lik_ely that the use of a HEPA-tilte,rtj:I vacuum to J'e!l)_ove larger quantities of soil ftoi;II_ the top surface of buried containers and soil materials in the. interstices surroundmg containers will be employed. Any use of the site wide lfVU will be performed under·the NOC applicable to the unit.

A1l es_t_imated 300 cubic meters of soil at contamination detection levels occupies the void spaces .between. the containers buried in the trenches.

Excavation activities will he·controlled closely. Heavy equipment, hand tools, light equipment, or HVUs will .be used t9 C!)!l!Pl!=!~ the sofl removal opera_rions and to access and remove the plastic and plywC>Od materials covering the containers. All containers will be·inspccted to verify integrity. The container inspection will consist ofa visual examination to detenn_ine if there are signific_a:n_t indications of corrosion, holes, dents or·other visual deformities. All containers could be moved, ni111ed, or otherwise relocated (inanuaUy or ~ith·powen:4 eqilijirntj\t, stings, clamp's, o.r appropriate rigging) to facilitate an adequate visual inspection.

The exposed containers will also be visually inspected and surveyed for contariririatioil. Eitterilally contatriinateii containers will have f'ixative applied or wilfbe decontaminated. Containers may also be bagged or over packed as ncc:<h:d. Over pa~kin:g m~ placing containers within a larger closed container. BWging or potentiaily pressurized containers will be vented as descril:,ed in PROCESS DESCRIPTION: VENTING OF CONTAINERS,

Severely degraded conta_i_ne_rs wili be repackaged or in-situ grouted. Repackaging meanS"transferring,the contents of a degraded container into a new c<in.tainer or C!ititaiilers. The eiitire contents of the cO:n!iiiner will not be soned but will be placed into the new container or containers through the use of slings, clamshell excavators, manual.labor, or m·e best available method that minimizes potential emissions.

Repackaging may include size reduction. Size reducing, cutting or disassembling material and equipment may be required to ensure personnel s~fety and/or more economical waste packaging. The process will include mechanical cutting tec_hniques su.ch as lo:w speed sawing, driUing, snippitig, arid sliearing. The ~s \'iill a~ incl~ bending and crimping- to preclude the need for cutting operations where possible.

Containers may include hut m:e not limited to drums, metal boxes, c<in_ciete boxes, fiberglass reinforced bo~es, culverts, and sealed gloveboxes. .. .

In-situ grouting will ii:iyolve gfu\1)itig a:rou;n~ a:n_d/or throughou_t the wiis_te, fil!Ch.\!Ja.t t))_e.emfi:e wast_e container~ be removed as a monolith. Retrieval activities will include appropriate disposition of sniall amounts of incidental contaminated soil (e.g., containerized or fixed in place). Larger areas of contamination could he fixed and the area posted as required by the R,aiiiologica) Con_troi organization for la)e_r dls~itioi:,.. Bulk transfer of contaminated soils for. disposal also could occ:ur.

Some co11_tainers wi_ll be assayed and, if they assay· as TRU waste; they may be further examined to determine ~hether they contain items prohibited from disposal at the Waste Iso_l_arion Pilot Plant (WIPP). Any j,rol)ibitc:)i items will be removed at a later date. Unvented TRU waste containers may be staged for venting in the burial groimds or may be trioved to the Central Wa_ste Complex (CWC) or another ~tm~t. storage or disposal (TSD) site for venting.

A numb.er of retrieved c0:11.tai.11~ are i_n good conditiO:n but are not vented. Altltougl:l _not ~.ic)ifiy trie~g t))e definition of'sealed' containers, Washington State Department of Health (WDOH) bas recognized these as closed coiltairiers such that potential emissions from these non vented containers need not be included so far as potential erii.issions spec_ific t_o y,,aste diiring rem.oval from the trenches. Oiice vtjl_ted, the coiltain_ers are inch(ded for

Page 4 of 8 lor EU_IO 1440

calculaµrig release ra_tes in NCJG 486, Pt:oc~ ~c;riptj~: Stal!ii,g of ~qieved Cp1_1)..;i_1_1_e:,:s for sW.gi_t_tg a~:d haild,li,l,g oj>eriitio11_S. ¾, es_tµiiat'1(1 arin_ual maximum of.15,200 verited containers ofwilste will be managed during the peak-years of this project

Cgn_ajt_t_c:rs ~y be:s1;igi,_d in.\!!~ bu;ria_l gro@i!s ~ding furth_¢' prQ!:CSsiiig or trat_tsfer. Waste containers ~e considered retrie,!ed once llilllsferredto an approved TSO facility. (WAC 24&-247-040(5) and WAC 24&-247-060(5)) . .

8) PROCESS DESCRIPTION: Venting of Containers T!Jjs appi:ova_l ilpp_lies to ii!~ a_dµitiO)la).activities d_escn),ed b_clow. No addit1onal a¢.ti-vit_i_es.or vanatfo_ns on the approved activities that constitute.a "modification" to the emission unit, as defined in WAC 246°247--030( 16), may be conducted. ·

All work will be perfom1ed to meet ALARApractices and will be conducted.according to·applicableoperating procedures, rad·iological control procedures, and radiological work permit (RWP's). · Vc:nt t}l.t¢rs "'.i.11 cotit~ue !o ~ i_(lsta))t;d in d~ignated coil_tailiers vi:a one of the djii):iJ. vet'ttiiig systeitls dcscfi~ in this process description. These systems will ensure personnel and environmental protection.:.The-methodology will require penetrating the container and inserting a vent Penetration of the lid will be accomplished by either drilling tl:m'nig], the lid _or P).in¢ni)i\lg the lid wit_!) a filter dart (using Datt Systejn). CO:n_tai,1,er venting systems are desct(bC!I in thefollowing text. Designated drums slated for venting willbe vented with the Mobile Orum Venting:System (MDVS); Drum Venting System 2 (DVS2),or.other venting methods. (WAC 246-247-040(5) and WAC 246-241-060(5))

9) ABATEMENTTECHNOLOGY: Excavation and Retrieval of Containers The administrative control points·set iii this emission unit for contamination, as monitored by stmdard radiological fie_l_d_ i$);riimtjl!a#on, W\il he '!Se~ to boijµd tj:Iiissio)'is ba,;ed on ci(rr~t efli.c.ien~ies of typi!')ii RM¢o(l ~eld contamination instruments.

The c:i)_n.tt:~ls (istaj ~tliin t_l)j_s approva_l iipply._t_o T~U Wl(s!~ ~etit\iva) Project oi>C:I! air "":c.a_viµio1_1 @~ re/tjeval activities. (WAC 24&-247--040(5} and WAC 246-247--060(5))

10) RELEASE RA TES: .Staging of Vented Containers A maximum of 15,200 vented cot_ttainers of waste (inchidi!lg TRU waste con\~iners, contain_ers iha.t are not desigmited as TR,U was_te, il;nd t_h_ose which coilld be ie_ttieved wit!) veiits in place) will lie retrieved per year: Once vented.,.the containers will be staged with the other retrieved.containers for further handling, resulting in.the staginglstorage of a maximum of l 5;200 vented co_nt_ain~ pc;r year at th~ LLl3G. Using a release fractiqn of 2-.0 E-09 for fugitive emissions frbii) vetited c.oritainm (as used iii Radiciactiye Afr Eririssio/ls N~ce ofC_oilstructi_Oii Application for ·the Waste R.eceiving•and Processing Facility, DOF.IRL 2000 34), the predicted release,rate from the staging of vented containers wi;hout any emis,sions con~i equipment is-6. IE--04 <;ilyr, with 3.8~5 Ci/yr attributed to Am-241 +Pr\Jgetiy (representi,l,g t\Jtol alpha) and 5_::rE--04 Cf/yr attnli)ited to Cs-137+Progepy (representing.total beta/gamma). No credit is.taken for abatement; therefore, the predicted-abated release rates are· assumed to be the same as the predicted unabated relel(s_e rates. "cw AC 246-241i--040(~) and WAC 246-247--060(5))

11) RELEASE RA TES: Excavation·and Retrieval of Containers To d"e_iefuiine t)je cprrest,oiidi~g s~ii cptic~triiti~ fu·p/~ries P!:r grain of individual radii:>iiti!:~des, ccinver.ii\lh factors, as developed in HNF 2418, Soil Contamination .Standards for Protection of Personnel were used. The average soil density was-assumed to be 98 pounds per cubic foot The beta gamma contributii:J.g radionuclides were l!)I~~ \o be r~r~:~!ed by ¢esilll1!, 137+Proge!jy Sl)_d ti(~ alp!;# <;;ontti~iltiiig ra.~i)>tiil¢(i_i!_es w<ire·asslil;:l~ !.o be represented by Am 241 +Progeny (predominant alpha contributing,radionuclide in the soil is unknown; therefore, assumption of Am 241 +Progeny will produce the most conservative:dose consequence). The respective volumes ·of con~ted soil (i_.~_,, 300 i:t_t,':i, 3 tn"J, 8!14 0;3 111AJ) llt t_h¢ t_~ c(it_ttaJIJ.ioa_tiol). l_ev~is.a,e c~~i.#red as ~l~C!_l during maliual excavation, using a release fraction of LO E-3.

The esti@lted":iOO m3 ofs~il i,J, contact wi_th tlie co1_1_taiflers is assumed to be C9n_tlin:ii_riat~ at det~b_le levels (100 dpm/100 cm2 alpha and 5,000 dpm/100 cm2 beia/gamma direct readings based on past operations and the pilot dig). A smaller percenfl!ge (I%) Qf th~ COl)._tll/l)!llll)t:;d so.ii (i.e,, 3 Ill}), is assUl(1¢ to be CO!)tamih~ at higher leyels (2;000 dpm/100 cm2 alpha·and 100,000 dpm/100 cm2 b_eta/gamma). Contamination at notification leyels (28,000 dpm/100 cm2 alpha and500,000 dpm/100 cm2 beta/gamma) is not expected. However, as a-contingency planning estimate, 0:1 % of ihe con!BiJljoated soil (i,e., 0.3 1)13) is ·as_sum:ed to Ix: co11~ed at no_t/tic_a!ign Jevels (WAC 246-247-040(5) and WAC 24&-247--060(5))

Page S'of 8 for EU_ID 1440

12) REL~E RATES: Da,:t and Qt),.cr Venti.l:ig Sys_~ A rila,i;iinuin of-4,200 .containei's per year will have installation of Nilcfil® or equivalent filten using the Dart or FRP System.s .. A conservative. time estimate for pressure release,during each installation is I hour. Using a release fraction of 1.0 E-3 for particulates and a time factor of 4.8E-Oi (60 minutes per container multiplied by 4,200 cot,_1/!iAers and divided by 5t6,000 m.inu~ pej" ye.a:,-), tl)e iifedi~ release riite (iinabated) froni using the Da)'I of FRP System for installation ofNucfil or equivaleni filters without any emissions collll'OI equipment is 9.6E-03 Ci/year. Following installation ofthe·Nw:fil or equivalent filter, the emissions,are routed through ihe HEPA-type Nucfii or equivalent filter (cl;rtifi"'199.97% removal et[iciency); then:fore, theJll'ec(licted rel~~ ,:,*'·(abattjl) wi_ip emissions coiltrol equipment is 4.SE-06 Ci/year. The predicted release rates for the representative radionuclides Am-24l+Progeny and'Cs-137+Progeny are,as follows: Unabated PTE; Am-24t+Progeny 6.0&0i Ci/yr. : Cs-t37+Pr<>geny A~ted PTE; Am-241+Pfugeny 3.0E-07 Ci/y : Cs-137+Pfugeny (WAC 246-247-040(5) and W AC246-247-060(5))

13) WOOH NOTIFICATION, Implementing PES orNGR.Containment

9.0E-Q3 Ci/yr. 4.5E-06 Ci/yr.

DiJJ:ing big() h¥ard work actjvit_i,;i;, rem.ovahl,e smface contaniiriatiO:n is maintained less !hail 2,000,000 t;lp(l)/100 cmA2 alpha and/or less than 4 rad/brJIOO cmA2 beta-gamma, liniited to a I ft~2 area. For an allowed increase in contaminated area footprint of 4 ftA2, the limiting condition for removable contamination will be 500,000 dpm/100 cmA2· al· ha and or trad/hrJIOO cinA2 beta- .. . Exceedin ari of these contarniruition Iiinits will · ··ire work . . . p . . . . . . . .. . giµm:na_ . . . g y . . . . . . . . .. . . requ to st~p. arid notification to Operation and RadCon management in accordance with the RWP. Notification to WD()H via email or the established procedures in the Envininmental Notification program will be required. For work' to con.ti.nue above ·any qf l)l~e limiting radi_ologi~ co11ditiot,_s, the NG.R c:Ontaini:I)!=llt sys~ or· th;e PES and coriimensur.ite controls will be implemented. The NGR containment or PES exhaust system will be utilized to minimize the potential for contamination spreads outsi_de of posted radiological areas. (WAC 246-24 7-040(5) and WAC 246-247-060(5))

14) wbo(I NOTIFICATION -Tr(llisjtion to High Haiaid Work Package During medium hazard work activities, removable:contarnination will be maintained less than 20,000 dpm/100 cm"2 alpha and/or less than 1,000,000 dpm/100cll)"2 beta0gamma and the n;r,:t!)vable contamination area limited to 4 f'\A2_. E.xc.~l'lg t'1cse (im.i'-6 ~ill r.""1uire Work to stop, and riotificli_tiO:n to Oi>,enitlon and RadCon management in accordance with RWP .. Notification to WDOH via eoiail or the established procedures in the-Environmental Notification program will be required. For work to continue above th~ lunitj_ng radiological C!)ricli_tjons, the highhazl(rd woi;l<: pa_ckage and a_ssocia_t_ed c:Ontrols shat.I be implemented. (WAC 246-247-040(5) ail_d Vf AC 246-247-060(5))

15) WOOH NOTIFICATION - Drum Vent Failure The department shall be l)oti(i_ed vi.a email or tli~ ~ta~ljs~.e4 p;oc~µres in t:(i,e El:,:yirOIIJl\e.t:118i Notjfii;atjon progrli!'fl widiin 24 lio.uis of all driJni. vents that fail to be installed properly and smears show >2,ooo· dpm/100 cm~2 alpha .or > I 00,000 dpm/100 cmA2.beta/gamma removable contaminaiion (an example of a "failure" ka pressure release that blo\lVS past the seat of the boot or a de_tlagrlition), (WAC 246-247-040(5) B!ld WAC 246-24'1-060(5))

16) WDOl:i NOTIFICATION - LO:ss ofCO:ritilinmeiit WOOH will be notified per WAC 2~6-247-080(5) via email.or the established procedures in the Environmental Notification program if a loss of containment occurs ( dropping, spilling, puncturing a container; or otherwise encountering loss of integrity wh~ contamination ~_apes cont\liniJ!e.t:1.t), wi;i)_tji c.J!.~ I 00,000 <!pm/I 00 cmA2 beta/ganinla or 2,000 dpm/10.0 ciii"2 alpha removable coiltattiinatiori. (WAC 246-247-040(5) and WAC 246-247-060(5))

17) WOOH NOTIF!CA T!ON - Transitio_n to High Hazard Designation During soil removal activities, if di_rect contarninatiD!) rc;adi_!)gs f<lr the ge:i:(!;l'lli are.a is greater than 2_8,000 dprn/100 cm2 a_lpha <# greater than 500,000 dpm/100 cm2 ~a-gamma, work will stop,.the environmental con:ipliance oflicer,.RadCon Management and WDOH will be notified via email or the established procedures in ihe Environmenta_l Notification progrBitl, ~t;I the col)~(s I.is~~ im:,0¢.dia_tely belo"'., implemented. Once notifi.cations have been made and the following controls implemented, work may resume. under high hazard designation: .a. Soil will be wetted prior to soil removal; and soil will be maintained damp during soil removal, B. Ga)~ a,ea wo,:iH,tace ~ sampling will be p¢rfoniied. (WAC 246-247-040(5) and WAC 246-247-060(5))

18) ALTERNATIVE APPROVAL .- Unabated Emissions The pot!#)ti.al iln!l):,a_t_ejl dose r,ite froi:n inai)ual exca'vation is 7.5 E-4 l)'lrelli/ye_ar. No credit is take~. for abatement; therefore, the abated emissions are assumed as the unabated emissions. Although fixatives and similar controls will

Page 8 ol 8 lor EU...)D 1440

be emplo~ for the high.,,- cont;i:minati1>11 l_ev~I and 11otificati1>n leve_I co11!BJ:!!inati<i11, no ~it is.being tak¢n for abatement; therefore, the abated dose rate is·the unabated dose rate. (WAC-246-247-040(5), WAC 246--247-060(S), WAC 246-247-075(4j) -

19) ALARACT APROV AL • Container Handling The process for handling of abnormal or severely d_egraded containers.as desci:ib_ed.in Proces~ I;)es<:ription: Excavation Apd Retrie-:al of Con~in!'B, for bagging, over packing, pla_c:u:ig d,egraded outer container contents into replacement cpniaincrs or-in-situ grouting is-approved as meeting.ALARACT, and these processes and associated records and procedures will be subject to inspection upon request by the depanment. (WAC 246--247-040(5) and WAC i46--247-060(5))

20) AL TE.RNA TIVE APPROV AL-WDOH NOTIFICA TION-Administratiyi: Co_ntrol on Emissions WOOH accepts the method proposed.for calculating the estimated dose with the:limitation.that the-annual release of the sum of the fractions-of the curies-~leased/annµal release cannot ex.~eed .a val_ue of I for a)phi!Jbeta p!U6 gam,:,:ia:rele$e. The limit <i11 annual release shall not exceed 2.1 E-2 Ci/year using Am-241 +D as·a representative for alpha calculations and LI 5 E() Ci/year using Cs-137+O-as a represenlativeJor Gamm·a calculations, collected al a point not to exceed to meters from the work area of disturbed material. WDOH_ w{(l be O:otifieq when the sum of the fi:a¢tions reaches a value of0.8 representing 0.08 mrem/year 10 the MEI, and additional controls will be initiated 10 ensure that the dose.to the MEI does not exceed 0.1 mrem/year. Workplace-air sampling will be· conducted when performing w~

21) CONTAMINATION CONTRPL · Limits to i/!i_ti_lite NGR <ir PES Adheren_ce to contamination limits-in ·the.immediate work location for-mediwn and higb,hazard work will help ensure that the work:area·nirbome radioactivity limits (i.e., 1.0E-69 µCi/ml for alpha emittcr,rand 2E~6 µCi/ml for beta-~ ein_i_ners) are not ex_Ci:eded. (WAC 246-)47-040(5) and WAC 246-247-060(5))

2_2) CONTAMINATION DOCUM_ENT ATION. E~posed Packages During repackaging activities {i.e., when.transferring the conients of a degraded container into a new container or containers) an operations log will be.kept noting corniitions of the transferrlld contents/pac;kages .. RaciCon will ~_e_11!_1_e ~-d retain ra_diol_ogical i'ecoids docu~_ei:iting·air-sample results ail"d removable contiuiiiriation conditions during-retrieval of each container. (WAC 246-247-040(5) and WAC'246°247~60(5))

23) CONTAMINATION CONTROL • Function Check Misters and Sprayern Atomized misters an!l ~live spr:ayc;,,; wi{l be i)in~tio1_1 c_l;t~~-e!i a_t i,ie work si_te prior to co~nu:n.ci,ng work activities. (WAC 246-247-040(5) and WAC 246-247-060(5)) -

24) CONTAMINATION CONTROL· NGRIPES Activities Activities done under confinement strueture of PES and NGR wift be considered 1_0 be diffuse and fugitive a~tivit_ies tinl_ess uo:d_er active vtjltilatio_n condi_ti_oiis. (WAC 246-247-040(5) and WAC 246-247-Q60(5))

25) CONTAMINATION CONTROL • Soil Excavation Near Containers Manual methods or HVU will be used to excavnte soil in close proximity to containern. (WAC 246--247~0(S) and W A_C 246-247-060(5))

26) CONTAMINATION CONTROL· Transporting Waste Packages Radiological rnntamination and dose rate monitoring will be conducted prior to transporting any waste containers. All waste-will be contained as·appwpriate for transport, Covers such as tarps or plastic will be placed over dete,{orat/:d cor11_ai_nt#S a_ul;te e.i:i.d o_f ~ch sl;t_i_fl_. These practic~ of nioO:i_toring, container integrity inspe¢tions, lin!i p_lacemeil_t of covers will C!]Sure go_od contamination c_ontrol practices are o_bserved during package handling activities, .soil removal ( excluding overburden removal) and over packing activities and when placing degraded outer container contents into replacement containers. (WAC 246-;247-040(5) an!l_ WAC 246--i47-060(5))

27) CONTAMINATION CONi:ROL • Bulk Tr$.~fer of ¢011):an).inattjl Soil The soil surface will be weired prior to bulk transfers of contaminated soil. (WAC-246--247~0(5) and WAC 246-247-060(5))

18) CONTAMINATION CONTROL· Wind Sp~ Work perfoi:rn~ oii_tside (eil:ciivation and/or container-retrieval) will stop if a"erage wind speeds exceed I I mph during the work and Contaniination Area cir Airborne Radioactivity Area conditions exist. (WAC 246-247-040(5) and WA~.246-247-060(5))

29) CONT AMIN.A TION CONTROL • Limits ti> Trigger: Further Airborne Controls Radiological field survey monitoring will use set points for removable surface contamination levels of> 1000 dpm/100 cm~2 b<:ta/ganuµa and >jO dpm/100 c:rn_~2 aipha to \riggtj' tl;te 11.~ t_o furth¢r evalil;ate ~.irbome C:ontrols cir tjaluate further preparation of materials for-release. (WAC 246-247-040(5) and W AC.246--247~60(S))

Page 7 al B ror EU_ID 1440

30)

31)

32)

33)

CONTAMINATION CONTROL - Soil Slirv · Duiin TRU Retrieval ' . . . . . . ' ' . ' eys_ .. 8 ' . ' . . I)uriiig excavation activities for retrieval, excluding activities SSS<J!:iated wi.th removal of soil overburden, radioactive contamination monitoring for·diffuse·and fugitive emissions will consist of soil surveys lit least hourly for both 1/,lpha iln!f be.r;i/gamnia con.tam..inaJ.ion dur{ng TRU Wast,: il~eval op~#oils., (WAC 24.6-?4 7-040(5) and WAC 246-247-0.60(5)) CONTAMINATION CONTROL "Removable-Contamination ·survey IJoth Aipha and beta,gamina cpntamination fJe.ld surveys shall. be pc:rfm:m~ f!J.r all ~9val,le co.ntaminatio1.1 &llrVtjs, pi:ior t.(:> '!!Id dJirii)"g s<i{l r1?]16Val (ex.clu)!ing ove;biirdcn n:i!l6Va)) and ove;pa~kil.lf! ~cr;:vi.ti~ ll)ld \Vh"!l placing degraded outer container contents into replacement containers..Alpha surveys !!hall be performed for dire¢! readings of container surfaces. Beta/garmna direct readings.may be influenced by container contents< so·are not as usefjll '!!Iii are not requ)red, (W '1.C i46-:z47-040(5) an!f W AP246-i47-060(5))

- . . -CONTAMINATION CONTR_OL - Fixatives Fixatives or other controls will be employed if removable contiunination levels exceed 100,000 dpm/100 c,iiA2 beta/gamma or exceed 2,000 dpm/100 cmA2 alpha. (WAC 246-247-040(5) and WAC 246-247-060(5))

CONTAMINATiQ)-1.SAM.PLING • AM W<>rkp~ airs_l!DlPling at tlte work sit.e ~ter (on~ four sick,s of the work l~~n) ap.d d!)wnwind of the contairier work location will be conducted w_hen p¢rformingwork in an Airborne Radfological Area, providi.ng ea,i:ly i!J.!fi~ation cif potenti.~I eleva.~on (I.I work s_ite ~J.llete.r ,jj-borile l'.114ioactiV1ty. (WAG 246-~4i-040(5), WAC 246-247-060(5), WAC 246,247-075(8)) .

Pago 8 af 8 for.EU_ID·1440

STATE OF WASHINGTON DEP~TMENT OF ~TH

ENVIRONMENTAL HEALTH PROGRAMS OFFICE-OF RADIATION PROTECTION

' In Re The Approval of: %S:.DA Y'DkAFT APPROVAL OF NOTICE OF CONSTRUCTION (NOC) io.42 ... . .

Approval No: AIR 16-1110

lJIE STATE OF WASJJINQ_TON TO:

Docket No: REQUEST FOR Al)JUDICATIVE PROC.EE.DJN.G

M ;-_ .. Doug Shoop, 111ax,a~r United States Depa:rtmeiffor En:e;-gy Richland Operations OIJJ~ P.O. Box 550, M_S:IN: AS-14 Richland, Wasblligt.on 99352

If you wish to request an adjudicative pr~ you_ or .yoi!f a):.10:rriey r:nii:st COMJ'LETE AND FILE THI.S FORM OR A DOCUMENT PROVIDING SUB ST ANTIALL Y THE·SAME INFORMATION WITH THE DEPARTMENT oF HEAL TH Ai>rutiicA TIVE sERvkil DN1i' ·WITHIN TWENTY-E1Gt1T(is> DA Ys oF YOUR RE<:EIPT ofthjs Request for A~udicarive Pro~ing form a)tjl a alp)' of the Office cif'Rltdiatlon . Proh:Ction's approval.AIR 16-IHO.

You musi file yOW'-appiication in a manner that slici:w, proof of service on the A.dji/dicativ~ Servi!:e Unit, lit the following address: .

Depar_trnent ·of Health Adjudicative Semce Unit 310 israei Road·s.E. P.O. Box 41°879 Olympia, WA 98504-7879

With your appli_cation, you m~ lncl)lde a copy of the Off"ice o_fR;idi!it_i_on. Pro!f!<:tion's approvai.

FILING SHALL NOT !IE DEEMED COMPLETE UNTIL TIIE ADJUDICATIVE SERVICE UNIT ACTUALLY REc:1IVEs·voiJR APPt.1cATioN.

YOU HA V£ THE RIGEIT TO a formal hearing in this matter cond1icted(':111Suaiit to Jl.evi~ Code of Washit)gton (RCW) 43.70.11 S, Chapter 34 .. 0S RCW, and Chapter 246-10 cifth~ Washington Adlnin_istrative Code (WAC). AlternativeJy, you may waive the formal hearing lind sub:niit a ~eil staten).~! and •!JPportjng dpcum~ts sc;ttiDg out your poi;ition, your defenses, and llllY mitigating circilms~ that you wis~ Ii> bririg to 1\1:e !)epartm,mt's attention.' · · You have the right to be, ,epic$ii..d by Bil linomey a.t. your own l'JipeDSe.

~

J I WILL BE represented by an attorney. His/her name, address, lind p_!:1one n((mber are:

Nlitne:

Ad_dress::

Phone:

Request for Adjudicative Proc,ee_dirlg Page I of 4

I I WI_LL NOT BE represented by ari •ltor!>•Y.

ij ajlenuJ,_milting lhu reques~ you.obtain attorney repraentation or change attorneys, you must notify tl]e Adjrldlcative Service-Unit- - · ·

II.

I I DO. NOT waive my rigl\t to a fO:mial ¥1iril)g.

J I DO waive my.right to a formal hearjng. I understand that ifJ1"'lliv~ niy right~~ ~onn_al hcarirag, thc Depanmcmt may decide this. J!l!ltet solely with ref~ce to in_fonnalion bi the Depamne_nfs possess_i_on W!_d i<l su_cll wri~_en s_tatemerits and s~g docµmerits m I riiay liave submitted.

ffyoQ choose to waive your right to a f~ ~ p~e COf!IP~ the following:

[ l l AM NOT subniitting documen!S to the Department in support of my position.

] I "-M · sµbmi)t4ig a-sworn sta1.ement_ Bild/or o_ther. do<:WDcmt;s to the Department ill support of my position. Instructions - Please ~i!=Bl,: your responses below:

If you are submitting documents to the Department, please list and briefly icknlify all such documents in the space provid= below and on any additional sheet.that may be ilecessary ..

Request for Adjudi~_ve ~~ding Page2of4

IIL

ADMISSION/DENIAL oF cONDmoNs _9R LtMrr ATtoNs Th~ Offi~~ of~~i.atjon l'ro~<>li's approvai AiR 16-lli0, ~ Novembe_r 17, ~016, contains conditions and l_in:,._itaµons set out as m1i:n~_red pa,ragrap_h,5. _ In the,space belo_w you must incl_icate, in good faith, whether you admit, at do not c_o:nt"!'I, <>r W!l)Y _the cgndilioils or limitations. Cond_itions _or limitations denied or not contested may later be 11$litted. Co:Qdi_tj_ci"1S or limitations l\(lmitted or not contested shall be conclusively deemed true for further ... eed". P!IJC. m~.

Instructions: I admit, deny, or do not contest ilie conditions or lim\u!tiol)s a:s follows (611 in the appropriate paragraph number): ·

Paragraph __

Paragraph __

Paragraph_. __

Paragraph - .

Paragrapl;i __

Paragraph.~

p .. h aragrap --

P eragra(l h -

Paragraph __

Admit

[ 1

[

[

1

1

l

~ [ 1

[

1

l

l

[ 1

Do Not Contest

[ 1

1

1

[

.1

[

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Piease attach any additional sheets that may be necessary to respond to all allegations.

If you have "1)osi:!l.l)O! to Vl'aive YO\!T rights.to a f<>rmal liearing, please state all groun!is fo_r contesting this matter in 1/l!: space provided below and on wiy additional sheelll that m_ay be necessary.

~eqii~ for Adjudicative Proceeding Page3 rif4

IV.

You have the right to liD iriterpreter, appointed at 110 cost, ifyoil ore a liearing impaired p_erson cir limited English speaking pe,son. If lilly wimess for you is a hearing iinjiaireil person or a limited English ~g person, lin interpreter will be appointed lityiii.ir-_experise.

I [DO] / [00 NOT] ( circle one) request an i!lterpreter be appointed. If lin interpreter is requested, please indicate the per.ion or persons for whom an interpreter' is required· iinil their primary Iaiigwigi:, anil/or"whcther they aie hearing impaired.

IF YOU FAIL TO FILE YOUR APPLICATION IN A TiMEL Y MANNER, OR IF YOU FILE YOUR .APPLICATION TIME!. y BUT FAIL TO APPEAR AT ANY. SCHEDULED . -SETTLEMENT CoNFERENCE, PREHEARiNG CONFERENCE, OR HEARING WITHOUT w'vfrooo so, TIIE DEPARTMENT MAY Dlk°iDE THIS MATTER WITHOUT YOUR YOUR PA!{Tit1i>i\f10Jii AND WITHOUT FURTHER NOTIC°E TO YOU.

DATEDtbis. ____ d_ayof ________ ~----

Party

Party's Representative (if any)

WS~A #:~---~~-~~-

Request for Adjudicative,Proccedillg Page4 of4

Extra o es s (check box. sao tea 0 Renim Recolp! {lwdcopy) S -d-'----1µ~ I

:;; D Retum Receipt (alae!rcnlc) Pos1mo.rl< D QCertlflad MIiii Rontnctad Delivery $ ____ _

D OAdull Slgnolure Required $ -----

QAdull SlgNmUe Restrieted Delivll:ly $

LO Sent To ,'I c:, -- ---·--- --- --. --- ----· .. ----- -------..... I"'-

CifY·,"SilJii,~"tfP+4•·----------------------------·-····---------------

1·-,-_, - - ---------------J

11 Ccirnple_te lt~m~ 1, 2, ~nd 3. Iii Print your name and address on the reverse

J so ttiafwe C<ii) returii ttie c:j,rc!'to you. - -I a Attach this card to the back of the mal!plece, 1 o,·on tl18 front if Space Peil'Tnits.

1.:~Art!cle Addr8SS8d to: ________ _

Mr. Doug Shoop, Manager Unrted States Departrmint of Energy Richland Operations Office PO. Box 550, MSIN: AS-14

-Richlan·d. WA 99352

1111111111111111111 II I II II II I II I I lrn 111111111-9590 9402 1337 5285 0588 41

3;·serv1ciiType --,'Y.J7i:f'"o -- M.ue.iiress® D~ultS!g~re . ~ ogl:rtaredMalln1··· D Adult S/gnature_Restrfcted 0ellvery O Reg!stoied Mall Restricted o Certified Mail® · · eenvery D Cortlflod Mall Re:'.ltrtctocl Doi Ivory· D Rotuin Receipt tor D Collect on Dellvery Merdlan_dlse_ .

-__ -,o,-_-,-ri-,.-,.-~-,-,~-,,.,.--,rr;~~-n-•"'~"-m_m_••_ro_;_'°~,.-,,.~,-, -_-__ -_-_-_~_--l O Collei:t: on Dellvery ROS!rlctod Oellvmy D Slgno.tum Conflrmo.tlonru :

7015 0640 0007 5050 7838 ,radMoll- OSlgo,n,,eCoafim>olloo Jrecl Mall Aestrtctecl qurlvery Restricted De!Mlry

: PS-Form 3811, July 2015 PSN is:io-02-ooii-9053

J

5

STATE OF WAS.HINGTON

DEPARTMENT OF .HEALTH OFFICE OF RADIATION PROTECTION

3_09 Bradley Blvd., Suite 201 • Richland, W,1shin'gton 99352 TDD Rcfay Service: 1-800-833-6388.

December 23, 2016

Mr. Doug Shoop, Manager Uni_ted States Departme11t of Energy Richland Operations Office P.O. Box 550, MSIN: AS-14 Rich_la,nd, Washington 99352

Re: Final Approval of Notice of Construction (NOC) 1042

Mr. Shoop:

AIR 16-1226 NOC 1042

Pursuant to Chapter 246-247 of the Washington Administrative Code (WAC), your modification was approved on December 19, 2016, according to the enclosed einis:Siori ililit (EU) specific license for:

TRU Waste Retrieval Diffuse and Fugitive Operation (Replaces NOC 804) (NOC 1042, EU 1440)

The conditions, controls, monitoring requirements, and limitations of this license must be observed ii!- order for you.to l;,e in compliiµice with WAC 246-247. Fail.· ure to meet any provision

. '

of this license may result in the revocation of approval, the issuance ofNotices of Violation, or other enforcement actions under WAC 246-247-100.

If yoii have any questions regarding this approval, please contact Tom Frazier at [email protected]!ov or, by phone, at (509) 946-0774_,

&Jt ~JobnM,rtol6tt,t-&r--

Radioactive Air Emissions Section

Enclosure: NOC 1042 for EU 1440

cc: (see next page)

Pub_lic Heallb - Alw,1ys V\lorking !or J S.iier and HeJlthicr W.ishingtun

<l>ci@<," 0

!'vfr. Doug ·shoop . December 23, 2016 Page.2 of7

cc_: R11th Allen, WRPS Matthew Barnett, PNNL Lilyann Bauder, Ecology Shawna Berven, WDOH Lucinda Borneman, WRPS Lee Bostic, BNI Frank Carleo, CHPRC Cliff Clark, USDOE-RL Jack Donni:_l_ly, WRPS Rick Engelmann, CHPRC Deiiriis Faulk, EPA Thcirws Frazier, WDOH Eric Faust, USDOE-RL Gary Fritz, MSA Phjlip Gent, Ecology Reed Kaldor, MSA Paul Karschnia, CHPB,C Jiln McAuley, EPA John Sclunidt, WDOH Jeff Voogd, WRPS Environmental Portal RAES Tracking: Line 16-154; EU 1440; NOC 1042

AIR 16-1226

Emission Unit 1D: 1440

200W 200 Area Diffuse/F11gitlve-TRU Retrieval 200 Area Diffuse/Fu2itive-TRU Retrieval This is a MNOR, -FUGITIVE, no~-point soun:e emi~sion unit.·

TRU Waste R~ev.::al

Abatement Technology BARCT WAC 246-247-040(3), 040(4)

state only enforceable: WAC 246-247-010(4), 040(5), 060(5)

Aba_t~men_t Tec~:Ology Required# of Units

Monitoring Requirements _ _ _

Additional Description

s_tate enforceable_:. WAC 246-247-040(5), 060(5), and federally enforceable: 40 CFR 61 subpart H

F edernl and State Regulatory

WAC 246-247-075[2]

Monitoring and Testing Requirements

40 CFR 6 I, Appendix B Method 114

Radionuclide, Requiring .Measurement

Each radionuclide that could contribute greater than IQ% of the p~tenti;;!~to.:emit TEDE to the MEI, greater than 0.1 mrem/yr potential-to-emit TEDE to the ME~ or gr'eakr thBn 25% of the TEDE to the MEI, after controls.

Sampling Frequency

Per the sitewidC amb.iCnt ~Oni'tOring program.

Sampling Requirements Per the sitcwide ambient monitoring program, samples will be c_ollected from the ex_ist_ing ne_ir-fac_i_lity monitoring stati_ons.

AddillOllal Roquirements

Sec Section S of the general conditions in this license for additional inronnation,

Additional m6nitorln-g or sampling reQlJirements established by this License will be listed in the Conditions ~nd Limitations section, if applicable.

operado·o_a_l s_~a:t~s

This Emission Unit has 1 active Notice(s) of Construction.

Project Title

TRU Waste Retrieval Diffuse and Fugitive Operation (Replaces NOC 804)

Approval#

AIR 16-1226

D_ate Approved NOC_ID 12/19/2016 !042

Conditions (state only enforceable: WAC 246-247-040(5), 060(5) if not specified) I) The total abated emission limit for this Notice ofConsmiction is limited to 3.90E+0I mrem/year to the

Maximally Exposed Individual (WAC246-247-040(5)).

2) This app_roval appiies to those additional activities described below. No additional activities or variations on rh_e app_roVed a:Ctivities that coristitute a '1mod.ification" to the emission unit, as defined in WAC 246·247· 030(16), may be conducted.

Transuranic waste retrieval involves the processes for removing and disp_ositiOning buried Suspect t_.ryins_u_ranic mixed low-level radioactive waste (hereafter called TRU waste) from Hanford Site burial trenches for storage or disposal at other approved locations. Dispositioning is the orderly administration and handling of waste (in:clu_din:g contaminated soil) from the low level burial grounds to place it in approved storage or disposal status. The handling includes such actions as_: packagi_ng, labeli_ng and tracking waste; venting, assaying, and staging waste; inspecting waste and waste staging areas·; sampling/characterizing/designating waste; maki11g arrangements for the transfer of waste; completing necessary paperwork; and perfonning radiological and/or in_dustrial hygiene surveys.

See the follo,ving emission units for a detailed description of additional coritrols/coriditiiins and limits under this approval: EU 455 HEPA Vacuums EU 486 200 Area Diffuse/ Fugitive; Operat_i_on of the Transura!'ic Waste Retrieval Project

Page 1 of 8 for EU_IO 1440

EU 755 EU 756 EU I 181 EU 1322 EU 1326 EU 1327

Mobile Drum Venting System (Active Ventilation) (MDVS) Mobile Drum Venting System (Passive Ventilation) (MDVS) Categorical Drum Venting System 2 (DVS2) Portabl_e Enclosme·System #I (PES) Vapor Extraction System (YES) Next Generation Retrieval (NGR)

3) The PTE for this project as detennined under WAC 246-247-030(2 l)(a-e) [as specified in the applicati_oq] is 3.90E+ol mrem/year. Approved arc the associated potential release.rates (Curies/year) of:

Alpha - 0 8.30E+OO Liquid/Particulate Solid WAC 246-247-030(21 )(a) Alpha release r3t8 based on Am-241 + Progeny. rt is recognized that other radionuclldes may be present in Very limited quantiti8s_. ·Rele"ase ra1e for the o·pel'atioii of NGR containment systeni and portable enclosure system (PES). See Condition ReleaSe rates: NRG containm-ent System and portable enclosure system PES.

Alpha-0 3.BOE-05 Solid WAC 246-247-030(21 )(e) Release rate based on Am·241 + Progeny. It is recognized that other radlonuclidcs may be present in very limited quantities. Release rate for staging/handling vented containers. See Condition Release rates: Staging of Vented Containers ..

Alpha -0 6.00E-04 Liquid/Particulate Solid WAC 246-247-030(21 )(e) Alpha release rate based on Am-241 + Progeny. It ls recognized that other radionuclides may be present in very limited quantities. Release rate for installat6ion or Nucfil filters using the Dart System. See condition Release Rates: Dart ar:id Other Venting Systems

Alpha - o 9.60E-05 Liquid/Particulate Solid WAC 246-247-030(21 )(a) Alpha release ~ate based on Am-241 + Progeny. It Is recognized that other radionudides may be present in very limited quantities. Release rate for excavation of soil (contamination detec_ted}. See condition: Release Rates: Excavation and Retrieval or Containers. ·

Alpha-0 2.00E-05 Liquid/Particulate So_lid WAC 246-247-030(21 Xa) Alpha release rate based on Am-241. It is recognized thal other radionuclides may be present in very limited quantities. Rel8ase rate for excavation of soil (Higher contaminalion level, controls required}. See condition: Release Rates: Excavation and Retrieval of Containers.

Alpha - 0 2.70E-05 Liquid/Particulate Solid WAC 246-247-030(21)(a) Alpha release rate based on Am-241 + Progeny. It is recognized that other radionudides may be present in very limited quantities. Release rate for excavation of soil (notification level). See condition: Release Rates: Excavation and Retrieval of Containers.

BIG - 0 1 :soE+OO Liquid/Particulate Solid WAC 246-247-030(21 )(a) Beta/Gamma release rate based on Cs-137 + Progeny. It is recognized that other radionuclide_s may be presenl in very limited quantities. Release rate for the operation of NGR containment system and portable endosure system (PES). See Condition Release rales: NRG containment System and portable endosure system PES.

BIG - 0 9.00E-03 Liquid/Particulate Solid WAC 246-247-030(21 )(e) Beta/Gamma release rate based on Cs-137 + Progeny. It is recognized that other radiorllldides may be present in very limited quantities. Release rate for installation of Nucfil fitters using the Dart System. · See condition Release Rates: Dart and Other Venting Systems

BIG - 0 5.iOE-04 Liquid/Particulate Solid WAC 246-247-630(21 Xe) Release rate based on Cs-137 +Progeny. lt is recognized that other radionuclides may be present in very limited quantities. Release rate for staging/handling vented containers. See Condition Release rates: Staging Ot_~ellted Containers ..

B/G-0 6.60E-04 Liquid/Particulate Solid WAC 246-247-030(21)(a) Bela/Gamma releaSe rate based on Cs-137 + Pri:>geny. It ts recognized thal other radlonudides may be present in very limited quantities. Rel_ease rate for ei:cavatlon of soil (contamlnaUon detected). See condition: Release Rates: Excavation and Retrieval of Containers. ~~--------------- .. - --------BIG - 0 1.30E-04 Liquid/Particulate Solid WAC 246-247-030(21)(a) Beta/Gamma release rate bas·ed on Cs-137 + Progeny. It is recognized that other radionuclides may be present in very limited quantities. Release rat8 for excavation of soil (Highe·r contamination level, controls required). See condition: Release Rate$: Excavation and Retrieval of Containe·rs.

BIG - 0 6_.60E-05 Liquid/Particulate Solid WAC 246-247-030(21 )(a) Beta/Gamma release rate based on Cs-137 + Progeny. It is recognized that other radionuclides may be present in very limited quantities. Release rate for excavation of soil (notification level). See condition: Release·Rates: Excavation and Retrieval of Containers.

The radioactive isotopes identified for this emission unit are (no quantities specified): Am-241 Am-243 Cf-2_52 Cm-244 Cs-134

Cs - 137

Pu -241

Eu - 152

Sr-90


Eu - 154

U-234

Pu - 238

U - 235

Pu - 239/240

U -236

U-238

The potential release rates described in this Condition were used to determine control technologies and monitoring requirements for this approval. DOE must notifiy the.Department of a "modification" lo the emission unit, as defined in WAC 246-247-030(16). DOE must notify the Department ofwiy changes to a NESHAP major emission unit when a specific isotope is newly identified as contributing greater than 10% of the potential TEDE to the MEI, or greater thwi 25% of the TEDE to the MEI after controls. (WAC 246-247-110(9)) DOE m_ust notify the Department of wiy changes to pol<;ntial release rates as required by state or federal regulations including changes that would constitute a significant modification to the Air Operating Permit under WAC 173-401-725(4). N()tice will be provided according to the particular regulation under which notifica_tion is required. If the applicable regulation(s) does not address manner and type of notification, DOE will provide the Department with advance written notice by letter or electronic mail but not solely by copies of documents.

4) CONTAMINATION MONITORING- Routine Boundary surveys would be performed in addition to radiological control air monitoring and field surveys performed during the work and end-of-shift activities. Routine on-going contamin·ation surveys of all contaminated areas would occur weekly. (WAC 246-247-040(5), WAC 246-247-060(5), WAC 246-247-075(8))

5) CONTAMINATION CONTROL- Dust Suppressants Dust control or suppressants such as water, fixatives, atomized misting, covers, windscreens. or weather encl_osures w{I! be used as necessary to minimize airborne contamination as determined by the Radiological C_ontrol organization. (WAC 246-24 7-040(5) and WAC 246-24 7-060(5))

6) CONTAMINATION CONTROL- End of Shift or High Winds Spoil piles containing radiologicaBy contaminated soi_! >20 dpm/1 00cmA2 alpha or> !000dpm/!00cmA2 beta/gamma will be segregated to the extent practicable from the nonradiologically contamin_ated soil. Containerizing spoils f()r disposal may be performed. Dust controls such as water, fixatives, or covers will be applied at the end of each shift or when sustained or predicted wind speeds are >20mph. The fixatives or other dust controls will not be required when the contaminated items·are frozen, or it is snowing, or other freezing precipi_tat_ion is falling and predicted wind speeds are <20mph (WAC 246-247-040(5) and WAC 246-247-060(5))

7) PROCESS DESCRIPTION: Excavation and Retrieval of Containers This approval applies to these additional activities described below. No additional activities or variations on the approved activities that constitute a "modification" to the emission unit, as defined in WAC 246-247-030(16), may be conducted.

Work will be performed in accordance with as low as reasonably achievable (ALARA) requirements as de_termiried by the. Radiological Control organization. One type of configuration is a V notched trench, containers in some tre_nches may not have been stacked or placed in any orderly manner for burial. The specific steps or approach to uncovering the containers w{il vary according to the configuration of the trench to be uncovered, the type of containers to be retrieved, the proximity of nearby trenches or fences, the designated location of the spoils pile, the planned extent of the soil removal, and other considerations.

Work to be performed within some trenches may be perfo"rrned within a weather resistant structure(s) that will be re-locatable along the tl"ench. Weather enclosures are effectively used for simHar remediation activities at other U.S. Department of Energy (DOE) sites and in general industrial use. Experience during retrieval activities bas shown that operational efficiencies can be improved if the operations are protected from impacts due to weather such as·wind, rain, snow, and temperature extremes. The use ofa weather resistant enclosure could allow a more effective recovery from events involving degraded containers and potential contamination spreads.

Prior to and during overburden removal, subsurface surveys such as ground penetrating radar, electromagnetic inductance, and magnetometer are performed. These surveys provide information regarding container depth, configuration, type, and condition. They may also identify and locate underground obstructions.

The overburden soil will be removed to expose the waste containers. Excavation e_quipment wiil be chosen to effectively remove soil and retrieve the waste containers while mini.mi.zing damage to the containers. Excavation activities will be monitored to identify contamination that might be present and to implement controls to minimize emissions. The most efficient methodology for removing the U:ncontamina_ted overburden from the containers will include the

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maximum use of conventio.nal methods such as excava.to~s, backhoes, fron_t end loaders, brooms (boom mounted), or manual digging with shovels and siniilar hand tools. To excavate COl).tan:iinated soil, hand tools predominantly will be used. Remotely-operated vehicles may be used to minimize personnel exposure in areas where high radiological and/or chemical hazards are discovered or anticipated. High efficiency particulate air (HEPA) filtered vacuums mny be used for soil excavation for this application. Spot contamination removal will be done in accordance with the HEPA filtered vacuum unit (HVU) NOC (DOE/RL 97 50, Radioactive Air Emissions Notice of Construction for HEPA Filtere_d Vacuum Radioactive Air Emission Units, as amended). Within the V Notched trenches, it is more likely that the use of a HEPA-filtered vacuum to remove larger quantities of soil from the top surface of buried containers and.soil materials in the interstices surrounding containers will be employed. Any use of the site wide HVU will be perfonned under the NOC applicable to the unit.

An estimated 300 cubi_c meters of so{! at contarnina_tion d_etection levels occupies the void spaces between the containers buried in the trenches.

Excavation activities will be controlled closely. Heavy equipment, hand tools, light equipment, or HVUs will be used to complete the soil removal operations and to access and remove the plastic and plywood materials covering the con_tainers. All containers wiH be inspected to verify integrity. The container inspection '¥ill consist of a visual examination to determine if there are significant indications of corrosion, holes, dents or other visual deformities. All containers could be moved, turned, or otherwise relocated (manually or with powered equipment, slings, clamps, or appropriate rigging) to facilitate an adequate visual inspection.

The exposed containers will also be visually inspected and surveyed for contamination. Externally contaminated containers will have fixative applied or ,vill be decontaminated. Containers may also be bagged or over packed as needed. Over packing means placing containers within a larger closed container. Bulging or potentially pressurized containers will be vented as described in PROCESS DESCRIPTION: VENTING OF CONTAINERS.

Severely degraded containers will be repackaged or in-situ grouted. Repackaging means transferri_ng the contents of a degraded container into a new container or containers. The entire contents of the container will not be sorted but will be placed into the new container or containers through the use of slings, clamshell excavators, mariual labor, or the best available method that minimizes potential emissions.

Repackaging may include size reduction. Size reducing, cutting or disassembling material and equipment may be required to ensure personnel safety and/or more economical waste packaging. The process will include mechanical cutting techniques such as low speed sawing, drilling, snipping, and shearing. The process will also include bending and crimping to preclude the need for cutting operations where possible.

Containers may include but are not limited to drums, metal boxes, concrete.boxes,.fiberglass reinforced boxes, culverts, and sealed gloveboxes.

In-situ grouting will involve grou_t,ing around and/or throughout _the waste, such that the entire waste container can be removed as a monolith. Retrieval act_ivities will include appropriate disposition of small.amounts of incidental contaminated soil (e.g., containerized or fixed in place). Larger areas of contamination could be fixed and the area posted as required by the Radiological Control organization for later disposition. Bulk transfer of contaminated soils for disposal also could occur.

Some containers will be assayed and, if they assay as TRU waste, they may be further examined to determine whether they contain items prohibited from disposal at the Waste lsolation Pilot Plant (WIPP). Any prohibited items will be removed at a later date. Un vented TRU waste containers may be staged for venting in the burial grounds or may be moved to the Central Waste Complex (CWC) or another treannent, storage or disposal (TSD) site for venting.

A number ofretrieved containers are in good condition but are not vented. Although not technically meeting the definition of 'sealed' containers, Washington State Deparnnent of Health (WDOH) has recognized these as closed containers such that pot_ential emissions from these non vented containers need not be included so far as potential emissions specific to waste during removal from the trenches. Once vented, the containers are included for calculating release rates in NOC 486, Process Description: Staging of Retrieved Containers for staging and


handling operations. An estimated aMual maximum of 15,200 vented containers of waste will be managed during the peak years of this project.

Containers may be staged in the burial grounds perid1ng furthe, processing or transfer. Waste containers are considered retrieved once transferred to an approved TSD fac_ility. (WAC 246-247-040(5) and WAC 246-247-060(5))

8) PROCESS DESCRJPTION: Venting of Containers This approval applies to these additional activities described be_l_ow. No add_itional activities or variations on the approved activities that constitute a "modification" to the emission unit, as defined in WAC 246-247-030(16), may be conducted.

All 1vork will be perfonned to meet ALARA practices and will be conducted according to applicable operating procedures, ra_diological control procedures, and radiol_ogical work permi_t (RWP's). Vent filters will continue to be installed in designated containers via one of the drum venting systems described in this process description. These systems will ensure persoMel and environmental protection. The methodology will require penetrating the container and inserting a vent. Penetration of the lid will be accomplished by either drilling through the lid or puncturing the lid with a filter dart (using Dart System). Container venting systems are described in the foll_owing text. Designated drums slated for veming wiil be vented with the Mobile Drum Venting System (MDVS), Drum Venting System 2 (DVS2), orother venting methods. (WAC 246-247-040(5) and WAC 246-247-060(5))

9) ABATEMENT TECHNOLOGY: Excavation and Retrieval cif Containers The administrative control points set in this emission unit for contamination, as monitored by standard radiological field instrumentation, will be used to bound emissions based on current efficiencies of typical RadCon field contamination instruments.

The controls listed within this approval apply to TRU Waste Retrieval Project open air ex_cavation and retrieval activities. (WAC 246-247-040(5) and WAC 246-247-060(5))

10) RELEASE RATES: Staging of Vented Containers A maximum of 15,200 vented containers of waste (including TRU waste containers, containers that are not designated as TRU waste, and those which could be retrieved with vents in place) will be retrieved per year. Once vented, the containers will be Staged with the other retrieved containers for further handling, resulting in the s_taging/storage ofa maximum of 15,200 vented containers per year at the LLBG. Using a release fraction of2.0 E-09 for fugitive emissions from vented containers (as us_ed in Radioactive Air Emissions Notice of Construction Application for the Waste Receiving and Processing Facility, DOE/RL 2000 34), the predicted release rate from the staging of vented containers without.any emissions control equipment is 6.1 E-04 Ci/yr, with 3.SE-05 Ci/yr attributed to Am-241 +Progeny (representing total alpha) and 5. 7E-04 Ci/yr attributed to Cs-l 37+Progeny (representing total beta/gamma). No credit is taken for abatement; therefore, the predicted abated release rates are assumed to be the same as the predicted uriaba_ted re_lease rates. (WAC 246-247-040(5) and WAC 246-247-060(5))

11) RELEASE RA TE:s: Excavati_on and Retrieval of Containers To determin·e the corresponding soil concentration in picocuries per gram of individual radionuclides, conversion factors, as developed in HNF 2418, Soil Contamination Standards for Protection of Personnel were used The average soil density was assumed to be 98 pounds per cubic foot. The beta gamma contributing radionudides were assumed to be represented by Cesium 137+Progeny and the alpha contributing radionuclides were assumed to be represented by Am 241 +Progeny (predominant alpha contributing radionuclide in the soil is unknown; therefore, assumption of Am 241 +Progeny will produce the most conservative dose consequence). The respective volumes of contaminated soil (i._e., 300 mA3, 3 mA3, and 0.3 mA3) at the three comamination levels are considered as released during manual excavation, using a release fraction of 1.0 E-3.

The estimated 300 m3 of soil in contact with the containers is assumed to be contaminated at detectable levels (100 dpm/100 cm2 alpha and S,000 dpm/100 cm_2 beta/gamma direct readings based on past operations and the pilot dig). A smaller percentage (I%) of the contaminated soil (i.e., 3 m3), is assumed to be contaminated at higher levels (2,000 dpm/100 cm2 alpha and 100,000 dpm/100 cm2 beta/gamma). Contamination at notification levels (28,000 dpm/100 cm2 alpha and 500,000 dpm/100 cm2 beta/gamma) is not expected. However, as a contingency planning estimate, 0.1 % of the contaminated soil (i.e.-, 0.3 m3) is assumed to be contaminated at notification levels (WAC 246-247-040(5) and WAC 246-247-060(5))

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12)

13)

14)

15)

RELEASE RA TES: Dart and Other Venting Systems A maximum of 4,200 containers per year will have installation of Nucfil® or equivalent filters using the Dart or FRP Systems. A conservative time estimate for pressure release during each installation is I hour. Using a release fraction of 1.0 E-3 for particulates and a time factorof 4_._SE-01 ( 60 minutes per container multiplied by 4,200 containers and divided by 526,000 minutes per year), the predicted release rate (unabated) from using the Dart or FRP System for installation ofNucfil or equivalent filters without any emissions control equipment is 9.6E-03 Ci/year. Following installation of the Nucfil or equivalent filter, the emissions are routed through the HEPA-type Nucfil or equivalent filter (certified 99.97% removal efficiency); therefore, the predicted release rate (abated) with emissions control equipment is 4.SE-06 Ci/year. The p_redicted release rates for the representative radionuclides Am-24!+Progeny and Cs-137+Progeny are as follows: Unabated PTE; Am-241 +Progeny 6.0E-04 Ci/yr. Abated PTE; Am-24 I +Progeny 3.0E-07 Ci/y (W AC.246-247-040(5) and WAC 246-247-060(5))

Cs-!37+Progeny Cs- I 3 7+ Progeny

WOOH NOTIFICATION - Implementing PES or NGR Containment

9.0E-03 Ci/yr. 4.5E-06 Ci/yr.

During high hazard work activities, removable surface contamination is maintained less than 2,000,000 dpm/100 emA2 alpha and/or less than 4 rad/hr./ I 00 cmA2 beta-gamma, limited to a I ftA2 area. For an allowed increase in contaminated area footprint of 4 ftA2 the limiting condition for removable contamination will be 500,000 dpm/100 cmA2 alpha and or I rad/hr./100 cmA2 beta-gamma. Exceeding any of these contamination limits will require work to stop, and notification to Operation and RadCon management in accordance with the RWP. Notification to WDOH via email or the established procedures in the Environmental Notification program will be required. For work to continue above any of these limiting radiological conditions, the NGR containment system or the PES and commensurate controls will be implemented_. The NGR containment or PES exhaust system will be utilized to minimize the potential for contamination spreads outside of posted radiological areas. (WAC 246-247-040(5) and WAC 246-247-060(5)) WOOH NOTIFICATION -Transition to High Hazard Work Package During medium hazard work activities, removable contamination will be maintained less than 20,000 dpm/100 cmA2 alpha and/or less than 1,000,000 dpm/1 00cmA2 beta-gamma and the removable contamination area limited to 4 ftA2. Exceeding these limits will require work to stop, and notification to Operation and RadCon management in accordance with RWP. Notification to WDOH via email or the established procedures in the Environmental Notification program will be required. For work to continue above these limiting radiologic_al conditions, the highhazard work package and associated c_ontrols shall be implemented. (WAC 246-247-040(5) and WAC 246-247-060(5)) WOOH NOTIFICATION - Drum Vent Failure The department shall be notified via email or the established procedures in the Environmental Nori fication program within 24 hours of all drum vents that fail to be installed properly and smears show >2,000 dpm/100 cmA2 alpha or> I 00,000 dpm/ I 00 cmA2 betn/g;muna removable contami.natioc (an example of a "failure" is a pressure release that blows past the seat of the boot or a deflagration). (WAC 246-247-040(5) and WAC 246-247-060(5))

16) WDOH NOTIFICATION - Loss of Containment WDOH will be notified per WAC 246-247-080(5) via email or the established procedures in·the Environmental Notification pro"gram if a loss of containment occurs (dropping, spilling, puncturing a container, or otherwise encoun_tering 1.oss of integri_ty where contamination escapes containment), which exceeds 100,000 dpm/100 cmA2 beta/gamma or 2,000 dpm/100 cmA2 alpha removable contamination. (WAC 246-247-040(5) and WAC 246-247-060(5))

17) WDOH NOTIFICATION - Transition to High Hazard Designation During soil removal activities, if direct contamination readings for the general area is greater than 28,000 dpm/100 cm2 alpha or greater than 500,000 dpm/100 cm2 beta-gamma, work will stop, the environmental compliance officer, RadCon Management and WDOH will be notified ,ia email or the established procedures in the Environmental Notification program, and.the controls listed immediately below, implemented. Once notifications have been made and the following controls implemented, work may resume under high hazard designation: a. Soil wi_ll be wetted prior to soil removal; and soil will be maintained damp during soil removal. B. General area workplace air sampling will be performed. (WAC 246-247-040(5) and WAC 246-247-060(5))

18) ALTERNATIVE APPROVAL - Unabated Emissions The potential unabated dose rate from manual excavation is 7.5 E-4 mrem/year. No credit is taken for abatement;

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therefore, the abated emissions are assumed as the unabated emissions. Although fixatives and similar controls will be employed for the higher contamination level and notification level contamination, no credit is being taken for abatement; therefore, the abated dose rate.is the unabated dose rate. (WAC 246-247-040(5), WAC 246-247-060(5), WAC 246-247-075(4))

19) ALARACTAPROV AL - Container Handling The process for handling of abnonnal or severely degraded containers as described in Process Description: Excavation And Retrieval of Containers, for bagging, over packing, placing degraded outer container contents into repl_acement con_tainers or in-situ grouting is approved as meeting ALARACT, and these processes and associated records and procedures will be subject to inspection upon re_ques_t oy the department. (WAC 246-247-040(5) and WAC 246-247-060(5))

20) AL TERNATNE APPROVAL- WDOH NOTIFICATION-Administrative Control on Emissions WDOH accepts the method proposed for calculating the estimated dose with the limitation that the annual release of the sum of the fractions of the curies released/annual release cannot exceed a value of I for alpha/beta plus gamma release. The limit on annual release shall not exceed 2.1 E-2 Ci/year using Am-241 +Das a representative for alpha cal_culations and 1.15 EO Ci/year using Cs-137+O as a representative for Gamma calculations, collected at a point not to exceed IO meters from the work area of disturbed material. WDOH will be notified when the sum of the. fractions reaches a value of 0.8 representing 0.08 mrem/year to the MEI, and additional controls will be initiated to ensure that the dose to the MEI does not exceed 0.1 mrem/year. Workplace air.sampling will be conducted when performing work.

21) CONTAMINATION CONTROL - Limits to Initiate NGR or PES Adherence to contamination limits in the immediate work location for medium and high-hazard work will help ensure that the work area airbome radioactivity limits (i.e., l .0E-09 µCi/ml for alpha emitters and 2E-06 µCi/ml for beta-gamma emitters) ore not exceeded. (WAC 246-247-040(5) and WAC 246-247-060(5))

22) CONTAMINATION DOCUMENTATION -Exposed Packages During repackaging activities (i.e., when transferring the contents ofa degraded container into a new container or containers) an operations log will be kept noting conditions of the transferred contents/packages .. RadCon will generate and retain radiological records documenting air sample results and removable contamination conditions during retrieval of each container. (WAC 246-247-040(5) and WAC 246-247-060(5))

23) CONTAMINATION CONTROL - Funccion Check Misters and Sprayers Atomized misters and fixative sprayers will be function checked at the work site prior to commencing work activities. (WAC 246-247-040(5) a_nd WAC 246-247-060(5))

24) CONTAMINATION CONTROL -NGR/PES Activities Activities done un_der confinement structure of PES and NGR will be considered to be diffuse and fugitive activities unless under active v~ntilation conditions. (WAC 246-247-040(5) and WAC 246-247-060(5))

25) CONTAMINATION CONTROL - Soil Ex_cavation Near Containers Manual methods or 1-fVU will be used to excavate soil in close proximity to containers. (WAC 246-247-040(5) and WAC 246-247-060(5))

26) CONTAMINATION CONTROL - Transporting Waste Packages Radiological contamination and dose rate monitoring will be conducte_d prior to transporting ariy waste containers. All waste will be contained as appropriate for transport. Covers such as tarps or plastic will be placed over deteriorated containers at the end of each shift. These practices of monitoring, container integrity inspections, and placement of covers will ensure good contamination control practices are observed during package handling activiti_es, soil removal (excluding overburden removal) and over packing activities and when placing degraded outer container contents in_to replacernen_t containers. (WAC 246-247-040(5) and WAC 246-247-060(5))

27) CONTAMINATION CONTROL -Buik Transfer of Contaminated Soil The soil surface will be weued prior to bulk transfers of contaminated soil. (WAC 246-24 7-040(5) and WAC 246-247-060(5))

28) CONT AMINA HON CONTROL - Wind Speed Work perfonned outside (excavation and/or container retrieval) will stop if average wind speeds exceed 11 mph during the work and C<lntamination Area or Airborne Radioactivity Area conditions exist. (WAC 246-247-040(5) and WAC 246-247-060(5))

29) CONTAMINATION CONTROL - Limits to Trigger Further Airborne Controls Radiological field survey monitoring will use set points for removable surface contamination levels of>I0OO dpm/100 crnA2 beta/gamma and >20 dpm/100 crnA2 alpha to trigger the need to further evaluate airbome controls or evaluate further preparation of materials for release. (WAC 246-247-040(5) and WAC 246-247-060(5))

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30) CONTAMfNA T!ON CONTROL - Soil Surveys Dutfag TRU R_etrieval During excavation acthities for re_trieva_l, excludi_ng a_ct_iVities assoC.i_at~d with re:1:noval of sofl overburden, radioactive contamination monitoring for diffuse and fugitive emissions will consist of soi_! surveys at h,ast hourly for both alpha and beta/gamma contamination during TRU Waste Retrieval operations. (WAC 246-247-040(5) and WAC 246-247-060(5))

31) CONTAMfNATION CONTROL - Removable Contamination Survey Both Alpha and beta-gamma conraminarion field surveys shall be performed for all removable contamination s_urveys, prior t_o and during soil removal (excluding overburden removal) and over packing activities and when placing degraded outer container contents into replaceme_nt containers. Alpha surveys shall be petformed for direct readings of container surfaces. Beta/gamma direct readings may be inhu·enced by cont_ainer contents, so are not as useful and are not required. (WAC 246-247-040(5) and WAC 246-247-060(5))

32) CONTAMfNATION CONTROL -Fixatives Fixatives or other controls will be employed if removable contamination levels exceed I 00,000 dpm/100 cmA2 beta/gamma or exceed 2,000 dpm/100 cmA2 alpha. (WAC 246-247-040(5) and WAC 246-247-060(5))

33) CONTAMfNATION SAMPLfNG-ARA Workplace air sampling at the work site perimeter (on all four sides of the work location) and downwind of the c·ontainer work loca_tion will be con_duc_ted whe_n performing work in an Airborne Radiological Area, providing early indication of potential elevation in work site perimeter airborne rad:ioactivity. (WAC 246-247-040(5), WAC 246-247-060(5), WAC 246-247-075(8))

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