Diablo Canyon Power Plant Semiannual Radioactive Effluent ... · Diablo Canyon Units 1 and 2 Semiannual Radioactive Effluent Release Report Gentlemen: Enclosed is the Diablo Canyon

.*~j l

ACCELHMTED IBSEN BUTlON BEMONS TION SYSTEM I

REGULATORY INFORMATION D TRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8803070190 DOC.DATE: E2/31 NOTARIZED- NOFACIL:50-275 Diablo Canyon Nuclear Power Plant, Unit 1, Pacific Ga

50-323 Diablo Canyon Nuclear Power Plant, Unit 2, Pacific GaAUTH.NAME AUTHOR AFFILIATION

SHIFFER,J.D. Pacific Gas 6 Electric Co.RECIP.NAME RECIPIENT AFFILIATION

DOCKET0500027505000323

SUBJECT: "Diablo Canyon Power Plant Semiannual Radioactive EffluentRelease Rept,Jul-Dec 1987." W/880301 ltr.

iliDISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR i ENCL ) SIZE:TITLE: 50.36a(a)(2) Semia nual Effluent Release Reports

NOTES:g~ gpss< CSP ii)

R

RECIPIENTID CODE/NAME

PDS LAROOD,H

INTERNAL: ACRSAEOD/DSP/TPABNRR/DEST/PSB8D1NRR/PMAS/ILRB12RGN5 FILE 02

EXTERNAL BNL TICHLERIJ03NRC PDR

COPIESLTTR ENCL

1 01 1

1 11 11 11 11 1

1 11 1

RECIPIENTID CODE/NAME

PD5 PD

AEOD/DOAARM TECH ADVNRR D PB10AREG ILE 01

G /5R PRPB

LPDR

COPIESLTTR ENCL

5 5

1 11 141 11 1

2'

A

A

TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 23

880310Pl

4 0

JAMES O. SHIKaKaER

VlCK PRKSIOKNT

NVCKKAR POWER GKNKRATIGN

e .C IF IC" CvA.B A.ND ZLECTRIC COMPS NYIP(CP~IE ~ 77 BEALE STREET ~ SAN FRANCISCO,(ALIFORNIA94106 ~ (415) 972'-7000 ~ TWX 910 372.6587

Harsh I, 1988

PGSIE Letter No.: DCL-88-047

U.S. Nuclear Regulatory CommissionAttn: Document Control DeskHashington, D.C. 20555

Re: Docket No. 50-275, OL-DPR-80Docket No. 50-323, OL-DPR-82Diablo Canyon Units 1 and 2Semiannual Radioactive Effluent Release Report

Gentlemen:

Enclosed is the Diablo Canyon Power Plant Units 1 and 2 Semiannual RadioactiveEffluent Release Report for the second half of 1987. The report describes thequantities of radioactive gaseous and liquid effluents released from the plantover the period of July 1, 1987 through December 31, 1987, and the solidradioactive waste shipments during the same period.

This report is required by 10 CFR 50.36a(2) and Section 6.9.1.6 of the DiabloCanyon Technical Specifications.

Kindly acknowledge receipt of this material on the enclosed copy of thisletter and return it in the ericlosed addressed envelope.

Sincerely,

Enclosure

cc: J. S. McGurkCalifornia Department of Health Services

R. H. CarrSan Luis Obispo Air Pollution Control District

G. Rowland, MD

San Luis Obispo County Department of Public HealthJ, B. MartinM. M. MendoncaP. P. NarbutB. NortonA. Rosen

California Polytechni cal InstituteB. H. VoglerCPUCDiablo Distribution

1947S/0054K/JLP/0649

(

t" '\h,m'l' Fqp~ ll

ll

PGI|E Letter No.: DCL-88-047

ENCLOSURE

DIABLO CANYON POHER PLANT

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

JULY 1, 1987 - DECEMBER 31, 1987

<

PACIFIC GAS AND ELECTRIC COMPANY

FEBRUARY 1988

8802070190 871221pDR *DocK o5ooo2~s,,R 'DCD "

1947S/0054K

N

1



JULY 1, 1987 THROUGH DECEMBER 31, 1987

TABLE OF CONTENTS

INTRODUCTION 3

SUPPLEMENTAL INFORMATION .................................... 4

II. MAJOR CHANGES TO LIQUID, GASEOUS AND SOLID RADHASTE TREATMENTS YSTEMS o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10

III. CHANGES TO THE PROCESS CONTROL PROGRAM ...................... 10

IV. CHANGES TO THE ENVIRONMENTAL RADIOLOGICAL MONITORINGPROCEDURE (ERMP) ............................................ 10

V. CHANGES TO THE OFFSITE DOSE CALCULATION PROCEDURE (ODCP) ~ ~ ~ ~ 1 0

VI. 1987 LAND USE CENSUS ........................................ 10

VII. GASEOUS AND LIQUID EFFLUENTS ................................ 11

Table 1 - Gaseous Effluents - Summation of All Releases ..... 12

Table 2 — Gaseous Effluents - Ground-Level Releases ......... 13

Table 3 — Gaseous Effluents - Lower Limits of Detection ..... 15

Table 4 — Liquid Effluents - Summation of All Releases ...... 17

Table 5 — Liquid Effluents — Nuclides Released .............. 19

Table 6 — Liquid Effluents - Lower Limits of Detection ...... 22

VIII. SOLID RADWASTE SHIPMENTS .................................... 25

IX. RADIATION DOSE DUE TO GASEOUS AND LIQUID EFFLUENTS .......... 28

Table 7 — Radiation Dose Due to the Release ofRadioactive Liquid Effluents ......... ........... 31

Table 8 — Radiation Dose Due to the Release ofRadioactive Gaseous Effluents .................... 32

Table 9 — Percent of Technical Speci fi cati on Limitsfor Radioactive Liquid Eff1 uents ................. 37

1947S/0054K

0



JULY 1, 1987 THROUGH DECEMBER 31, 1987

TABLE OF CONTENTS

IX. RADIATION DOSE DUE TO GASEOUS AND LIQUID EFFLUENTS (Continued)

Table 10 — Percent of Technical Specification Limitsfor Radioactive Gaseous Effluents ................ 38

Table 11 — On Site Dose To Members Of The Public ............ 42

X. METEOROLOGICAL DATA ......................................... 46

ATTACHMENTS

1. MABOR CHANGES TO LIQUID, GASEOUS AND SOLID RADHASTE TREATMENT SYSTEMS

2. CHANGES TO THE PROCESS CONTROL PROGRAM

3. CHANGES TO THE OFFSITE DOSE CALCULATION PROCEDURE

4. 1987 HAND USE CENSUS

1947S/OOS4K


SEHIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987

INTRODUCTION

This Semiannual Radioactive Effluent Release Report summarizes the gaseous andliquid effluent releases made from Diablo Canyon Power Plant's Units 1 and 2for the third and fourth, quarters of 1987. This report also includes thedoses due to the release of radioactive liquid and gaseous effluents and asummary of solid radwaste shipments. This report contains the informationrequired by Unit 1 and 2 Technical Specification 6.9. 1.6 and is generallypresented in the format of Regulatory Guide 1.21, Appendix B.

In all cases, the plant effluent releases were well below TechnicalSpecifications for the report period.

The Unit 1 reactor operated at full power throughout the report period exceptfor short period outages in August, November, and December. The Unit 2reactor returned to power following its first refueling outage during July andthen at full power throughout the report period except for short periodoutages in November and December.

1947S/0054K

I. SUPPLEHENTAL INFORHATION

A. Regulatory Limits

1. Gaseous Effluents

Noble Gas Dose Rate Limit

The dose rate in unrestricted areas due to radioactivenoble gases released in gaseous effluents is limited toless than or equal to 500 millirem per year to the totalbody and less than or equal to 3000 mi llirem per year tothe skin.(Technical Specification 3.11.2.l.a.)

b. Particulate and Iodine Dose Rate Limit

The dose rate in unrestricted areas due to Iodine-131,Iodine-133, tritium, and all radionuclides in particulateform with half lives greater than 8 days in gaseouseffluents is limited to less than or equal to 1500 milli remper year to any organ. (Technical Specification3.11.2.l.b.)

c ~ Noble Gas Dose Limit

The air dose due to noble gases released in gaseouseffluents, from each reactor unit, from the site, islimited to the following.

Gamma radiation

Beta radiation

CALENDAR QUARTER

5 mi 1 1 irad

10 mi 1 1 irad

CALENDAR YEAR

10 mi 1 1 irad

20 mi 1 1irad

d.

(Tech. Spec. 3.11.2.2)

Particulate and Iodine Dose Limit

The dose to an individual from Iodine-131, Iodine-133,tritium, and all radionuclides in particulate form withhalf lives greater than 8 days in gaseous effluentsreleased, from each reactor unit, from the site, is limitedto less than or equal to 7.5 millirem to any organ in anycalendar quarter and less than or equal to 15 mi llirem toany organ during a calendar year. (Technical Specification3.11.2.3)

1947S/0054K

2. Liquid Effluents

a. Concentration

The concentration of radioactive material released from thesite is limited to the concentrations specified in 10 CFR

Part 20, Appendix B, Table II, Column 2 for radionuclidesother than dissolved or entrained noble gases. Fordissolved or entrained noble gases, the concentration islimited to 2 x 10-4 microcuries/ml total activity.(Technical Specification 3. 11. 1. 1)

b. Dose

The dose or dose commitment to an individual fromradioactive materials in liquid effluents released, fromeach reactor uni t, from the site, is limited to thefollowing:

Total Body

Any Organ

CALENDAR QUARTER

1.5 millirem

5 mi1lirem

CALENDAR YEAR

3 mi 1 1 irem

10 mi 1 1irem

(Technical Specification 3.11.1.2)

B. Haximum Permissible Concentrations


Maximum permissible concentrations are not used in themethodology for determining allowable release rates for gaseouseffluents at Diablo Canyon Power Plant.

2. Liquid Effluents

The concentrations listed in 10 CFR 20, Appendix B, Table II,Column 2 for radionuclides other than dissolved or entrainednoble gases are used for determini ng the allowable release rateat the point of discharge from the site for liquid effluents.For dissolved or entrained noble gases, the allowable releaserate concentration at the point of discharge is limited to 2 x10-4 microcuri es per milliliter total activity for liquideffluents.

1947S/0054K

C. Measurements and Approximations of Total Radioactivity


a ~ Fission and Activation Gases

b.

The gaseous radioactivity released from the plant vent ismeasured by a pair of off-line monitors each usingGeiger-Mueller detector readings from these monitors.These monitor readings are correlated to isotopicconcentration based on isotopic analysis of a grab sampleusing a germanium detector. A noble gas grab sample isobtained and analyzed at least weekly. The isotopicmixture is assumed to remain constant between grab sampleanalyses. Containment purges, gas decay tank releases andair ejector discharge are all routed through the plant ventfor release. The gaseous radioactivity released from thesteam generator blowdown tank vent is measured by analyzinggrab samples with a germanium detector. The isotopicconcentrations are assumed to remain constant between grabsamples.

Hhen the plant vent measurements as indicated by theprocess monitors are below the lower limit of detection,the results of the grab samples are used to quantifyreleases. In addition, the individual batch release datais used to quantify the radioactivity discharged from thegas decay tanks, and containment.

Other potential pathways for releasing gaseousradioactivity are periodically monitored by collecting grabsamples and analyzing these samples with a germaniumdetector system.

Iodine s

Radioiodines released from the plant vent are monitored bycontinuous sample collection on silver zeolite cartridges.The cartridges are changed at least weekly and analyzedwith a germanium detector., The radioiodine releases areaveraged over the period of cartridge sample collection.

Other potential pathways for releasing radioiodines areperiodically monitored by collecting samples using charcoalcartridges and analyzing these cartridges with a germaniumdetector.

1947S/0054K

c ~

d.

Particulates

Radioactive materials in particulate form released from theplant vent are monitored by continuous sample collection onparticulate filters. The filters are changed at leastweekly and analyzed with a germanium detector. Theparticulate radioactivity is averaged over the period ofparticulate filter sample collection. Each filter isanalyzed for alpha emitters using an internal proportionalcounter. All of the plant vent particulate filterscollected during a quarter are used for the compositeanalysis for strontium-89 and-90 which is counted on aninternal proportional counter after chemical separation.

Other potential pathways for releasing radioactiveparticulates are periodically monitored by collectingsamples using particulate filters and analyzing thesefilters with a germanium detector.

Tri tium

Tritium released from the plant vent is monitored bypassing a measured volume of plant vent sample through awater column and determining the tritium,increase in thewater. An aliquot of the water is counted in a liquidscintillation spectrometer. Tritium is determined at aminimum sample frequency of weekly. The tritiumconcentration is assumed to remain constant between samples.

2. Liquid Effluents

a. Batch Releases

Each tank of liquid radwaste is analyzed for principalgamma emitters using a germanium detector prior torelease. The pre-release analysis includes dissolved andentrained gases. Volume proportional monthly and quarterlycomposites are prepared from aliquots of each tankreleased. The monthly composite is analyzed for tritiumusing a liquid scintillation spectrometer and gross alpharadioactivity using an internal proportional counter. Thequarterly composite is analyzed for iron-55 using a liquidscintillation spectrometer and for strontium-89 and-90using an internal proportional detector following chemicalseparations.

1947S/0054K

b. Continuous releases

For the continuous liquid releases of steam generatorblowdown tank and turbine building sump oily waterseparator, daily grab samples are collected and volumeproportioned for weekly, monthly and quarterly composites.The oily water separator weekly composite is analyzed forgross gamma and principal gamma emitters using a germaniumdetector. The steam generator blowdown tank weeklycomposite is analyzed for principal gamma emitters andiodine-131. The steam generator blowdown tank monthlycomposite is analyzed for tritium using a liquidscintillation spectrometer and for gross alpha using aninternal proportional counter. The steam generatorblowdown tank quarterly composite is analyzed for iron-55using a liquid scintillation spectrometer and forstrontium-89 and-90 using an internal proportional counterfollowing chemical separations. The results for each ofthe composites are averaged over the period of thecomposite. In addition, one grab sample of the steamgenerator blowdown tank is analyzed monthly for dissolvedand entrained gases using a germanium detector. Theresults of this analysis are assumed to remain constantover the period of one month.

D. Batch Releases

l. Liquid

a 4 Number of batch releases...................'.... 544

b.

c ~

d.

e.

Total time period for batch releases...........

Haximum time period for a batch release........

Average time period for a batch release........

Hinimum time period for a batch release........

Average saltwater flow during batch releases...

1281 hours

12.60 hours

2.35 hours

0.017 hours

1.65E+6 GPH

2. Gaseous

a.

b.

c ~

d.

e.

Number of batch releases.......................Total time period for batch releases...........

Maximum time period for a batch release........

Average time period for a batch release........

Hinimum time period for a batch release........

109

64.0 hours

3.00 hours

0.59 hours

0.10 hours

1947S/0054K

E. Abnormal Releases

F.

On October 22, 1987, an unplanned release from a Unit 1 Gas DecayTank occurred when valve CVCS-1-667 was inadvertently left open. Therelease occurred inside the Auxiliary Building and was monitored bythe plant vent monitors. During this event, 6.68E-1 curies ofXe-133, 1.20E-2 curies of Xe-131m, 5.10E-3 curies of Xe-133m, 1.71E-4curies of Xe-135, and 2.98E-2 curies of Kr-85 were released. Thetotal activity of the release was 7.15E-l curies and the release ratewas determined to be 1.04E-l'L of Technical Specification Limit.

On December 9, 1988, an unplanned release from Unit 1 Vent Headeroccurred when a relief valve (RV-54) malfunctioned. The releaseoccurred inside the Auxiliary Building and was monitored by the plantvent monitors. During this event, 1.01E-3 curies of Xe-133, 2.64E-7curies of Kr-85m, 1.57E-5 curies of Xe-131m, 1.22E-5 curies ofXe-133m, 5.84E-6 curies of Xe-135, and 2.53E-5 curies of Kr-85 werereleased. The total activity of the release was 1.07E-3 curi es andthe release rate was determined to be 1.33E-4'L of TechnicalSpecification Limit.

On January 5, 1988, an unplanned release from Unit 2 Air Ejector Ventwas identified as a result of a missing cap on the test port. Atthis time, the exact release period could not be determined.However, based on the most conservative estimation the release periodwas determined to be July 20 through December 31, 1987. Based on thenoble gases mixture on January 5, 1988, and the estimated releaseperiod, 7.53E-2 curies of Xe-133, 2.85E-3 curies of Kr-85m, 1.27E-2curies of Xe-131m, 6.92E-3 curies of Kr-88, 2.88E-2 curies of Xe-135,2.59E-2 curies of Xe-138, 5.69E-3 curies of Kr-87, 5.29E-2 curies ofXe-135m and 7.86E-4 curies of Ar-41 were released during this event.The total activity of the release was 2.12E-l curies and the releaserate was determined to be 6.61E-5'X of Technical Specification Limit.

Effluent Honi toring Instrumentation

During the report period, there were several RE-18 (Liquid RadwasteEffluent Monitor) alarms due to the crud accumulation in the pipingdead legs shared by the Liquid Radwaste Discharge System and theSpent Resin Transfer System. This crud is transported to the RE-18monitor during the beginning of a discharge causing a RCV-18 tripwhich terminates the release. The residue in the line is thenflushed back to the Liquid Radwaste System after a sample is obtainedand analyzed.

A plant technical review group determined the corrective action toprevent recurrence is to develop and implement a design change toseparate the shared piping between Liquid Radwaste Discharge Pipingand the Spent Resin Transfer System.

1947S/0054K

MAJOR CHANGES TO LIQUID, GASEOUS AND SOLID RADHASTE TREATMENT SYSTEMS

During the report period, one ma]or change to the Liquid Radwaste Systemwas approved. Design change DCP M-35781 removed the Unit 1 monitor tanksfrom the Boric Acid Recycle System and converted them intoLaundry/Distillate Tanks which were added to the Liquid Radwaste System.A major change to the Solid Radwaste System also occurred during thereport period. Dry Active Haste and expended cartridge filters wereprocessed by a mobile shredding system prior to packaging the waste usingin-plant compactors. This change was controlled by Revision 8 toProcedure AP C-257. A description of the design change evaluations isincluded as Attachment l.

III. CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

The radioactive waste packaging Process Control Program (PCP), aspromulgated in DCPP Administrative Procedures AP C-253 and AP C-253Sl,was revised twice during the report period. Revision 8 to AP C-253"Process Control Program" combined with Revision 1 to AP C-253Sl"Dewatering Control Program", was a change which did not affect any PCP

formulas. This change to the DCPP procedures involved a reorganizationof the referenced vendor procedures in AP C-253 and AP C-253Sl tosegregate solidification from dewatering. Since no vendor proceduralrevisions were associated with these DCPP procedural changes there was noeffect on waste solidification. This revision was reviewed and foundacceptable by the Plant Staff Review Committee (PSRC) on July 30, 1987.Revision 9 to AP C-253 incorporated a change to the vendor's acidsolidification PCP procedure. This change involved requiring the fullscale chemical addition to be based on the successful specimen sampleversus a fixed amount. This full scale formula change corrected anoversight in the text and was within the scope of the Topical Report.This revision was reviewed and found acceptable by the Plant Staff ReviewCommittee (PSRC) on November 12, 1987.

Therefore, the above changes to the PCP did not reduce the overallconformance of the solidified waste product to existing criteria forsolid wastes. A copy of the changed pages are included as Attachment 2.

IV.

V.

~

CHANGES TO THE ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURE (ERMP)

There were no changes to the DCPP Environmental Radiological MonitoringProcedure (ERMP) during the report period.

CHANGES TO THE OFFSITE DOSE CALCULATION PROCEDURE (ODCP)

During the report period, one on-the-spot-change to the DCPP Offsite DoseCalculation Procedure (ODCP) was approved. This change was to render anomenclature change for two liquid radwaste tanks and will not reduce theaccuracy or reliability of dose calculations or setpoint determination.This change was reviewed and found acceptable by the Plant Staff ReviewCommittee (PSRC) on September 17, 1987. A copy of the change page isincluded as Attachment 3.

1987 LAND USE CENSUS

There were no changes from the 1986 Land Use Census. The 1987 Land UseCensus results are included as Attachment 4.

1947S/0054K

VII. GASEOUS AND LIQUID EFFLUENTS

1947S/0054K - 11-

DIABLO CANYON POMER PLAHT

SEMIANNUAL RADIOACTIVE EFFLUEHT RELEASE REPORT 1987

TABLE 1

6ASEOUS EFFLUENTS - SUIOOTION OF ALL RELEASES

Units Third Fourth Est. Totalquarter quarter Error,X

A. F1ssion E act1vation gases

. Total release2. Average release rate for period3. Percent of technical specification limit

C1

pCi/sec

.39 E+2

.74 E+

5.43 E-3

.9 E+2 5.5 E+

2.40 E+

8. 6 E-

B. Iodines. Total iodine- 31

2. Average release rate for period3. Percent of techn1cal specification limit

Ci

pCi/sec

8.80 E-5 .64 E-4

E-5 2.06 E-5

.83 E-4 3.39 E-4

2.4 E+

C. Particulates1. Particulates with half-lives > 8 days C1 .96 E-5 1.77 E-5 2.4 E+1

2. Average release rate for period3. Percent of technical specification 11mit

pCi/sec 2.46 E-6 2.24 E-6

1.46 E-5 1.22 E-5

4. Gross alpha radioactivity Ci HDA MDA

D. Tritium. Total release Ci 3.06 E+0 .20 E+ .3 E+

2. Average release rate for per1od

3. Percent of techn1cal spec1f1cation 11mit

pCi/sec 3.85 E-

.29 E-4

1.51 E+0

5.07 E-4

NOTE:

'DA = Less than the "a posterior1" m1nimum detectable activity (microcuries per unitmass or volume). This note applies to all tables.

~ Techn1cal Spec1f1cat1on 3.11.2.1 Limit

J00001. S EH -12-

V

>1

DIABLO CANYON POWER PLANT

SEHIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987

TABLE 2

6ASEOUS EFFLUENTS - GROUND-LEVEL RELEASES

THIRD QUARTER FOURTH QUARTER

uclides Released UnitCONTINUOUS

MODE

BATCHHODE

CONTINUOUS BATCHMODE MODE

1. Fission gases

argon-41

krypton-85

krypton-85m

krypton-87

krypton-88xenon-131m

xenon-133

xenon-133m

xenon-135

xenon-135m

xenon-138

TOTAL FOR PERIOD

Ci

Ci

Ci

Ci

Ci

Ci

Ci

MOA

MOA

MDA

MDA

MDA

MDA

6.72 E+1

MDA

2.60 E+0

4.55 E-4

MDA

6.98 E+

.4 E+0

7.6 E-

3.58 E-2

5.42 E-4

9.55 E-2

.02 E+0

6.45 E+

4.82 E-

4.34 E-1

MDA

MDA

6.87 E+

MOA

.73 E-

MDA

MDA

6.68 E+1

MDA

3.24 E+0

MDA

MOA

7.02 E+1

2.26 E+0

MDA

7. 5 E-2

MDA

5.38 E-2

1.84 E+0

3 E+2

9.03 E-

9.38 E-1

MOA

MDA

. 9E+2

2. Iodines

iodine- 31

iodine- 33

iodine- 35

TOTAL FOR PERIOD

Ci

Ci

8.80 E-5

. 2E-4MDA

2.00 E-4

1.64 E-4

9.95 E-5

MDA

2.64 E-4

J00001. SEM -13-

1

(i

h

~ '

\* ~

DIABLO CANYON PSKR PIAHT

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987

TABLE 2 (Continued)

GASEOUS EFFLUEHTS —GROUND-LEVEL RELEASES

Nuclides Released Unit

CONTINUOUS MODE

Third Quarter Fourth Quarter

3. Particulatescesium- 34

cesium- 37

cerium- 4

cerium-144

chromium-51

cobalt-58cobalt-60iron-59

manganese-54

molybdenum-99

ruthenium-103

stront ium-89

strontium-90zinc-65

zirconium-95

TOTAL FOR PERIOD

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

.68 E-6

MDA

MDA

.69 E-5

MDA

MDA

MDA

MDA

MOA

MDA

MDA

MDA

1.96 E-5

2. 0 E-6

4.34 E-6

MOA

MDA

MOA

MDA

. 3 E-5

MDA

MDA

MOA

MDA

MOA

MDA

MDA

MDA

.77 E-5

Note:

'ncludes Daughters

000001.SEM

\

-14-

C

0


SEMIANHUAL RADIOACTIVE EFFLUEHT RELEASE REPORT 1987

TABLE 3

6ASEOUS EFFLUENTS - LOWER LIMITS OF DETECTION

Nuclide Unit Continuous Mode Batch Mode

1. Fission gases

krypton-85

krypton-85m

krypton-87

krypton-88xenon- 3 m

xenon- 33

xenon- 33m

xenon- 35

xenon- 35m

xenon-138

argon-41

pCi/ml

pCi/ml

pCi/ml

pCi/ml

p i/mlpCi ml

pCi/ml

pCi ml

pCi/ml

pCi/ml

pCi/ml

8.49 E-

.70 E-8

7.76 E-8

5.24 E-8

8.01 E-7

4.40 E-8

.28 E-7

.67 E-8

3.76 E-7

1.25 E-6

6.71 E-8

ontainmentPurge

8.49 E-

.70 E-8

7.76 E-8

5.24 E-8

8.0 E-7

4.40 E-8

.28 E-7

.67 E-8

3.76 E-7

1.25 E-6

6.71 E-8

Gas DecayTank

2.22 E-3

4.32 E-6

.29 E-5

.47 E-5

2.06 E-4

.28 E-5

3.10 E-5

5. E-6

2.52 E-5

4.75 E-5

.04 E-5

2. Tritiumhydrogen-3 pCi/ml 1.27 E-8 .27 E-8

3. Iodi nes

iodine- 3

iodine- 33

iodine- 35

pCi/ml

pCi/ml

pCi/ml

2.7 E- 3

3.41 E- 3

3.99 E- 2

J00001. S EM -15-

*~

DIABLO CANYON POMER PLANT


TABLE 3 (Continued)

GASEOUS EFFLUENTS - LOMER LIMITS OF DETECTION

Nuclide Un t Continuous Mode

4. Particulatescesium- 34

cesium- 37

cerium- 4

cerium- 44

chromium-51

cobal t-58cobalt-60iron-59manganese-54

molybdenum-99

ruthenium-103

strontium-89

strontium-90zinc-65

zirconium-95

pCi ml

p i/ml

p i/mlpCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

3. 0 E- 3

2.64 E- 3

.97 E- 3

.02 E- 2

.7 E- 2

2.78 E- 3

3.0E-34. 6 E- 3

.39 E-13

2.77 E- 2

2.19 E-13

8.99 E-15

395 E-53.63 E- 3

3.42 E-13

gross alpha pCi/ml 5.58 E- 5

Note:

'ncludes daughters

J00001.SEM -16-

II

DIABLO CANYON NUCLEAR POMER PUST


TABLE 4

LIQUID EFFLUENTS - SSORTION OF ALL RELEASES

Third Fourth Est TotalUnit quarter quarter Error, X

A. Fission and activation products. Total release not including

tritium, gases, alpha)2. Average diluted concentration

during period

Ci

pCi/ml

4.64 E-1 1.23 E+0

1.94 E-9 5.10 E-9

2.1 E+1

3. Percent of applicable limit 4.39 E-2 .29 E-

B. Tritium. Total release

2. Average diluted concentrationduring period

3. Percent of applicable limit

. 9 E+2

pCi/ml 4.96 E-7

.65 E-2

1.63 E+2

6.74 E-7

2.25 E-2

.3 E+1

C. Dissolved and entrained gases

. Total release Ci 3.35 E-2 4.37 E-2 2.1 E+1

2. Average diluted concentrationduring period

3. Percent of applicable limituCi/ml 1.40 E-10 1.81 E-10

7.00 E-5 9.04 E-5

D. Gross alpha radioactivity. Total release Ci MDA MOA 6.0 E+

'echnical Specification 3.11.1.1 Limit

J00001. S EM -17-



TABLE 4 (Continued)

LIgUID EFFWEHTS - SO%ATION OF ALL RELEASES

Third Fourth Est TotalUnit quarter quarter Error, X

. Volume of waste released(prior to dilution)

. Volume of circulating saltwaterused during release

liters

liters

7.58 E+7

2.39 E+11

9.08 E+7 5.0 EO

2.42 E+11 6.6 EO

J00001.SEM -18-



TABLE 5

LIQUID EFFLUENTS

THIRD UARTER FOURTH UARTER

Nuclides Released UniONTINUOUS BAT H

MODE MODE

ONT IKUOUSMODE

BATCHMODE

antimony- 22

antimony- 24

antimony- 25

beryll ium-7

barium- 39

cerium- 39

cerium- 43

cerium- 44

Ci

Ci

Ci

MDA

MOA

MDA

MDA

MDA

MDA

MDA

MOA

MDA

2.8 E-4

7.03 E-3

.34 E-4

HDA

MDA

3.93 E-6

2.89 E-4

MOA

MDA

MOA

MDA

MDA

MDA

MDA

MDA

4. 9 E-5

3.2 E-5

7.32 E-3

4.05 E-4

5.26 E-8

2.66 E-6

MDA

4.77 E-4

cesium- 34

cesium- 36

cesium- 37

Ci

Ci

8.00 E-4

MDA

Ci 9.97 E-4

2.90 E-2

3.13 E-5

3.57 E-2

MDA 3.29 E-3

9.98 E-5 1.22 E-1

4.39 E-5 8.90 E-2

cesium-138

chromium-51

cobalt-57cobalt-58cobalt-60

Ci

Ci

Ci

Ci

Ci

MDA

MOA

MDA

9.14 E-5

MDA

MDA

4.15 E-3

4.75 E-4

4.86 E-2

7.38 E-2

MDA

MDA

MDA

MDA

MDA

3.66 E-10

MDA

8. 34 E-4

4.05 E-2

.29 E-1

iron-55iron-59lanthanum- 40

manganese-54

manganese-56

Ci

MDA

MDA

Ci 2.53 E-5

8.74 E-6

MDA

.99 E-

7. 7 E-4

7.78 E-4

1.46 E-2

MDA

MDA

MDA

MDA

MDA

MDA

7.07 E-

3.01 E-4

1.30 E-3

2.02 E-2

3.97 E-8

Kote:

'ncludes daughters

J00001. SEM -19-

k

e

DIABLO CANYON POMER PUNT


TABLE 5 (CONTINUED)

LIQUID EFFLUENTS

THIRD UARTER FOURTH UARTER

Nuclides Released

molybdenum-99

rubidium-86

si 1 ver- Om

sodium-24

strontium-89

strontium-90

strontium-9strontium-92

tln- 3

tin- ?m

tungsten-187

zirconium-95

Uni

Ci

Ci

Ci

Ci

Ci

Ci

Ci

0NT INUOUSMODE

MOA

MDA

HDA

HOA

MDA

MDA

MDA

MDA

MOA

MDA

BATCHHODE

.88 E-4

.03 E-4

8.77 E-5

6.62 E-4

9.82 E-4

3.57 E-5

7.92 E-7

2.40 E-4

MOA

.95 E-5

7.40 E-3

CONTINUOUSMODE

MDA

MDA

MDA

MDA

MOA

MDA

MOA

MOA

MDA

MDA

MOA

BATCHMODE

. 8E-3MDA

.54 E-3

7.89 E-4

5.61 E-4

2.29 E-6

.96 E-5

.82 E-7

5.01 E-4

MDA

5.32 E-5

6.15 E-3

zinc-65

iodine-131

iodine-132

Ci

Ci

Ci

MDA

1.22 E-4

MDA

2.84 E-4 MDA

2.22 E-6 HDA

2.56 E-2 9.07 E-4

.95 E-5

8.04 E-2

8.98 E-6

Note:

'ncludes daughters

J00001. SEM -20-

PjI

DIABLO CANYON POMER PUUIT

SEMIAHHUAL RADIOACTIVE EFFLUEHT RELEASE REPORT 1987

TABLE 5 (CONTINUED)

LIQUID EFFLUEHTS

HIRD UARTER FOURTH UARTER

Nuclides Released UniONTINUOUS

MODE

BATCHMODE

ONT INUOUSMODE

BATCHMODE

iodine- 33

iodine- 34

iodine-135

4.45 E-5

MDA

MDA

6.64 E-9

.08 E-3

MDA

MDA

9.98 E-3 3.84 E-4 .67 E-2

4.56 E-8

E-3

TOTAL FOR PERIOD Ci 2.09 E-3 4.62 E- .43 E-3 1.23 E+0

DISSOLVED AKD ENTRAINED GASES

xenon- 3 m

xenon- 33

xenon- 33m

xenon-135

krypton-85m

TOTAL FOR PERIOD

Ci

Ci

Ci

MDA

MDA

MDA

.65 E-5

MDA

.65 E-5

MDA

3. 6 E-2

3.22 E-5

.82 E-3

MDA

3.35 E-2

MDA

2. 9 E-4

MDA

.02 E-4

MDA

3.21 E-4

3.24 E-3

3.82 E-2

1. 1 E-6

1.94 E-3

MDA

4.34 E-2

J00001. SEM -21-

DIABLO CANYOH PNER PLAHT .

SEHIAHHUAL RADIOACTIVE EFFLUEHT RELEASE REPORT 1987

TABLE 6

LIQUID EFFLUEHTS - LOMER LIMITS OF DETECTIOH

Nuclide

antimony- 22

Unit

pimlLLD

E-8

antimony- 24

antimony- 25 .

beryllium-7barium- 39

cerium- 39

cerium-143

cerium- 44

cesium- 34

cesium-136

cesium- 37

cesium- 38

chromium-5

cobalt-57cobalt-58cobalt-60iron-55iron-59lanthanum- 40

manganese-54

manganese-56

molybdenum-99

rubi dium-86

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

p i/mlpCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

pCi/ml

.23 E-7

.06 E-7

2. 6 E-7

.80 E-7

2.70 E-8

.07 E-7

2.53 E-7

4.6 E-8

6. 2 E-8

4.65 E-8

5.09 E-8

2.50 E-7

3. 5 E-8

4.78 E-8

9.45 E-8

3.00 E-7

7.35 E-8

9.74 E-8

3.65 E-8

.42 E-6

2.32 E-8

3.26 E-7

Note:

'ncludes Daughters

J00001. S EM -22-

J J I ~J

~

~ ~J

~ ~ ~

~ o II

I I J~ J J

~ ~

~ ~ ~ ~ ~

~ ~e ~ ~

~ g

~ ~ ~ ~ ~

~ ~ ~

~ ~

~ ~

~ I

~ ~~ ~

~ I

~ i ~

~ ~ ~ I

DIABLO CANYON POWER PLAHT


TABLE 6 (CONTINUED)

LIQJID EFFLUENTS - LNER LNITS OF DETECTION

Nuclide

xenon- 3 m

xenon-133

xenon- 33m

xenon- 35

krypton-85m

Un tAC) ml

y 1/ml

ml

p 1 ml

pC1/ml

LLO

.05 E-6

9.56 E-8

3. 4 E-7

7.63 E-8

.82 E-7

Note:.

'ncludes daughters

IIIJ00001. SEM -24-

VIII. SOLID RADNSTE SHIPMENTS

1947S/0054K -25-

f



SOLID WASTE AND IRRADIATED FUEL SHIPMENT

A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1.- Type of Waste

a. Spent Resins, sludges

b.- Dry CompressibleWaste, ContaminatedEquip. Etc.

c. Irradi atedComponents, ControlRods, Etc.

d. Sand, BuildingRubble, BiologicalWaste

Unit

m'i

m'i

6-Month Period

1.24 E+11.16 E+2

1.13 E+21.59 E+0

0.00 EO

0.00 EO

0.00 EO

0.00 EO

Est. TotalError, X

10.0

10.0

H/A

N/A

2. Estimate of Major Nuclide Composition (by type of waste) '

a0

b.

c ~

d.

Fe-55Co-60Mn-54

Fe-55Co-60Co-58

NOT APPLICABLE

NOT APPLICABLE

303010

303030

N/A

N/A

J00001. SEM 25„


SENIAKHUAL RADIOACTIVE EFFLUEHT RELEASE REPORT 1987

SOLID WASTE AHD IRRADIATED FUEL SHIPMEHT

A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)(Continued)

3. Supplemental Information Required by T.S. 6.9.1.6

SolidificationAgent

Cement

Cene nt

ContainerType

Strong Tight

Strong Tight

ShippingPackage Type

Type B

Type B

Number of 10 CFR 61Containers Waste Class

Cement

Absorbent 7A Type A LSA>Type A

Strong Tight LSA>Type A

Absorbent

None

7A Type A.

7A Type A

7A Type A

LSA>Type A

Hone Strong Tight LSA>Type A

None

None

7A Type A

Strong Tight

7A Type A

LSA 38

4. Solid Waste Disposition

Number of Shi ments Mode of Trans ortation Destination

14 Truck Hanford, WA

B. Irradiated Fuel Shipments (Disposition)

Number of Shi ments Mode of Trans ortation Destination

NONE N/A N/A

J00001.SEM

IX. RADIATION DOSE DUE TO GASEOUS AND LIQUID EFFLUENTS

1947S/0054K -28-

A.

B.

RADIATION DOSES

Radiation doses due to radioactive liquid effluents

The radiation dose contributions due to releases of radioactive liquideffluents to the total body and each individual organ for the maximumexposed adult have been calculated in accordance with the methodology inthe Offsi te Dose Calculation Procedure. Dose contributions, listed inTable 7, show conformance with Technical Specification 3.11.1.2.

Radiation doses due to radioactive gaseous effluents

The radiation dose contributions due to radioactive gaseous effluents atthe site boundary for the land sectors have been calculated in accordancewith the calculational methodology in the Offsite Dose CalculationProcedure. Each unit's dose contribution has been calculatedseparately. The meteorology conditions concurrent with the time ofdischarge were used in these calculations. In addition to the siteboundary doses, the dose to all age groups at the nearest residencewithin the low population zone for each of the land sectors and a fivemile infant milk dose in each of the land sectors is included. Dosecontributions, listed in Table 8 which represents the maximum dose of agegroups, organs, and geographic locations for the third and fourthquarters, show conformance with Technical Specifications 3.11.2.2 and3.11.2.3.

D.

E.

Radiation doses due to direct radiation (Line-of-Sight Plus Sky-Shine)-Closest site boundary (800 m)

For the Third and Fourth Quarters of 1987, the radiation dose isevaluated to be 1.82 E-1 mrem due to the presence of radioactive wastecontainers outside of plant buildings.

Radiation Doses Due to Chemistry Laboratory Radioactive Gaseous Effluents— Closest Site Boundary (800m)

The radiation doses due to Chemistry Laboratory Radioactive GaseousEffluents for the report period is evaluated to be 1.70 E-6 mrem.

40 CFR 190 Considerations

The release of radioactivity in liquid and gaseous effluents during 1987resulted in doses that are small percentages of the technicalspecification limits as shown in Tables 9 and 10. This coupled with thefact that there are no other uranium fuel cycle sources within eightkilometers of the Diablo Canyon Nuclear Power Plant shows conformancewith 40 CFR 190.

1947S/0054K -29-

J

F. Radiation doses from radioactive liquid and gaseous effluents to membersof the public due to their activities inside the site boundary.

1. Liquid effluents

The radiation dose to members of the public within the site boundarydue to the release of radioactive liquid effluents is negligible.This is because the discharge piping for liquid radwaste is mostlyburied in concrete walls, is located in remote or inaccessible areasor is underground. In addition, the quantity of radioactivityreleased was very low during 1987.

2. Gaseous effluents

The radiation dose to members of the public within the site boundarydue to the release of radioactive gaseous effluents are listed inTable ll for the year of 1987.

1947S/0054K -30-

i

(

DIABLO CANYON NUCLEAR POWER PLANT


TABLE 7

RADIATIOH DOSE DUE TO THE RELEASE OF RADIOACTIVE LIQUID EFFLUENTS

millirem

ORGAN FirstQuarter

SecondQuarter

ThirdQuarter

FourthQuarter

AnnualTotal

Total Body

Bone

LiverThyroid

Kidney

Lung

G. I. LLI

.25 E-3 .95 E-3

3.55 E-3 3.97 E-3

3.27 E-3 4.09 E-3

4.60 E-3 3.25 E-3

2.47 E-4 3.56 E-4

.40 E-3 .55 E-3

6. 0 E-3 2.2 E-2

.53 E-3 4.73 E-3

5.79 E-3 2.06 E-2

4.57 E-3 .55 E-2

.55 E-3 4.76 E-3

2.64 E-4 6.37 E-4

2. 8 E-3 7.76 E-3

8.65 E-3 .48 E-2

9.46 E-3

3.39 E-2

2.74 E-2

.42 E-2

.50 E-3

.29 E-2

5.17 E-2

CKII

J00001. SEM -31-



TABLE 8A

RADIATION DOSE'UE TO THE RELEASE OF RADIOACTIVE GASEOUS EFFLUEH'FS (UHIT 1)

First quarter Second quarter

S te Boundary

Sector'ose Sector Dose

Noble GasGamma air dose mradBeta air dose mrad

I PT'hild'Thyroid) mrem

NW

NW

NNW

4.94 E-31.01 E-2

1.42 E-4

HNE

NNE5.01 E-38.72 E-3

1.22 E-3

Residence


~IP TChild'Thyroid) mrem

HNW

NNW

ESE

6.59 E-41.17 E-3

1.80 E-4 ESE

2.25 E-44.03 E-4

1.12 E-3

Five Mile Dairy

I PTInfant (Thyroid) mrem ESE 2.77 E-4 ESE 1.32 E-3

J00001. SEM -32-



TABLE 8A (Continued)

RADIATION DOSE DUE TO THE RELEASE OF RADIOACTIVE GASEOUS EFFLUENTS (UNIT 1)

Third quarter Fourth quarter Annua1 Tota1

Site Boundary

Sector'ose Sector Dose Sector Dose


I P T3

Child'Thyroid) mrem

NNW

NNW

7.19 E-31.61 E-2

2.40 E-3

NW

NW

2.15 E-24.70 E-2

2.26 E-3

NW

NW

NNW

3.18 E-26.98 E-2

4.15 E-3

Residence


I PTChild'Thyroid) mrem

NNW

NNW

ESE

8.54 E-41.96 E-3

2.96 E-3

NNW

NNW

NNW

1.90 E-34.05 E-3

7.56 E-4

NNW

NNW

ESE

3.55 E-37.46 E-3

4.70 E-3

Five Nile Dairy

I PTInfant (Thyroid) mrem ESE 6.05 E-3 ESE 5.10 E-4 ESE 8.16 E-3

J00001. SEA -33-



TABLE 88


First Quarter Second Quarter

ite Boundary

Sector'ose Sector Dose

Noble GasGamma air dose mradBeta air dose mrad-I PT5Child'Thyroid) mrem

NW

NW

NW

2.80 E-25.73 E-2

2.62 E-3

SESE

NNW

2.71 E-38.08 E-3

1.42 E-3

Residence


I P TChild'Thyroid) mrem

NNW

NNW

NNW

8.28 E-42.31 E-3

1.88 E-3

ESEESE

ESE

3.43 E-41.02 E-3

2.91 E-3

Five Nile Dairy

IPTInfant (Thyroid) mrem 2.74 E-3 ESE 4.40 E-3

F00001. SEM '34

DIABLO CANYON NUCLEAlt POWER PLANT


TABLE 8B (Continued) ~ ~


Site Boundary

Third quarter

Sector~ Dose

Fourth quarter

Sector Dose

~ Annual Total

Sector Dose


I P TIChild'Thyroid) mrem

7.26 E-31.48 E-2

4.26 E-3

ENE

ENE

ENE

4.29 E-31.01 E-2

1.22 E-3

NW

NW

3.70 E-27.85 E-2

6.58 E-3

Residence


I PTChild'Thyroid) mrem NNW

6.27 E-41.31 E-3

1.70 E-3

NNW

NNW

3.89 E-41.04 E-3

1.28 E-4

NNW

NNW

ESE

1.99 E-35.09 E-3

7.52 E-3

Five Nile Dairy

I P TInfant (Thyroid) mrem 2.18 E-3 ESE 3.78 E-3 ESE 1.16 E-2

J00001. SEH -35-

DIABLO CANYON NUCLEAR POWER PLANTSEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987

TABLE 8 (Continued)

NOTES:

l. This represents the maximum dose of age groups, organs, and geographiclocations for the quarter.

2. The ocean sectors SSE, S, SSH, SH, WSH, H, and HNH are not included.

3. Radioiodines, Radioactive Material in Particulate Form and RadionuclidesOther Than Noble Gases With Half-lives Greater Than Eight Days.

4. The inhalation, ground plane and animal-meat pathways are included inthis dose calculation.

5. The inhalation, ground plane, animal-meat and vegetable pathways areincluded for this location. An occupancy factor of 0.5 was used for theinhalation and ground plane pathways. The child age group had thehighest calculated dose for this. location.

1947S/0054K -36-

e

4

q4



TABLE 9

PERCEHT OF TECHNICAL SPECIFICATION LIHITS~ FOR RADIOACTIVE LIQUID EFFLUENTS

ORGAN

Total Body

FirstQuarter

8.33 E-2

SecondQuarter

.30 E-

percent

ThirdQuarter

.02 E-

FourthQuarter

3. 5 E-

AnnualTotal

3. 5E-Bone

Liver'hyroid

Kidney

Lung

7. 0 E-2

6.54 E-2

9.20 E-2

4.94 'E-3

2.80 E-2

7.94 E-2 . 6 E-

8. 8 E-2 9. 4 E-2

6.50 E-2 3.10 E-2

7.12 E-3 5.28 E-3

3. 0 E-2 4.36 E-2

4. 2 E-1

3. OE-

9.52 E-2

1.27 E-2

.55 E-

3.39 E-

2.74 E-

.42 E-

.50 E-2

1.29 E-1

G. I. LLI 1.22 E- 4.42 E- .73 E- 2.96 E-1 5. 7 E-

Note:

'echnical Specification 3.11. 1.2

J00001. SEA -37-

DIABLO CANYON NUCLEAR f'OWER PLANT

SEMIANHUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987

TABLE 10A

PERCENT OF TECHNICAL SPECIFICATION LIMITS FOR RADIOACTIVE GASEOUS EFFLUENTS (UNIT 1)


Site Boundary

Noble GasGambia air dose mradBeta air dose mrad

I PTG01d (Thyroid) mrem

Sector

NW

NW

I ofT.S. Limit

9.88 E-21.01 E-1

1.89 E-3

Sector

NNE

NNE

ofT.S. Limit

1.00 E-18.72 E-2

1.63 E-2

Residence

mradmrad

Noble GasGamma air doseBeta air dose

~IP TChild (Thyroid) mrem

NNW

NNW

ESE

1.32 E-21.17 E-2

2.40 E-3 ESE

4.50 E-34.03 E-3

1.49 E-2

Five Mile Dairy

~IP TInfant (Thyroid) mrem ESE 3.69 E-3 ESE 1.76 E-2

Note:

'echnical Specification 3.11.2.2 and 3.11.2.3

F00001. SEM -38-

I .Q

DIABLO CANYON NUCLEAR f'OWER PLANT


TABLE 10A (Continued)

PERCENT OF TECHNICAL SPECIFICATIOH LIHITS FOR RADIOACTIVE GASEOUS EFFLUENTS (UNIT 1)

Third quarter Fourth quarter Annual Total

ite Boundary


~IP TTeen (Thyroid)

Sector

NNW

HNW

X ofT.S. Limit

1.44 E-11.61 E-1

3.20 E-2

Sector

NW

NW

NW

X ofT.S. Limit

4.30 E-14.70 E-1

3.01 E-2

Sector

HNW

X ofT.S. Limit

3.18 E-13.49 E-1

2.77 E-2

Res dence


I PTChild (Thyroid)

NHW

HNW

ESE

1.71 E-21.96 E-2

3.95 E-2

NNW

NNW

NNW

3.80 E-24.05 E-2

1.01 E-2

HNW

NNW

ESE

3.55 E-23.73 E-2

3.13 E-2

Five Nile Dairy

IPTInfant (Thyroid) ESE 8.07 E-2 ESE 6.80 E-3 ESE 5.44 E-2

Note:

'echnical Specification 3.11.2.2 and 3. 11.2.3

J00001. SEM -39-


SEMIANNUAL RADIOACTIVE EFFLUENf RELEASE REPORT 1987

TABLE 108

PERCENT OF TECHNICAL SPECIFICATION LIMITS FOR RADIOACTIVE GASEOUS EFFLUENTS (UNIT 2)


te oun aryo e as

amia air dose mradBeta air dose mrad

IPTCh 1d (Thyroid) mrem

Sector

NW

NW

'X ofT.S. Limit

5.60 E-15.73 E-1

3.49 E-2

Sector

SESE

X ofT.S. Limit

5.42 E-28.08 E-2

1.89 E-2

es ence

o e asGama air dose mradBeta air dose mrad

I PTCh 1d (Thyroid) mrem

1.66 E-22.31 E-2

2.51 E-2

ESEESE

ESE

6.86 E-31.02 E-2

3.88 E-2

ve e a ryT

Infant (Thyroid) mrem 3.65 E-2 ESE 5.87 E-2

Note:


J00001.SEW -40-

P


SEHIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i987

TABLE 10B (Continued)

PERCENT OF TECHNICAL SPECIFICATION LIHITS FOR RADIOACTIVE GASEOUS EFFLUENTS (UNIT 2)

Third quarter Fourth quarter Annual Total

Site Boundary


~IP TChild (Thyroid)

Sector X ofT.S. Limit

1.45 E-11.48 E-1

5.68 E-2

Sector

ENE

ENE

ENE

X ofT.S. Limit

8.58 E-21.01 E-1

1.63 E-2

Sector X ofT.S. Limit

3.70 E-13.93 E-1

4.39 E-2

Residence


I PTChild (Thyroid)

NNW

NNW

NNW

1.25 E-21.31 E-2

2.27 E-2

NNW

NNM

NNM

7.78 E-31.04 E-2

1.71 E-3

NNW

NNW

< ESE

1.99 E-22.55 E-2

5.01 E-2

Five Hile Dairy

I P TInfant (Thyroid) 2.91 E-2 ESE 5.04 E-2 ESE 7.73 E-2

Note:


J00001. SEH -41-

Wt4



TABLE iiA

RADIATION DOSE DUE TO RELEASE OF RADIOACTIVE GASEOUS EFFLUENTSFIRST QUARTER, 1987

ONSITE DOSE TO MEMBER OF THE PUBLICSPECIAL INTEREST GROUPS

EXTERNAL DOSE (MREM)INTERNAL

DOSE (MREM)

NOBLE GAS IODINES, PARTICULATES, AND TRITIUM

SPECIFICACTIVITY

EXPO URE EXPOSURELOCATION CLOSEST(SECTORS) DISTANCE

EXPOSURETIME

(HOURS)WHOLE BODY SKIN GROUND PLANE INHALATION

Pol ce atshooting range

Tour Partic pants

(a) Simulator Bldg.

(b) Bio Lab

(c) Overlook

American Ind ansat burial grounds

Ranch hands drivingcattle around site

SE

SSE

NW

NNW

NW

NNW

N

NNE

NE

700m

320m

700m

200m

200m200m

250m350m320m450m630m

52

1.0

1.5

0.25

2424

0.250.250.250.250.25

1.22 E-4

1.35 E-5

2.32 E-3

1.86 E-5

2.62 E-4

2.89 E-5

5.08 E-3

4.08 E-5

2.95 E-7

3.19 E-8

9.02 E-7

6.98 E-9

3.82 E-5

4.29 E-6

3.31 E-4

2.67 E-6

F00001. SEM -42-

0vtf

DIABLO CANYON NUCLEAR 00'WER PLANT


TABLE 11B

RADIATION DOSE DUE TO RELEASE OF RADIOACTIVE GASEOUS EFFLUENTSSECOND QUARTER, 1987


EXTERHAL DOSE (MREM)

NOBLE GAS

INTERDOSE (MREM)

IODINES, PARTICULATES, AND TRITIUM

SPECIFICACTIVITY

Police atshooting range

Tour ParticiPants

(a) Simulator Bldg.

(b) Bio Lab

(c) Overlook

American Indiansat burial grounds


EXPOSURELOCATION(SECTORS)

SE

SSE

NW

HNW

NW

NNW

N

NNE

NE

EXPOSURE

CLOSESTDISTANCE

700m

320m

700m

200m

200m200m

250m350m320m450m630m

EXPOSURETIME

(HOURS)

52

1.0

1.5

0.25

2424

0.250.250.250.250.25

WHOLE BODY

3.18 E-4

3.50 E-5

2.87 E-4

3.86 E-6

SKIN

7.21 E-4

7.95 E-5

6.11 E-4

8.05 E-6

GROUND PLANE

3.25 E-4

3.49 E-5

4.23 E-5

5.75 E-7

INHALATION

1.50 E-5

2.28 E-4

2.63 E-6

F00001. SEM -43-



TABLE 11C

RADIATION DOSE DUE TO RELEASE OF RADIOACTIVE GASEOUS EFFLUENTSTHIRD QUARTER, 1987


EXTERNAL DOSE (MREM)

NOBLE GAS

INTEDOSE (MREM)

IODINES, PARTICULATES, AND TRITIUM

SPECIFICACTIVITY


Tour Participants

(a) Simulator Bldg.

(b) Bio Lab

(c) Overlook



EXPO URE

LOCATION(SECTORS)

SE

SSE

NW

NNW

NW

NNW

N

NNE

NE

EXPOSURECLOSESTDISTANCE

700m

320m

700m

200m

200m200m

250m3SOm

320m4SOm

630m

EXPOSURETIME

(HOURS)

52

1.0

1.5

0.25

2424

0.250.250.250.250.25

WHOLE BODY

3.73 E-4

4.07 E-5

1.23 E-3

1.16 E-5

SKIN

8.13 E-4

8.90 E-5

2.57 E-3

3.39 E-5

GROUND PLANE

2.56 E-5

2.75 E-6

2.04 E-5

1.93 E-7

INHALATION

1.01 E-4

1.40 E-5

3.54 E-4

4.00 E-6

J00001. SEM -44-

SPECIF ICACTIVITY


Tour Participants

(a) Simulator Bldg.

(b) Bio Lab

(c) Overlook



F00001. SEM

DIABLO CANYON NUCLEAR l'OWER PLANT


TABLE 11D

RADIATION DOSE DUE TO RELEASE OF RADIOACTIVE GASEOUS EFFLUENTSFOURTH QUARTERi 1987


INTER ALDOSE (MREM)EXTERNAL DOSE (MREH)

NOBLE GAS IODINES, PARTICULATES, AND TRITIUM

EXPOSURE EXPOSURELOCATION CLOSEST(SECTORS) DISTANCE

EXPOSURETIME

(HOURS)WHOLE BODY SKIN GROUND PLANE INHALATION

9.39 E-44.32 E-4700mSE 6.22 E-652 7.20 E-5

1.0320m

9.29 E-66.76 E-71.01 E-44.65 E-51.5700mSSE

0.25200m

200m200m

2424

NW

NNW 7.35 E-6 2.36 E-43.29 E-31.54 E-3

NW

NNW

N

NNE

NE

250m350m320m450m630m

0.250.250.250.250.25

3.20 E-5 2.24 E-61.48 E-5 5.57 E-8

-45-

X. HETEOROLOGICAL DATA

1947S/0054K — 46-

METEOROLOGICAL DATA

The hour-by-hour listing of wind speed, wind direction, atmosphericstability and precipitation is being submitted on magnetic tape inaccordance with Technical Specification 6.9.1.6.

1947S/0054K -47-

ATTACHMENT 1

1947S/0054K - 48—

ATTACHMENT 1

MAJOR CHANGES TO LIQUID, GASEOUS AND SOLID RADHASTE TREATMENT SYSTEM

1947S/0054K -49-

y U

Di scussion of Design ChangeDCO-SM-35781

Unit 1 Monitor Tanks Conversion toLaundry/Distillate Tanks

Page 1 of 2

ITEM: a.

RESPONSE:

ITEM: b.

A summary of the evaluation that led to the determination thatthe change could be made in accordance to 10 CFR 50.59.

The existing Unit 1 Monitor Tanks were designed to receiveradioactive liquids. The conversion to enable these tanks toreceive Laundry drains in addition to evaporator distillate hasnot created the possibility for an accident or malfunction of atype not previously evaluated in the FSAR. These tanks retainthe same ventilation to the offgas system and auxiliary buildingspill retention as before. The function of the tanks will be toreceive waste streams which are currently collected in similarunshielded tank rooms.

Sufficient detailed information to totally support the reasonfor the change without benefit of additional or supplementalinformation.

RESPONSE:

ITEH: c.

RESPONSE:

ITEH: d.

RESPONSE'947S/0054K

This design change increases laundry wet washing capacity withexisting equipment. The Unit 1 Monitor Tanks were originallyprovided to receive evaporator distillate from the Boric AcidRecovery System. Since distillate could not be recovered fromthese tanks due to dissolved oxygen, low conductivity distillateis sent directly to the Primary Hater Storage Tanks and thevolume of distillate released has been greatly decreased. Theexpansion of laundry drain collection capacity enables greaterflexibilityfor processing laundry during outages.

A detailed des cripti on of the equipment, components andprocesses involved and the interfaces with other plant systems.

The tank conversion required the installation of interconnectingpiping, valves and controls to permit diversion of laundrydrains into the Laundry/Distillate Tanks (LDTs). The dischargeof the LDTs was diverted from the Processed Haste Receivers tothe inlet header of the overboard filters.An evaluation of the change which shows the predicted releasesof radioactive materials in liquid and gaseous effluents and/orquantity of solid waste that differ from those previouslypredicted in the license application and the amendments thereto.

There will be no increase in liquid release due to this change.Any increase volume of Laundry drain liquid will be offset bythe volume of distillate recovered which could not be recoveredin the past. Failure or overflow of the tanks will result inliquid flow to the auxiliary building sump for collection andfurther treatment. No increase in the gaseous effluentspredicted will result due to this change since the contents ofexisting drain collection tanks are degassed and vented. Thischange will not effect the quantity of solid waste since onlystorage capacity is added.-50-

'C

Discussion of Design ChangeDCO-SH-35781

Unit 1 Honitor Tanks Conversion toLaundry/Distillate Tanks

Page 2 of 2

ITEH: e.

RESPONSE'TEH:

An evaluation of the change which shows the expected maximumexposures to individuals in unrestricted areas or to the generalpopulation that differ from those previously estimated in thelicense application and amendments thereto.

Plant processing capabilities are similar with or without thischange. This change has no effect on plant discharges.

A comparison of the predicted releases of radioactive materials,in liquid and gaseous effluents and in solid waste, to theactual releases for the period prior to when the changes aremade.

RESPONSE'here is no change in the predicted releases of radioactivematerials.

ITEH: g.

RESPONSE:

ITEH: h.

RESPONSE:

An estimate of the exposure to plant operating personnel as aresult of the change.

This change results in no change in the estimated radiationexposure to plant operating personnel. The unshielded LDT roomis similar to the existing Laundry/Hot Shower drain tank room.

Documentation of the fact that the change was reviewed and foundacceptable by the PSRC.

This design change was approved by the PSRC on October 13, 1987.

1947S/0054K - 51-

T

Discussion of Design Change

Shredding of Solid Radwaste

Page 1 of 2

ITEM: a.

RESPONSE'TEM:

b.

A summary of the evaluation that led to the determination thatthe change could be made in accordance to 10 CFR 50.59.

The 10 CFR 50.59 evaluation considered that the shredding systemwould process ll Ci of waste. It was assumed that 25'L of thewaste activity would become airborne requiring filtration by theintegral shredding HEPA filter system. The offsite release dueto waste shredding was calculated to be 0.3'X of Tech. Spec.limits. Based upon this calculated predicted release andmonitoring of the effluent, it was determined that the changecould be made without affecting offsite releases.

Sufficient detailed information to totally support the reasonfor the change without benefit of additional or supplementalinformation.

RESPONSE:

ITEM: c.

RESPONSE'TEM:

d.

RESPONSE:

A mobile shredding system service was procured to process.DANand cartridge filters. This service was procured to ascertainthe volume reduction which could be achieved for each of thesewastes. A DAN density increase from 33 lb/ft3 to 38 lb/ft3 anda VR of 4 for filters was anticipated. Substantial disposalcost savings based on the reduced waste volume was the majorreason to procure shredding services.

A detailed description of the equipment, components andprocesses involved and the interfaces with other plant systems.

The self, contained shredding trailer consisted of a remote wastefeed section, two stage shredder, waste loadout station,integral shredder HEPA filter system, trailer ventilation. HEPA

system, a common stack with a sampler and a fire protectionsystem. Electric power was the only interface to the trailer.Bagged waste was delivered to the trailer and bagged shreddedwaste was removed from the trailer and packaged using in-plantcompactors.

An evaluation of the change which shows the predicted releasesof radioactive materials in liquid and gaseous effluents and/orquantity of solid waste that differ from those previouslypredicted in the license application and the amendments thereto.

The 10 CFR 50.59 evaluation predicted no liquid releases and0.3X of the Tech. Spec. limit as the change in the gaseousrelease. No quantity of solid waste reduction was predicted inthe 50.59 evaluation because the actual VR was unknown anddetermining the VR was the reason the service was procured.

1947S/0054K -52-

Discussion of Design Change

Shredding of Solid Radwaste (Continued)7

Page 2 of 2

ITEM: e.

RESPONSE'TEM:

An evaluation of the change which shows the expected maximumexposures to individuals in unrestricted areas or to the generalpopulation that differ from those previously estimated in thelicense application and amendments thereto.

As discussed above, the maximum offsite exposure to individualsin unrestricted areas or to the general population is negligible.

A comparison of the predicted releases of radioactive materials,in liquid and gaseous effluents and in solid waste, to theactual releases for the period prior to when the changes aremade.

RESPONSE: No change in liquid release and a reduction in solid waste waspredicted. An increase in gaseous effluents of 0.3'L of Tech.Spec. limits was predicted.

ITEM: g.

RESPONSE:

ITEM: h.

RESPONSE:

An estimate of the exposure to plant operating personnel as aresult of the change.

The estimate exposure to plant operating personnel due tooperation of the shredder system was 800m Man-Rem.

Documentation of the fact that the change was reviewed and foundacceptable by the PSRC.

Revision 8 of Procedure AP C-257 was approved by the PSRC onAugust 7, 1987.

1947S/0054K -53-

ATTACHHENT 2

1947S/0054K -54-

ATTACHHENT 2

CHANGES TO THE PROCESS CONTROL PROGRAM

1947S/0054K -55-

t@'b

PACIFIC GAS AHD ELECTRIC CCHPANY

DEPARTMENT OF NUCLEAR POWER GENERATION

DIABLO CANYOH POWER PLANT

NMER AP C-253

REVISION 8

PA6E 1 OF 6UH ITS

ADMINISTRAT IVE PROCEDURETITLE: PROCESS CONTROL PR06RAM

APPROVED: / PLAH MANA R

1.0 SCOPE

REFiR TO RECORDS i:.~'i~"Elilr'.TFOR LATCBT 6"-".

i".'he

purpose of the Process Control Program (PCP) 1s to define thenecessary program guidance used at DCPP to ensure that SOLIDRADIOACTIVE HASTE MANAGEMENT activ it1es, 1n packag1ng radioactive~aste for d1sposal, conform to the Code of Federal and StateRegulations and the Waste Bur1al 51te License Cr1ter1a.

1.2 This procedure and changes thereto require PSRC review.

2.D RESPONSIBILITIES

2.1 Plant Manager has the overall responsibil1ty for the SolidRadioactive Haste activities at OCPP.

2.2 Manager of Chemistry and Radiation Protection is responsible forthe implementation of the requ1rements of this procedure.

2.3 Radwaste Engineer is responsible for the development andimplementation of procedures relat1ng to the requ1rements of thisprocedure.

=.4 QC is responsible for verification of compliance with the Qualityrequirements.

3.1 This procedure with the attachments and any changes theretorequires revie~ by the Plant Staff Revie~ Conaittee and subm1ssionta the US NRC 1n the Semi-annual Effluent Report for the period 1nwhich the changes. were made.

00158808.01a 11


I I ILE: PROCESS CONTROL PROGRAH

NEER AP C-253REVISION'PAGE 2 OF 6

UN ITS 1 AND 2

4.0 INSTRUCT IOHS

4. 1 GEHERAL

It is the policy of Pacific Gas and Electric Company toconsc1entiously apply emphas1s and attention to those activitiesassociated with generat1on, processing, packaging, storage anddisposal of radioactive waste generated at the Diablo Canyon PowerPlant and to maintain a high level of assurance that radioactivewaste products meet or exceed the applicable Federal and Stateregulations and the Radioact 1ve Waste Bur1al Site License. Criteria.

4.2 MET WASTE

4.2.1 LIQUID/WET WASTE .

Liquid / 'Met wastes at DCPP are processed to a cond1tionmeeting shipping and disposal criteria. These criteria1nclude requ1rements for imaobilization, stabil1ty andlimits on Free Standing Mater (FSW). Specificinstructions on processing and required FSM limits arecontained in plant procedures and/or qualified vendorprocedures. These procedures are to be approved by thePSRC prior to implementation.

4.2.2 CONTAINERS, SHIPPING CASKS AHD PACKAGING

Solid radioactive waste is processed,'ackaged and shipped1n accordance with DCPP procedures and/or qualified vendorprocedures which have been approved by the PSRC. Theseprocedures provide specific instructions wh1ch ensure thecontainer, shipping casks and packaging methods complywith the applicable Code of Federal Regulations, StateRegulations and the Radioactive Waste Burial S1te LicenseCr1ter 1 a.

4.2.3 SHIPPIHG AHD DISPOSAL

Solid radioactive waste is prepared, loaded and shipped toa Federal and/or State Licensed Radioactive Waste DisposalFacility (Burial Ground) in accordance with DCPPprocedures and/or qualified vendor procedures which havebeen approved by the PSRC. These procedures providespec1f 1c instructions which ensure the shipments meet the1ntended Burial Site License Requ1rements as well asapplicable Federal and State Regulations.

00158808.01a 2l

::>SLY CANYON 9(k R?l>JI'l

ll f: PROCESS CCXT~OL W9,;?M

NLISER AP C-253RE V I S ION 8PAGE 3 OF 6

UN I TS \ ANO 2

~ g ~~ ~ g ~ 4 BURY M.X ING OF SAMPLES

Oualified vendor procedures approved by the PSRC prov1dewritten instructions on sampling, processing and handl1ngwaste for the determination of process parameters prior totne actual full scale solidificat1on. These procedurescontain the description of the laboratory mixing methodsused for these samples.

4 2.5 SOLIDIFICATION PROCESS

Oualified vendors used by OCPP for radioact1ve wastesolid1fication are required to provide the Process ControlProgram and written procedures. These procedures andchanges thereto must be approved by the PSRC pr1or to use.Further, the vendors are required to have a top1calreport, as referenced, on the waste forms which will besolid1fied at OCPP. This topical report shoulddemonstrate compliance with the NRC requirements for wasteform. These documents should include:

a.b.C.d.e.f.

Oescription of the solid1ficat1on processType of sol id1f icat1on usedProcess control parametersParameter boundary conditionsProper waste form propertiesSpec1fic instructions to ensure the systems areoperated within established process parameters.

4.2.6 SAMPLING PROGRAH FOR SOLIDIF ICATION

Vendors, utilized by OCPP for radioactive ~astesolidification, are required to include 1n the1r approvedprocedures, requirements to sample at least every tenthbatch of the same ~aste type to ensure solid1fication andto provide actions to be taken if a sample fails to verifysolidification. After a test spec1men failure, initialtest specimens from three consecutive batches of thatwaste type must demonstrate solidif1cat1on before testingrequirements of every tenth batch can be resumed.Verif1cation of such sampling 1s to be accomplished bycomplet1ng Form 69-10350, "Process1ng Control Program(PCP) Verification". These forms will be maintained inthe Chemistry and Radiation Protect1on Oepartment and theRecords Management System (RHS). These procedures andchanges thereto must be approved by the PSRC pr1or to use.

00158808.01a 31

....'LOLQ whiYON I~IWLR PL&I

l IILE: PROCESS CONTROL PROGRAM

Nu&ER AP C 253RE V IS ION 8PAGE 4 OF 6

UNITS I AND 2

4.3

.2.7 WASTE FORH VERIF ICATION

Vendors '.ilized by OCPP to process wet wastes arerequired to include in their procedures provisions toverify that the solidification and/br FSW Criteria in theFederal and State regulations and the Burial Site LicenseCriteria are met for the spec1fic type of waste beingprocessed. These procedures and changes thereto must beapproved by the PSRC prior to use.

4.2.B CORRECTIVE ACTIONS FOR FREE STANDING WATER

Vendors utilized by DCPP to process wet wastes arerequired to include in their approved proceduresprovisions for correcting processed waste in which freestanding ~ater in excess of the FSW Criteria is detected.These procedures and changes thereto must be approved byzhe PSRC prior to use.

4.2.9 EXOTHERHIC PROCESSES

Vendors utilized by OCPP for radioactive wastesolidification are required to include in their approvedprocedures specific process control parameters forexothermic solidification methods that must be met beforecapping the container. These procedures and changesthereto must be approved by the PSRC pr1or to use.

OILY WASTE

4 ~ 4

Oily wastes at OCPP are processed in accordance with approvedvendor procedures. These procedures specify the proper methods totreat oily wastes to comply with Federal and State regulations andapplicable Burial Site License Criter1a. These procedures andchanges thereto must be approved by the PSRC prior to use.

SPEGIAL CASES

Based upon previous industry experience, OCPP foresees thepotent1al for situations arising that may be beyond existing plantcapabilities. Anticipating this possib1 11 ty, provisions are madeherein to accomnodate such situations in a timely manner by usingspecial techniaues or processes. These special cases would becont ~o l l ed as fo l low s:

OOI58808.0la 41

f

DlADLO CANYON PCxER PLANT~ ~T

i I TI.E: PRiXESS CONTROL PRGGRAM

KQCER AP C-253C VISION 8PAGE 5 OF 6

UN ITS 1 AND 2

4.5

,4.4.1 Implementing procedures would be developed comparable tothose used for normal plant solid waste activities basedon the guidance of this PCP and incorporating theapplicable provisions for process control and testing.

4.4.2 The implementing procedure would receive PSRC approvalprior tc use.

4.4.3 Use of this provision and supporting information would beincluded in the next Semi-annual Effluent Report to theHRC.

REHED I AL ACT IDHS

iIII

4.5.1

4. 5.2

5 0 PEFERENCES

For waste forms which do not meet Federal, State andburial site regulations and requirements, suspension ofshipment of the inadequately processed ~aste andcorrection of the PCP, procedures or processing equipmentshall be performed as necessary to prevent recurrence.

For waste forms not prepared in accordance with the PCP,teSting Of the waSte tO Verify Shipping and burial Siterequirements sha 11 be perf'ormed and appropriateadministrative action taken to prevent recurrence.

5. 1 Title 10 Code of Federal Regulations

5.2 NUREG 0472 and 0473

5.3 NUREG-0800, 11.4 US NRC Standard Review Plan Solid WasteManagement Systems

5.4 AP C-253S1, "Dewatering Control Program."

5.5 AP C-257, "Mobile Service Operating Procedure for Low-LevelRadioactive 'Haste Processing."

6.0 ATTACHMENTS

6. 1 Chem-Nuclear Systems, Inc. Procedure SD-OP-003-482, "ProcessControl Program for CHS I Cement Solidification Units at DiabloCanyon," Rev. A.

00158808.01a 5I

0

liIABIO CANYON POL'ER PL/dtI

T I ILE: PROCESS CONTROL PROGRAM

NURSER AP C-253RE VISION 8

'AGE6 OF 6

UN I TS 1 AND 2

6.2

6.3

6.4

6.5

Topical Report CNSI-2 (4313-01354-01P-A), "Chem-Nuclear Systems,Inc. Mobile Cement Solidification System", Rev. 2.

Chem-Nuclear Systems, Inc. Procedure SD-OP-026, "Process ControlProgram for the Cement/011 Solidification", Rev. B.

Chem-Nuclear Systems, Inc. Procedure SD-OP-053, "Process ControlProgram for the CNSI Acid Solidification", Rev. A.

Chem-Nuclear Systems, Inc. Procedure SD-OP-068-482, "CalibrationCheck Procedure for the Triple Beam Balance at Diablo Canyon,"Rev. Original.

NOTE: The above attachments are maintained in Document ControlMaster File, Catalog No. TK 9400/CNSI-2A andTK 9400/CNS I -2A-1.

Form 69-10350, "Process Control Program {PCP) Verification"~

11/85.

00158808.0 I a 6 I

59 10350 I I /8»PACI F I C GAS ANO. ELECTRIC COHPANY

DIABLO CAN'iON POWER PLANT UNIT NOS. 1 ANO 2

Page 1 of 1

'. ILK: PROCESS CONTROL PROGRAM 'P".P'ERIFICATION

I

OATE WASTE BATCH PCP

1 II NOTES ( OPERATOR tVERIFIERI

Number ype assed

00158808.01a 7 I

vA(:.r iL,A:i wli) L! ( „:~:.„L.&lAH ~

0'ARIA'RT Qt NUCLEAR P~WLR GLkt i'llIGH

UlABLO CAHYUIL POWER PLANT

NEER AP C-253S IRE VIS ION IPA6E I OF 2

UHIT S

ADHIHl STRATI VE PROCEDURETl ILE: DEWATERIHG CONTROL PROGRAH

] NI0

APPROVED:PLAN HAHA R

A'-'7-g7DA

1.0 SCOPE

REFER TrI R"rclRQ.-; ~ ...:," - ~ ~ =y;I',iR AT'T .""= ":".'i

l. 1 The purpose of the Dewatering Control Program is to assure thatall dewatering of vendor vessels meets State and FederalRegulations as well as Burial Site Cr1teria for Free StandingWater (FSW).

1.2 This Dewatering Process Control P~ogram applies to all vendorsystems, pressure vessels and 11ners contain1ng ion exchange andf11 ter media.

1.3 This procedure and changes thereto requ1re PSRC review.

2.0 DISCUSSIOH

2. 1 The dewatering system consists of a pump with necessary hoses forconnection to the pressure vessel or 11ner and to the drain orcollection point. Pressure vessels or liners supplied by a vendorare preassembled w1th a hub and/or lateral assembly for dewateringand med1a retent1on. Procedures for dewatering are dependent onthe material to be dewatered and/or the pressure vessel or linersize.

2.2 These procedures, spec1fic to vessel and material provideinstruct1on for the pumping and settl1ng time sequences as wellas; pump rate, total times pumped, and acceptance criteria.Additional contingenc1es are provided for vessels or linersrequiring further steps to meet acceptance criter1a and the meansOf VerifiCat1On Of COmplianCe. HethadS fOr reCOrding dewateringdata are included in the specific procedure.

3.0 RESPONSIBILITIES

3. 1 The Manager of Chem(sary and Radiation Protect1on is respons1blefor 1mplementation of the requirements of this program.

00302901.01a I I

::Qadi:~ 'RYQN I'WI w PLAN I NOSER AP C-253SIREVI SION IPAGE 2 Of 2

i ii ': .pE W i<A~ CDN I'ail P~iGRAHUN I TS 1 AND 2

Namaste E ng ineer ' respons ib le for imp lementat1on of thepr CeoureS relating to:."e requirements of this program.

~1.0 INSTRUCT IONS

4.1 The Oewatering Control Program for Carbon Steel (CS), HighIntegrity Container (HIC), and Fiberglass Re1nforced Plastic (FRP)vessels, shall onsist of DCPP PSRC approved procedures.

4.2 These procedures contain the specific instructions for:

4.2.1 Pumping Time Cycles4.2.2 Puay Rate4.2.3 Total Time to be Pumped4.2.4 Acceptance Criteria of FSW

4.2.5 Documentation and Records of Dewater1ng Act1v1t1es

4.3, These procedures also specify the size of vessels and media thatmay be dewatered. Contingencies are provided for additional stepsthat may be necessary to meet FSW criteria.

4 ~ 4 GENERAL CONTROL PARAMETERS

4.4.1

4,4,2

4.4.3

5.0 REFERENCES

At the end of the appropriate pump cycle, as outlined bythe procedure, a measurement of d1splaced liquid 1s made.

Records as outl1ned by the dewatering procedure will bemaintained for all dewater ing projects prior to shipment.The originals are delivered to the Radwaste Eng1neer.

Carbon Steel Pressure Yessel or liners are not to beloaded with material over 1 uCI/cc of nuclides w1th half11ves greater than five years.

5.1 AP C-257 "Mobile Service Operating Procedure for Low-LevelRadioactive Waste Processing."

6.0 ATTACHMENTS

6.1 Oewatering Topical: Chem-Nuclear Systems, Inc. CNSI-DW-11118-01,Rev. Or1ginal.

NOTE: The above attachment is maintained in Document ControlMaster File, Catalog No. TK 9400/CNSI-2B.

00302901.0la 21

PACIFIC GAS AND ELECTRIC COMPANY

DEPARTMENT OF NUCLEAR POWER GENERATION


NUNER AP C-253

REVISION 9

PAGE 1 OF 6

UNITS

ADMINISTRATIVE PROCEDURE

TITLE: PROCESS CONTROL PROGRAM

AHD

APPROVED:PLAN MANAGER D E F CT VE DATE

1.0 SCOPE

1.1 The purpose of the Process Control Program (PCP) is to define thenecessary program guidance used at DCPP to ensure that SOLIDRADIOACTIVE WASTE MAHAGEMEHT activities, in packaging radioactivewaste for disposal, conform to'the Code of Federal and StateRegulations and the Waste Burial Site License Criteria.

: 1.2 , This procedure and changes thereto require PSRC review.

2 D: RESPONSIBILITIES

2.1 Plant Manager has the overall responsibility for the SolidRadioactive Waste activities at DCPP.

2.2 Manager of Chemistry and Radiation Protection is responsible forthe implementation of the requirements of this procedure.

2.3 Radwaste Engineer is responsible for the development, review andimplementation of procedures relating to the requirements of thisprocedure.

2.4 QC is responsible for verification of compliance with the Qualityrequirements.

3. E ttfl3.1 This procedure with the attachments and any changes thereto

requires review by the Plant Staff Review Committee and submissionto the US NRC in the Semi-annual Effluent Report for the period inwhich the changes were made.

00158809.01a 1II

DIABLO CAHYOH POWER PLAHT

TITLE: PROCESS COHTROL PROGSN

NQSER AP C-253RE VIS IOH 9PAGE 2 OF 6

a. NITS 1 AND 2

4. 0 INSTRUCTIONS

4.1 GENERAL

It is the policy of Pacific Gas and Electric Company toconscientiously apply emphasis and attention to those activitiesassociated with generation, processing, packaging, storage anddisposal .of radioactive ~aste generated at the Diablo Canyon PowerPlant and to maintain a high level of assurance that radioactivewaste products meet or exceed the applicable Federal and Stateregulations and the Radioactive Waste Burial Site LicenseCriteria.

4.2 WET WASTE

4.2. 1 LIQUID/WET WASTE

Liquid / Wet wastes at DCPP are processed to a conditionmeeting shipping and disposal criteria. These criteriainclude requirements for immobilization, stability andlimits on Free Standing Water (FSW). Specificinstructions on processing and required FSW limits arecontained in plant procedures and/or qualified vendorprocedures. These procedures are to be approved by thePSRC prior to implementation.

4.2.2 CONTAINERS, SHIPPING CASKS AND PACKAGING

Solid radioactive waste is processed, packaged and shippeain accordance with DCPP procedures ana/or qualified venderproceaures which have been approved by the PSRC. Theseprocedures provide specific instructions which ensure thecontainer, shipping casks and packaging methods complywith the applicable Code of Federal Regulations, StateRegulations and the Radioactive Waste Burial Site LicenseCriteria.

4.2.3 SHIPPING AND DISPOSAL

Solid radioactive waste is prepared, loaded and shipped toa Federal and/or State Licensed Radioactive Waste DisposalFacility (Burial Ground) in accordance with DCPPprocedures and/or qualified vendor procedures which havebeen approved by the PSRC. These procedures providespecifi" instructions which ensure the shipments meet theintended Burial Site License Requirements as well asapplicable Federal and State Regulations.

00158809.0la 2II


TITLE: PROCESS COHTROL PROGRAM

HU|SER AP C-253REVISION 9PAGE 3 OF 6

UNITS I AND 2

4.2.4 LABORATORY MIXING OF SAMPLES

4.2.5

gualified vendor procedures approved by the PSRC providewritten instructions on sampling, processing and handlingwaste for the determination of process parameters prior tothe actual full scale solidification.. These proc durescontain the description of the laboratory mixing methods

. used for these samples.I

SOLIDI F I CATION PROCESS

gualified vendors used by DCPP for radioactive wastesolidification are required to provide the Process ControlProgram and written procedures. These procedures andchanges thereto must be approved by the PSRC prior to use.Further, the vendors are required to have a topicalreport, as referenced, on the waste forms which will besolidified at OCPP. This topical report shoulddemonstrate compliance with the NRC requirements for wasteform. These documents should include:

a.b.C.d.e.f.

Description of the solidification processType of solidification usedProcess control parametersParameter boundary conditionsProper waste form propertiesSpecific instructions to ensure the systems areoperated within established process parameters.

4.2.6 SAMPLING PROGRAM FOR SOLIDIF ICATION

Vendors, utilized by DCPP for radioactive wastesolidi fication, are required tc include in their approvedprocedures, requirements to sample at least every tenthbatch of the same waste type to ensure solidification andto provide actions to be taken if a sample fails to verifysolidification. After a test specimen failure, initialtest specimens from three consecutive batches of thatwaste type must demonstrate solidification before testingrequirements of every tenth batch can be resumed.Verification of such sampling is to be accomplished bycompleting Form 69-10350, "Processing Control Program(PCP) Verification". These forms will be maintaine~ inthe Chemistry and Radiation Protection Department and theRecords Management System (RMS). These procedures anochanges thereto must be approved by the PSRC prior to use.j

00158809.01a 311

, I'4

DIABLO CANYON POWE% PLANT

TITLE: PROCESS CONTROL PR06RAM

NJNER AP C-253REVISION 9PA6E 4 OF 6

UNITS I ANO 2

4.2.7 WASTE FORM VERIF ICATION

4.2.8

Vendors utilized by DCPP to process wet wastes arerequired to include in their procedures provisions toverify that the solidification and/or FSW Criteria in theFederal and State regulations and the Burial Site LicenseCriteria are met for the specific type of waste beingprocessed. These procedures and changes thereto must beapproved by the PSRC prior to use.

CORRECTIVE ACTIONS FOR FREE STANDING WATER

Vendors utilized by DCPP to process wet wastes arerequired to include in their approved proceduresprovisions for correcting processed waste in which freestanding ~ater in excess of the FSW Criteria is detected.These procedures and changes thereto must be approved bythe PSRC prior to use.

4.2.9 EXOTHERMIC PROCESSES

Vendors utilized by DCPP for radioactive wastesolidification are required to include in their approvedprocedures specific process control parameters forexothermic solidification methods that must be met beforecapping the container. These procedures and changesthereto must be approved by the PSRC prior to use.

4;3

4.4

OILY WASTE

Oily wastes at DCPP are processed in accordance with approvedvendor procedures. These procedures specify the proper methods totreat oily wastes to comply with Federal and State regulations andapplicable Burial Site License Criteria. These procedures andchanges thereto must be approved by the PSRC prior to use.

SPECIAL CASES

Based upon previous industry experience, OCPP foresees thepotential for situations arising that may be beyond existing plantcapabilities. Anticipating this possibility, provisions are madeherein to accommodate such situations in a timely manner by usingspecial techniques or processes. These special cases would beccntrolled as follows:

00158809.0la 4II



HU}SER AP C-253REVISION 9PA6E 5 OF 6

UH ITS I AND 2

4.4.1 Implementing procedures would be developed comparable tothose used for normal plant solid waste activities basedon the guidance of this PCP and incorporating theapplicable provisions for process control and testing.

4.4.2 The implementing procedure would receive PSRC approvalprior to use.

4.4.3 Use of this provision and supporting information would beincluded in the next Semi-annual Effluent Report to theNRC.

4.5 REMEDIAL ACTIONS

4.5.1

4. 5.2

5.0 REFERENCES

For waste forms which do not meet Federal, State andburial site regulations and requirements, suspension ofshipment, of the inadequately processed waste andcorrection of the PCP, procedures or processing equipmentshall be performed as necessary to prevent recurrence.

For waste forms not prepared in accordance with the PCP,testing of the waste to verify shipping and burial siterequirements shall be performed and appropriateadministrative action taken to prevent recurrence.

5. 1 Title 10 Code or Federal Regulations

5.2 NUREG 0472 anu 0473

5.3 NUREG-0800, 11.4 US NRC Standard Review Plan Solid WasteManagement Systems

5.4 AP C-253S1, "Oewatering Control Program."

5.5 AP C-257, "Mobile Service Operating Procedure for Low-LevelRadioactive Waste Processing."

6.0 ATTACHMENTS

6. 1 Chem-Nuclear Systems, Inc. Procedure SQ-OP-003-482, "ProcessControl Program for CNSI Cement Solidification Units at DiabloCanyon," Rev. A.

00158809.0la 511

DIABLO CANYON POWER PUUIT


NNER AP C-253RE V IS I OH 9PA6E 6 OF 6

UH ITS I AND 2

6.2 Topical Report CNSI-2 (4313-01354-01P-A), "Chem-Nuclear Systems,Inc. Mobile Cement Solidification System", Rev. 2.

6.3

6.4

Chem-Huclear Systems, Inc. Procedure SD-OP-026, "Process ControlProgram for the Cement/Oil Solidification"., Rev. B.

Chem-Nuclear Systems, Inc. Procedure SD-OP-053, "Process ControlProgram for the CNSI Acid Solidification", Rev. B.

6.5 Chem-Nuclear Systems, Inc. Procedure SD-OP-068-482, "CalibrationCheck Procedure for the Triple Beam Balance at Diablo Canyon,"Rev. Original.

NOTE: The above attachments are maintained in Document ControlHaster File, Catalog No. TK 9400/CNSI-2A andTK 9400/CNS1-2A-1.

6.6 . Form 69-10350, "Process Control Program (PCP) Verification",11/85.

00158809. 01a 611

69-10350 11/85PACIFIC GAS AND ELECTRIC COHPANY

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2

Page 1 of 1

TITLE: PROCESS CONTROL PROGRAM PCP VERIFICATION

DATE WASTE BATCH PCP NOTESI

OPERATOR IVERIFIERINumber ype assed a ed

00158809.0la 711

ATTACHMENT 3

1947S/0054K -56-

ATTACHHENT 3

CHANGES TO THE OFFSITE DOSE CALCULATION PROCEDURE

1947S/0054K -57-

P

82~i19BB 14: 24 PGEE REGLLRTCRY ~1FWC 8855954987 12689177 P. 22

DlhSLO CNtYN Nike MNT

naa: m-Sm4OSS Ca~TlOeS

~ ~

NNON CAP heViSiOa 5l%0E l2 Of b5

lN1TS 1 NO 2

d. OOie PrO)lct10n (ToS ~ i ll lo3oi and ToSo 1 iloi 3 ~ 3)

Dose pro)act1ons for the categor1es of calculated total body exposure~nd organ exposure are recorded at least once per 31 days. The periodover ~ 1ch propct1ons are sade 1s 31 days. The calculat1ons are alsomde pr1or to each release to sat1sfy T.S. 4.ll.i.3.3The purpose of th1s 1s to deterelna 1f appropr1ate treatNent of 11qu1drad1oact1ve eater1als 1n relat1on to ae1nta1nlng releases "as low asreasonably ach1evabla', 1s necessary.

pro)ect1ons w1ll 1n any case be recorded on the last vork1ng day ofeach oenth fifth attent1on to the Techn1cal Spec1f1cat1on frequencyrequ1~nt contained 1n Sect1on 4.11.1.3.1. ~

'

The orojecsad dose ls calcul aced by aool1caslon or eovas1on (R) below%The follat1ng gu1danca of default flowratas 1s prov1ded, whereappr opr1ate stan us1ng equat1on (I).l) lhx1aa Rated Flmeates {for default use)

a) Chm1cal Drain Tanks (26 gpe).

b) Laundry Masta TankS (l3 gpa).

c) Floor Craln Reca1ver Tahks (35 gpss).pgggg ~ uvsihlC 4Cts VC' h

d) (60 gpI)).

e) Equ1PNent Cra1n Reca1var Tanks (I 9PI)) e

f) Steam Generator Nowdom, both-un1 ts R (150 gpss). Jg ds)idd

o) tyewc Radanarans Resolver Tonho (70 Roa).

h) 01ly Mite'eparator (Turb1na Su1ld1ng Suap) (100 gpss).0

1) Condensate DaI1n. Reian. Sys, Maste Transfer 01scharge L1ht,Un1t l, (Nax 240 gpe).

3) Condensate Qee1n. Regen. Sys. Maste Tr ansfer 01schirge L1ne,Un1t 2, (Hax 2'pe).

x006923a.OS l2t

ATTACHMENT 4

1947S/0054K -58-

ATTACHHENT 4

1987 LAND USE CENSUS

1947S/0054K -59-

0

PGwEPOA INTRA COMPANY Ue'ES

~ Regin or~~™" ENGINEERING RESEARCHNU OPER SUPPORT

420DC (6100/51-6200/52)RE. LETTER OF

suLIECT DCPP Land Use Census

October 15, 1987

DAVID H. OATLEY:

Here is the 1987 Land Use Census for Diablo Canyon Power Plant. There wereao changes Srom the 1986 Land Use Census.

PAUL A. SZALINSKI

PAS(551-5332):cap2680a/capA9

cc: NLKnox (Nuclear Indexer)AOng/CSChengJDTownsend/JVBoots/AOTaylorTCWilson/RMRichardson

Attachment

"THINK SAFETY"

DIABLO CANYON LAND USE CENSUS

Engineering Research conducted a land use census in the vicinity ofDiablo Canyon Power Plant. This census vas for 1987. The land use censusis required by Nuclear Regulatory Commission, Regulatory Guide 4.8"Environmental Technical Specifications for Nuclear Power Plants" and by theDiablo Canyon Power Plant Technical Specification 3.12.2. These bothrequire that a census be conducted at least once per year during the grovingseason (between June 1 and October 1 for the Diablo Canyon environs). Thecensus is to identify the nearest residence, the nearest milk animal and thenearest garden greater than 50 square meters (500 sq. ft.) producing broadleaf vegetation in each of the 16 meteorological sectors vithin a distanceof five miles.

The methods for conducting the census vere: direct contact withindividual land owners or tenants and property visits. The land ovners vereidentified from County records. The land owners and Tenants vere contactedpersonally or by phone between June 30 and September 30, 1987.

Contact with the land ovners or tenants and the property visitsidentified no household gardens greater than 500 square feet. No milkanimals were identified on these properties. Much of the area surroundingMe plant site is used for cattle grazing and there is a farm in theeastsoutheast sector (along the site access road) producing legumes andcereal grass (grains).

Results

The attached table and map summarize the land use census results. No

milk animals vere identified within the first five miles in any sector. Theonly garden or farm greater than 500 square feet is in the eastsoutheastsector. The farm is on the coastal plateau; it starts at approximately twomiles from the plant and extends to 4.5 miles from the plant. The nearestresidence is 1.55 miles north northwest of the plant. A total of eightpermanent residences vere identified within five miles of the plant.

2680a/capA9

TABLE 1

LAND USE CENSUS - DISTANCES IN MILES PROM THE UNIT 1 CENTER LINETO THE NEAREST MILK ANIMAL RESIDENCE VEGETABLE GARDEN

22-1/2 Degree(1)Radial Sector

N

SE

NearestMilk Animal

None

None

None

None

None

None

None

None

None

NearestResidence

hn mi

5;95 (3.7)

2.50 (1.55)

None

5.30 (3.3)

8.15 (5.06)

7.15 (4.44)

7.25 (4.5)

None

None

ResidenceAzimuth

~de ree

326

333

018.5

037

062.5

096.5

NearestVegetable

Garden

None

None

None

None

None

None

None

None

(1) Sectors not shown contain no land beyond the site boundary, other thanislets not used for the purposes indicated in this table.

2680a/capA9

4m gpKztAET

TO ALSO RCOaKt

kTASCAOEOO

V le SLY

5ixTA0 mawworm

~ I

JACKSCCfAN

ORLA O~

lJNlTS I iND tONSLC CANYON $1TE

fNVttK Q LANDMSK CKNSVS

9 aevi m tswRKStDKNCES

0 i t 5 a 0OCALK N NLLS

1

0

I

II

Documents

Diablo Canyon Power Plant Semiannual Radioactive Effluent ... · Diablo Canyon Units 1 and 2 Semiannual Radioactive Effluent Release Report Gentlemen: Enclosed is the Diablo Canyon