· REGUL'A»TORY INFORMA»TION» D»ISTR»I BUT»IO SYSTEM» (RIDS) DOCKE»T< 0 05%RZ2~ 05090529 05090530 ACCESSIO»VI NBR ~ 8110300289 DOC ~ DA»TE1:'1/10'/28 NOTARIZED!: NO FACIlr:

REGUL'A»TORY INFORMA»TION» D»ISTR»I BUT»IO SYSTEM» (RIDS)

DOCKE»T< 005%RZ2~0509052905090530

ACCESSIO»VI NBR ~ 8110300289 DOC ~ DA»TE1:'1/10'/28 NOTARIZED!: NO

FACIlr:STN 50 528 Pa»1 or Ve'rdei Nucl ear» Statiloni, Uhit» 1P Ar»izone Publ iSTN 50 529 Palo; Ve'rdeI Nucle'eri StationP Unit" 2'P Arizona PubliSTN"50', 530 Palo Vei der iVucl ebr< Statlioni Und t" 3P Ar lizone Publ i

AUTH!,NAMEI AUTHORr AFFIL»I'ATIION-VAN'RUV!T'EEI,E!~ Arizonei Publ i c; S'ervi c,et C'o,

RECIP' VAMEI RKCIIPZENTI AFFIL»IA!T'ION»TEDESCO»P R "B L!B" AssistantB Dir e'ctor» for» I.rlcehsing

SUB'JECIl"t: Forwards dr af t» FSAR" cl er»if i cathons'er fecil i ty sampling,par amet'ers" (T'ah»le 9.3 3) Pse'condary sys drain» sampling,(Se'ctioni 9;3~,2 2D3') EreVise'd» Pages 1 1.2!-20. through, 2?l 1 Page's»11,4 1 iI ff.4 2'.Ihfo will bel included» in FSAR'mehd."

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Ãult&IICIKSIEPllt5lltl CKSKMEFP.o. BOX 21666 PHOENIX, ARIZONA85036

October 28, 1981ANPP-19292 — JMA/WFQ

Mr. R. L. TedescoAssistant Director for LicensingDivision of LicensingOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashington, D.C. 20555

~~)

p

g4( (')

Subject: Palo Verde Nuclear Generating Station(PVNGS) Units 1, 2 and 3Docket Nos. STN-50-528/529/530File: 81-056-026; G.1.10

Dear Mr. Tedesco:

Attached please find draft FSAR clarifications regarding PVNGS samplingparameters (Table 9.3-3), secondary systems drain sampling (Section9.3.2.2.3), revised pages 11.2-20 thru 22 and pages 11.4-1, 11.4-2.

This information is provided in response to telephone requests forclarification from the NRC's Effluent Treatment Systems Branch and willbe included in a future FSAR amendment.

Very truly yours,

EEVBJr/WFQ/avAttachment

cc: J. Kerrigan (w/a)P. Hourihan (w/a)A. C. Gehr (w/a)T. Chandrasekaran (w/a)

E. E. Van Brun Jr.APS Vice Presi ent,

Nuclear ProjectsANPP Project Director

p~c 1

(/i

8||0300289 8110&8 ~

PDR ADDCK 05000528 I

q A PDRy

~ ~

STATE OF ARIZONA )) ss.

COUNTY OF MARICOPA)

lf

I, John M. Allen, represent that I am Nuclear Engineering Manager ofArizona Public Service Company, that the foregoing document has been signedby me for Edwin E. Van Brunt, Jr., Vice President Nuclear Projects, onbehalf of Arizona Public Service Company with full authority so to do, thatI have read such document and know its contents, and that to the best of myknowledge and belief, the statements made therein are true.

hn M. Alle

Sworn to before me thisg9 day of 1981.

Notary Public

My Commission expires:

V~ ~

f"~ ~

J

'fj

Table 9.3-3SAMPZING SYSTEM DESIGN PARAMETERS (Sheet 2 of 13)

/

Sample OriginType ofSamplecooler

TypicalDiscrete Sample

Analysis(b)

PressurizedSample

Capability

'ontinuousOn LineAnalysisProvided

Mode of SampleRemoval and

Location

Nominal

Pressure(psig)

Tempera-ture ('F) Figure No. )7

Primar Sam linS stem Cont'd

'Pressurizer SurgeLine

Reactor Drain PumpDischarge BeforeFilter

Reactor Drain PumpDischarge AfterFilter

Rough

None

None

Boron

ConductivitypH, Cl Boron

ConductivitypI), Cl Boron

No

No

No

None

None

None

RemoteAux BldgE1-140'ocal

Aux BldgEl-120'ocal

'Aux Bldg

El-120'500

.

65

65

700

120

120

5. 1-19.3-2

9.3-13

9.3-13

Q C)

4) 4)Q II

00 ~

Pre-holdup IonExchanger Outlet

None

Holdup Tank Inlet None

Boric Acid Conden- Nonesate,Ion ExchangerInlet

ConductivitypH

.Conductivity .

pH, Boron, Cl

ConductivitypH, Boron

No

No

No

None

None

None

Local~ Aux BldgEl

120'ocal

Aux BldgEl-120'

k

LocalAux BldgEl-120'5

60

60

120

130

140

9.3-13

9.3»13

9.3-13

Boric Acid Conden-sate Ion ExchangerOutlet

None ConductivitypH, Boron

No None LocalAux BldgEl-120'0

140 9.3-13

Reactor Makeup Water NonePump Discharge

Reactor Makeup Water NonePump Recirculation.

ConductivitypH, Boron, Cl


No

No

None

None

LocalAux BldgEl-120'ocal

Aux BldgEl-120'30130

120

120

9.3-13

9.3-13

Boric Acid MakeupPump Recircula-tion

None Boron No None t,ocalAux BldgEl-120'30 120 9.3-13 M

M

SHAFT~ ~

Table 9.3-3SAMPLING. SYSTEM DESIGN PARAMETERS (Sheet 1 of 13)

C

Sample Origin

Type ofSampleCooler


Analysis(b)

PressurizedSample

Capability

ContinuousOn LineAnalysisProvided

Node of SampleRemoval and

Location

Nominal

Pressure(psig)

Tempera-ture ('F) Figure No.

IoeI

o (.

Primar Sam lin~sstem

Hot Leg Loop 1

Pressuriier SteamSpace

Shutdown CoolingSuction Lines 1& 2

ESF A&B Train SafetyInjection PumpMini Flow Line

Purification FilterInlet

Purification FilterOutlet, IonExchanger Inlet

Purification IonExchanger Outlet

Rough

Rough

Rough

Rough

None

None

None

pH ~ 02'2'otalDissolved

Gas, NH3,Lithium, Boron,Cl , F , Radio-activity

82

Boron, Radio-activity


pH, NH3,Lithium, Boron,Cl , F , Radio-activitySuspendedSolids

pH, Lithium,Boron Cl , F ,Radioactivity

Yes

Yes

No

No

No

No

No

None

None

None

None

None

Radio-activ-ity«)

None

RemoteAux Bldg

El-140'emote

Aux BldgE1-140

'emote

Aux BldgEl-140'emote

Aux Bldg

El-140'emote

Aux BldgEl

140'emote

Aux BldgEl-140 s

RemoteAux Bldg

E1-140'485

2500

435

2050

60

50

50

621

700

350

350

120

120

120

5.1-19.3-2

5.1-19.3-2

6.3-19.3-2

6.3-19.3-2/, ~

9.3-139.3 2

9.3-139.3-2

9.3-139.3 2

Q

M

a. Pressure value in PSIA.b. Radioactivity samples can be analyzed for gross activity, isotopic composition, tritium or alpha activity.c. Refer to section 11.5 for detailed descriptions of process and effluent radiation monitors.d. Refer to section 11.3 for a description of the explosive mixtures monitoring.


r

Sample OriginType ofSampleCooler


Analysis(b)

PressurizedSample

Capability



Location

Nominal

Pressure(psig)

Tempera-ture (4F) Figure No.

Ol ~

W 4lO I(m CO

Primar Sam linS stem Cont'd

Boric Acid MakeupPump Discharge

Boric Acid BatchingTank

Reactor Makeup Waterto Volume ControlTank

Volume Control TankDrain to RecycleDrain Header

CVCS Letdown

Shutdown CoolingHeat ExchangerOutlet

Safety injectionTanks 1,2,3,4

Secondar Sam lePo ill'ts

Hotwell 1A, 2A, 18,2B, lC, and 2C

None

Portable

None

None

None

Portable

None

Fine

Boron

Boron

conductivitypH, Boron Cl


Boron


Conductivity,pH, Boron

YesCationConductivitySodium

No

No

No

No

No

No

No

No

None

None

None

None

YesBoron

None

None

YesCationConduc-tivitysodium

Local Aux BldgE1-120'ocal

Aux BldgEl

120'ocal

Aux Bldg

E1-120'ocal

Aux Bldg

El-120'emote

Aux BldgEl-120'ocal

Aux BldgE1-120'ocal

Containment

El-80'emote

HotwellAnalysis Sta-tion TurbineBldg El

100'30

130

50

50

650

610

2(a)

120

160

120

120

120

160

120

121

9.3-13

9.3-13

9.3-13

9.3-13

9.3-13

6.3-1

6.3-1

10.4-99.3-3

MLM

a(0n(090'-(0

Table 9.3-3SAMPLING SYSTEM DESIGN PARAMETERS (Sheet 4 of 13)

Sample Origin

Secondar Sam lePoints cont'

Type ofSampleCooler


Analysis(b)

PressurizedSample

Capability



Location

Nominal

Pressure(psig)


S/G 1 and 2 HotlegBlowdown

S/G 1 and 2 ColdlegBlowdown

Rough &Fine .

Rough 6Fine

YesConductivitypH & Radio-activity

YesConductivitypH & Radio-activity

No Yes, Con-ductivitypH, Radio-activ-ity(c)Yes, Con-ductivitypH, Radio-activ-i,ty (c)

'emoteCold

Lab Aux Bldg

E1-140'emote

ColdIab Aux BldgEl-140'1791179

554

450

10.3-19.3-3

10.3-19.3-3

S/G 1 and 2Downcomer Blow-down

Condensate LP HeaterTrain A, B, and COutlet

FW Pump A and BSuction

HP Heater TrainA and B Outlet

Rough 6Fine

YesConductivitypH 6 Radio-activity

Portable YesConductivity



No

No

No

No

Yes, Con-ductivitypH &Radio-activ-ity(c)

\None

None

None

RemoteCold LabAux Bldg

E1-140'ocal

TurbineBldg,

El-140'ocal

TurbineBldg

El-140'ocal

TurbineBldg

E1-140'179

400

400

1225

554

396

396

450

10.3 19.3-3:

10.4-9

10.4-10

10.4-10

MSR A, B, C and DDrain

Portable YesConductivityIron, Copper

No None Local TurbineBldg El 140'02(') 383 10.2 2

First Stage RHTRDrain Tank A, B,C and D


No None Local TurbineBldg El-140'32(') 452 10.2 2

Second Stage RHTRDrain Tank A, B,C and D


No None Local TurbineBldg E1-140'85( ) 543 10.2 2

0


Sample Origin

Type ofsamplecooler


Analysis(>>

PressurizedSample

Capability


NominalNode of Sample

Removal and PressureLocation (psrg)


IOe~ lAO)co O

Seconda Sam lePornts

Cont'tr

Drain Tank Aand B Drain

Htr Drain Pump Aand B Discharge

Spray Pond Water

Circulating WaterOutlets

Condensate TankSample

Portable

Portable

None

Fine

None

ConductivityIron, Copper

ConductivityIron, Copper

Hardness~ Alkalinity

pH, TDSConductivity

ConductivitypH, Chlorine

ConductivitypH, ChloridesFluorides,DissolvedSolids.Silica

No

No

No

No

No

None

None

YesConduc-tivity

YesConduc-tivity pHChlorine

None

Local TurbBldg El

100'ocal

Turb BldgEl

100'emote

YarYa Area

Remote ColdLab Aux Bldg140'is

Sta Tur-bine Bldg

100'ocal

Yard Area

433( )

202«)

15(a)

30

371

383

97

108

Ambient

10.2-2

10.2-2

9.2-1

10.4-49.3-3

9.2-8

U(8n(0

Essential chillerA and B Outlets

Essential coolingWater Pumps Aand B Discharge

None

None

Normal Chillers NoneA, B, and C OutletHeaders

pH,Chromate

pH,Chromate

pH,Chromate

No

No

No

None

Radio-activ-ity(c)None

Local ControlBldg El 74'5

Local Aux Bldg 45RoofEl 15'»

Local Aux Bldg 105El 70'9 9.2-11

9.2 4

9.2 10

M

M

0


4

Sample Origin

Secondar Sam lePornts Cont'd

Type ofSampleCooler


Analysis (b)

PressurizedSample

Capability


NominalMode of Sample

Removal and PressureLocation (psig)

Tempera-ture ('F) Figure No. f7

Nuclear CoolingHater PumpDischarge Header

None pH,Chromate

No Radio-actjv-ity(c)

Local Aux BldgEl-88'0 105 9.2-5

shutdown CoolingHeat ExchangerRoom A and BDrain

None pH Ho Hone Local Radwaste Atmos.Bldg El-88'20 9 '-7

LRS Hold-Up TankLeak Drain

None Radio-activity

No None Local LRSHold-up TankArea

El-100'tmos.120 9.3-7

LRS Recycle MonitorTank Leak Drain

None Radio-activity

No None Local LRSHold-up TankArea

El-100'tmos.120 9.3-7

Main Turbine LubeOil CentrifugeOutlet

None SuspendedSolids

No None Local TurbineBldg El-100'5 120

FWPT Lube OilCentrifuge Outlet

Cooling H20 Hold-upTank

None

Hone

SuspendedSolids

RadioactivitypH, Chromate

No

Hone

None

Local TurbineBldg

El-100'ocal

Aux BldgEl-40'0 75

52 120

9.3-10f7

I

C)I

Chemical wasteNeutralizer Tank(1 Sample Pointat Each Tank)

None

Condensate Polishing NoneDemineralizer(LO-TDS) Sump(2 Sample Points)

RadioactivitypH, Chromate

Radioactivity

No None

None

Local YardArea

E1-100'V088-V195)

Local YardArea

El-100'V028,

V031)

10

60

75

100

9.3-10

9.3-10

0O

Ul

M

0

l


Sample Origin

Secondar Sam lePornts Cont'd

Type ofSampleCooler


Analysis(b)

PressurizedSample

capability



Location

Nominal

Pressure(psig)


Condensate Polishing NoneDemineralizer(HI-TDS) Sump(2 Sample Points)

Radioactivity No None Local YardArea

El-100'V034,

V037)

60 100 9.3-10

O Qe

lV LOO II M

co MI

Retention Basin(Holdup Prior toEvaporation Pond)(2 Sample Points)

Spent RegenerationSump (WaterReclamationFacility)

TCW Heat ExchangerA and B Outlet

ESF Sump Pump Aand B Discharge

Non-ESF SumpDischarge

Blowdown Demineral-izer Effluent (1)

Blowdown Demineral-izer Effluent (2)

Blowdown Demineral-izer StrainerInfluent (1)

Blowdown Demineral-izer StrainerInfluent (2)

None

None

None

None

None

Rough

Rough

None

Hone

pH, ConductivitRadioactivity

pH

Chlorine

Chlorine

Chlorine

Na, Si, pH,ConductivityRadioactivity,

Na. Si, pHConductivityRadioactivity

Conductivity

conductivity

No

No

No

No

No

Yes

Yes

Yes

Yes

None

YespH

YesChlorine

None

None

Yes, Na,pH.Si,Con-ductivityYes, Na,Si,pH,Con-ductivityYesconduc-tivityYesConduc-tivity

South ofUnit 3

El-100'V089, V090)

water RecFacility

Remote YardArea

Local Aux Bldg

E1-40'ocal

Aux Bldg

El-40'emote

YardArea

Remote YardArea

Remote YardArea

Remote YardArea

Atmos

40

25

50

15

225

225

225

225

116

75

110

120

120

135

135

135

135

9.3-11

9.3-10

9.2-9

9.3-5

9.3-5

10.4-8

10.4-8

10.4 8

10.4 8

an(080

Table 9.3-3SAMPZING SYSTEM DESIGN PARAMETERS (Sheet. 8 of 13)

Sample Origin

Type ofSampleCooler


Analysis (bI

Pressurizedsample

Capability



Location

Nominal

Pressure(psig)


Secondar Sam lin

rI

Ico LoI

Blowdown Demineral-izer Waste (HighTDS)

Blowdown Demineral-izer Waste (IowTDS)

Blowdown Demineral-izer Caustic DayTank Effluent

Blowdown Demineral-izer Acid Day TankEffluent

Diesel Fuel OilStorage Tank Aand B

Condenser Sump(North and South)Pump Discharges

Turbine BuildingSump

TCW Pump A and BDischarge

Auxiliary SteamCondensateReceiver Tank

Auxiliary Steam

None

None

None

None

None

Hone

None

None

Portable

Rough

ConductivityRadioactivity

ConductivityRadioactivity

Conductivity

Conductivity

Apjo,Viscosity,HVV, Sediment

pH,suspended

'olids,Radio-activitypH, SuspendedSolids, Radio-activitypH Chloride,ions

pH,Conductivity

pH,Conductivity

Yes

Yes

Yes

Yes

No

No

No

No

No

No

Yes .Conduc-tivityYesConduc-tivityYesConduc-tivityYesConduc-tivityNone

None

None

None

Radio-activ-ityIc)

None

Remote YardArea(V182, V204)

Remote YardArea(V172, V169)

Remote YardArea

RemoteYard Area

Local Outsideby D.G. BldgEl-100'ocal

TurbBldg

El-100'V075, V078)

Local TurbBldg

El-100'V076)

Local TurbBldg

E1-105'ocal

Turb.Bldg

El-100'ocal

YardArea

225

225

50

50

35

20

20

90

15

250

135

135

85

85

75

75

75

110

212

405

10.4-5

10.4-5

10.4-8

10.4-8

9> 5-7

9.3-11

- 9.3-11

9.2-9

13-M-ASP-001

AO-M-ASP-002

Table 9.3-3SAMPLING SYSTEM DESIGN PARAMETERS (Sheet: 9 of 13)



Analysis(b)

PressurizedSample

Capability



Location

Nominal

Pressure(psig)


l7

IQSbJ 4)Q II

C0 +

Seconder Sam linPoints Cont d

Circulating WaterCooling Towers

Demineralized WaterSurge-Rinse Tank

Demineralized WaterStorage Tank

Fuel Pool Clean-upPump (1 & 2)Discharge (SpentFuel Pool orRefueling Pool)

Fuel Pool CleanupFilter 1 and 2Outlet (SpentFuel Pool orRefueling Pool)

Fuel Pool CleanupDemineralizer 12 Outlet (SpentFuel Pool orRefueling Pool)

Radwaste Sam linPoints

Evaporator Feed fromLRS Holdup Pumps

Chemical Drain PumpDischarge

None

None

None

None

None

None

None

None

Water Chemistry

Water Chemistry

pH, Chloride,ions, Fluorideions, Boric AcidHydrazine,Ammonia, Lithium

~ RadioactivityIConductivity,pH, Chlorideions, SuspendedSolids, Sodium,Radioactivity

Conductivity,pH, Chlorideions, SuspendedSolids, Sodium,Radioactivity

pH

pH,Conductivity

No

No

No

No

No

No

Yes

YesFoam

None

None

None

None

None

None

None

Local CoolingTower Area

Wtr TreatmentArea

Local YardArea

Local FuelBldg

El-100'ocal

Aux BldgEl-120s

Local Aux Bldg

E1-120'ocal

RadwasteBldg

El-100'ocal

RadwasteBldg

El-40'tmos.

20

288" H20

90

50

50

107 psia

88 psia

108

Ambient

Ambient

125

125

125

60 to120

60 to120

10.4 4

9.2-6

"9.2-6

9.1-9

~9'1-9t

9. 1-9

11.2-2

11.2-2

)6

M

WM

IC

Table 9.3-3SAMPLING SYSTEM DESIGN PARAMETERS (Sheet: 10 of 13)

Sample Origin

Radwaste Sam linPornts Cont'd

Type ofSampleCooler


Analysis (b)

PressurizedSample

Capability

ContinuousOn tine 'Mode of SampleAnalysis Removal andProvided Location

Nominal

Pressure(psig)


Hi-Lo TDS HoldupPump Recycle

None pH, Conduc-tivity BoricAcidConcentration

Yes None Local RadwasteBldg El 100'i-TDS

55 psiaLO-TDS42 psia

eo-120

11.2 2

Evaporator Concen-trate PumpsRecycle to VaporBody

Portable Boric Acid Con-centration, pH,,, Wtg "Solids

Yes None Local RadwasteBldg El-120'24 11.2-2

Ioem LOO II

CO Ol

Cas Sam lin S stem

Gas Surge Tank

Gas Decay Tank

None

Hone

Radioactivity,H2, 02


No

Yes

H2,02 (d)

H2,02 (d)

Remote Rad-waste Bldg

El-140'emote

Rad-waste BldgEl-140'80380

200

200

11.3»29.3-2

1'1'.3-29.3-2

Cas Stripper None Radioactivity,H2, 02

Yes H2,02 (d) Remote Rad-waste BldgEl-140'00 120 11.3 2

9.3-2

Volume Control Tank

Equipment Drain Tank

Reactor Drain Tank

None.

None

None

Radioactivity,ity, H2'2



No

No

No

H2,02 (d)

H 0 (d)2'

H2,02 (d)


El-140'emote

Rad-waste Bldg

El-140'emote

Rad-waste BldgE1-140'0

120

120

120

9.3-139.3-2

9.3-139.3-2

11.3-29.3-2


Sample Origin

Holdup Tank

Type ofSampleCooler

None


Analysis(b)


PressurizedSample

Capability

No

ContinuousOn I.ineAnalysisProvided

H2,02 (d)


Location


El-140'ominalPressure

(psig)Tempera-ture ('F)

Atmos. 120

Figure No.

9.3-139.3-2 (7

ContainmentAtmosphere

Containment PurgeExhaust

None

None

Radioactivity

Radioactivity

No

No

Radio-activ-ity(c)

Radio-actjv-ity(c)

Local AuxBldg

100'evel

NE Quad

Iocal Aux.Bldg

140'evel

NE Quad

Atmos.

122

120

9. 4-13

9.4-13

oe) ~

o )M

co Ql

Plant Vent

ContainmentAtmosphere

Control BuildingOutside AirIntake

Post-AccidentSam Inn S stem

None

None

None

Radioactivity

Moisture(4 points)

RadioactivitySmoke, C12,2 points each

No

No

No

Radio-activ-ity(c)

YesMoisture(4 points)

Radio-activ-ity (c)Smoke, C12,2 pointseach

Local TurbBldg160'evel

Local 1 at'El-104'-6" NW

Quad; 1 atEl 124>-9NW Quad;2 laterRemote Con-trol Bldg,140'evel inOutside AirChase

Atmos. 120

122

Atmos. 113

9.4-13

9.4-12

9.4-1

Hot Leg Loop 1 Rough Isotopic, GrossGamma, pH, Oxy-gen, Hydrogen,Chloride, Boron

Yes Isotopic,GrossGamma, pH,Oxygen,Hydrogen,Chloride,Boron

Remote AuxBldg, Eleva-tions 140'nd70'yringeGrab Sample

2485 621 9.3-2A

MtM




Analysis (b)

PressurizedSample

Capability

ContinuousOn t.ineAnalysisProvided


Location

Nominal

Pressure(psig)


7

Post-AccidentSam lan S stem~CoC '

Hot I.eg Loop 2 Rough Isotopic. GrossGamma, pH, Oxy-gen, Hydrogen,Chloride, Boron

Yes Isotopic,GrossGamma, pH,Oxygen,Hydrogen,Chloride,Boron

Remote AuxBldg, Eleva-txons 140'nd70'yringeGrab Sample

2485 621 9.3-2A

ESF A&B SafetyInjection Sumps

ESF A&B SafetyInjection HiniFlow Line

ContainmentRadwaste.Sumps

Rough

Rough

Rough

Isotopic, GrossGamma, pH, Oxy-gen, Hydrogen,Chloride, Boron

Isotopic, GrossGamma, pH, Oxy-gen, Hydrogen.Chloride, Boron

Isotopic, GrossGamma, pH,- Oxy-gen, Hydrogen,Chloride, Boron

Yes

Yes

Yes

Isotopic,GrossGamma, pHOxygen,Hydrogen,Chloride,Boron

Isotopic,GrossGamma, pH,Oxygen,Hydrogen,Chloride,Boron

Isotopic,GrossGamma, pH,Oxygen,Hydrogen,Chloride,Boron

Remote AuxBldg, Eleva-tions 140'nd70'yringeGrab Sample—



60

2050

60

350

350

120

9.3-2A

r.~9.3 2A

9.3-2A

0AMN

CM

M

MW

Table 9.3-3SAMPE ING SYSTEM DESIGN PARAMETERS (Sheet 13.of 13)

Sample Origin

Post-Accident~sx s st.cont

Type ofSampleCooler


"Analysis(>>

PressurizedSample

capability



Location

Nominal

Pressure(psig)


O ~

bD

I

Auxiliary BuildingSumps

Containment Air

Rough

Rough

Isotopic, GrossGamma, pH, Oxy-gen, Hydrogen,Chloride, Boron

Isotopic, GrossGamma, Oxygen(Hydrogenprovided byContainmentHydrogen ControlSystem)

Yes

Yes

Isotopic,GrossGamma, pH,Oxygen,Hydrogen.Chloride,Boron

Isotopic,GrossGamma,Oxygen(Hydrogenprovidedby Con-tainmentHydrogencontrolSystem)



50

60

120

350

9.3-2A

9.3 2A

0nW

PVNGS FSAR

9.3.2.2.2 Post-AccidentPROCESS AUXILIARIES

Liquid samples are taken from both RCS hot legs, containmentsumps, auxiliary building sumps and the ESF A6B mini-flow line.All samples are routed to a liquid;input header. After sampleselection, isotopic analysis is performed. The sample is thendepressurized and cooled to allow chemical analyses to beperformed. At this point a syringe grab sample can be taken;or the sample can be discharged to the RDT or EDT. Uponcompletion of the analysis, the source is isolated, and thesystem is then purged with demineralized water, then nitrogengas.

Gas samples are taken from containment air via the containmenthydrogen control system. Samples are routed to a gas inputheader. Isotopic analysis is performed then the sample isdepressurized and cooled to STP conditions in order to perform02 analysis. A syringe grab sample can be taken or the sampleis returned to the containment. The. normal hot lab countingroom at the 140-foot elevation in the auxiliary building isshielded to provide low background post accident. The countingchamber can be purged with instrument air or bottled gas. When

the analysis is complete, the source is isolated, and the systemis purged with nitrogen gas.

Liquid samples will provide information on isotopic content,gross gamma, pH, chloride concentration, dissolved oxygen,dissolved hydrogen and boron. Gas samples will provideinformation on isotopic content, gross gamma, gaseous

oxygen,'nd

hydrogen (from hydrogen monitor of the containment hydrogencontrol system).

9.3.2.2.3 Secondary Systems Drain Sampling

There are eight sumps in or near Turbine Building Structureswith potential for transferring radioactivity to flow pathsleading to the retention basins/evaporation ponds. There are

Amendment 7 9. 3-31A10-20-81

December 1981

1

PVNGS FSAR

PROCESS AUXILIARIES

three drainage sumps in the turbine building: the north sump,the south sump, and the turbine, building sump. Each sump hasan analysis point on its discharge piping and can transferfluids to the liquid radwaste system (LRS), either of twochemical waste neutralizing tanks (CWNT), or to an oil/waterseparator. Each CWNT has separate analysis points,and can besampled prior to discharge. Each CWNT can discharge- to theLRS or the retention basins. The oil/water separator dis-charges to its sump (sump four), which in turn discharges to.the retention basins.

There is not a very great potential of introducing significantradioactivity to these sumps, and it, is not likely that thesumps would be aligned to „discharge radioactivity to theretention basins. The following are the sources to thesesumps:

North Sum

Battery room neutralizing pit (nonradioactive)Floor drains (equipment leakage and cleaning liquids)Feedwater heaters

Heater drain tank and pump

Instrument air compressor drains (nonradioactive)Air dryer/prefilter drains (nonradioactive)Blowdown flash tank liquid drainTurbine cooling water heat exchanger drain(nonradioactive)

Turbine cooling water surge tank drain(nonradioactive)

Heater blowdown stack

Condensate storage tank

December 1981 9.3-31B10-20-81

Amendment 7 4

PVNGS FSAR

PROCESS AUXILIARIES

Condenser drains

Generator stator cooler drain (nonradioactive)

'V

Floor drains (equipment leakage and cleaning liquids)Low pressure heaters and condenser drainsCondenser evacuation drainSteam seal exhauster drainIsophase bus cooler drain (nonradioactive)

H2 seal oil cooler (nonradioactive)Condensate pump drainage

Turbine Buildin Sum

Feedwater pump lube oil reservoir drains(nonradioactive)

Feedwater pump drainTurbine lube oil drains (nonradioactive)

Oil ater Se arator Sum

North, South, and turbine building sumps.

Control bu"'lding sumps (nonradioactive)The only sources noted above that could contain any radioactiv-ity are secondary system component sources — condensate orblowdown. No regenerant chemicals are present. Thus, anyradioactivity which is present must be at least as dilute asthe secondary system.

The activity level in the secondary is monitored at two points.Steam generator blowdown monitors 13-J-SQN-RU-4 and RU-5 willdetect abnormal activity in the secondary as it is diverted tothe blowdown processing equipment. The condenser gland sealexhauster monitors 13-J-SQN-RU-141 and RU-142 (low and highrange) will detect abnormal activity in the condenser.

7l .Amendment 7 9.3-31C,10-20-81

December 1981

PVNGS FSAR

PROCESS AUXILIARIES

If abnormal activity levels are present, sump transfer pathswill be aligned to transfer to.the LRS or the CWNT's with sub-sequent alignment to the LRS. However, if it is determinedduring operating (by sampling or monitoring) that the sumps do

'

not contain significant radioactivity, they may be realignedto discharge to the CWNT's (aligned to the retention basins)or the oil water separator and thence to the retention basins.

The remaining four sumps are the high and low total dissolvedsolids (TDS sumps that receive regenerant wastes from the con-densate polishing demineralizers or the blowdown demineralizers,respectively each sump has local drains that will be used forgrab sampling. For either processing stream, initial regener-ant eluent is fed to the resin and subsequently directed tothe high TDS sumps. These discharge to the CWNT's. As notedpreviously, the CWNT's,can discharge to the LRS or retentionbasins and are sampled prior to discharge. Only after the TDS

level of the regenerant has drops (associated with activitylevels), as measured by on-line conductivity cells, would flowbe directed to the low TDS sumps, or the circulating watersystem (and thence to the evaporation ponds via blowdown).Thus, the systems are designed to send radioactive waste tothe LRS and yet recover clean liquid for recycle to thegreatest extent practical.To ensure that abnormal levels of activity are not sent toclean systems, design provisions for sampling are beingclarified. FSAR Table 9.3-3 is being revised to show thesampling capabilities at these sumps. Operationally, when

significant activity is present in the secondary (as detectedby the steam generator blowdown or condenser gland sealexhaust monitors) the low TDS sumps will be aligned to dis-charge to the high TDS sumps. A grab sample analysis forradioactivity will be required prior to changing this alignment,to allow discharge to the circulating water.

December 1981 9.3-31D10-20-81

Amendment 7 7

PVNGS FSAR

PROCESS AUXILIARIES

In summary, the secondary systems are continuously monitoredfor activity. If abnormal activity is present, this will leadto alignment of leakage and cleanup stream discharge to theLRS. If after grab sampling, no abnormal activity is presentin,effluents they can be directed to the circulating wateror retention basins.

9.3.2.2.4 Retention Basin Sampling

The divided retention basin is located south of the Unit 3

spray ponds. It has a one million gallon capacity and isdivided into identical compartments. The compartments havesloping sides and are approximately 172' 98't top and121' 47't. bottom. Nominal depth is 6-1/2 feet with2 feet freeboard; The top of the dikes are 4-1/2 feet abovegrade to provide flood protection.The basins act as storage in the event the effluent is notwithin the standards for pH, conductivity, and radioactivityprior to discharge to the evaporation pond. One retentionbasin can store the normal waste effluent of 800 gal/min fora 10-hour period. The offline basin is monitored, chemicallytreated (if necessary) and discharged to the evaporation pond.

Sampling can be conducted directly by dip grab sampling or bysampling retention basin sump discharge (Figure 9.3-11,valves V089 or V090).

If a portable ion exchanger is used to purify the retentionbasin, expended resins will be disp'osed of in one of two ways.If resins are radioactive, they will be transferred by truckor drum to the solid radwaste system of either Unit 1, 2, or 3.If resins are not radioactive but do not meet chemistrylimits (excess chromate or other ions), resins will be hauledto a licensed disposal site. Regeneration is not currentlycontemplated due to the low frequency projected for thisoperation.

Amendment 7'.3-31E10-20-81

December 1981

PVNGS FSAR

LIQUID WASTE MANAGEMENT SYSTEMS

Table 11.2-7FPCCS EXPECTED PROCESS POINT ACTIVITIES (pCi/g) (Sheet 3 of 3)

RadionuclideSpent

Fuel PoolRefueling

Pool

Fuel PoolIX No. 1Outlet(

Fuel PoolIX No. 2Outlet (a)

CE-144PR-143PR-144NP-239CR-51

MN-54

FE-55FE-59CO-58

CO-60

See table11.1-5 11.1-5 1.7E«7

S.SE-S1.5E-62.2E-7

8.8E-94.8E-90.06.9E-81.6E-7

See table 3.3E-S

1.2E-105.0E-110.02.1E-101.9E-91.9E-92.3E-91.1E-91.9E-S3.0E-9

~ 7

through the LRS than necessary, non-radioactive turbine build-ing drains are processed by the chemical waste system. Besidesthe low TDS tank, an additional holdup tank is provided toaccommodate overflow from either the low TDS or the high TDS

holdup tank and is normally isolated from the supply headers.If necessary, this tank can be used to collect either low TDS

or high TDS liquid waste. An internal mixing header uniformlymixes the contents of each holdup tank prior to and duringprocessing. Acidic or caustic agents may be added for pH

control, and anti-foaming agents may be added if surfactantsexist in the tank contents. Decontamination facility wastesfrom Unit 1 only (including laundry liquid waste) and radio-chemistry laboratory wastes are collected in the chemicaldrain tanks prior to processing. Refer to section 12.5.2for further details on laundry system wastes.

Amendment 7 11.2-2010-,20-81 December 1981

1~

PVNGS FSAR


Table 11.2-8WASTE INPUTS TO THE LRS (Sheet 1 of 2)

LRS Inputs

Hi h TDS HolduTanks

Containment sump

Auxiliary build-ing floor drains

Condensatepolisherregenerants

Blowdowndemineralizerregenerants

Chemical draintank (includeslaundry inputs)

Laboratory drains

Miscellaneoussources

ExpectedFlow

(gal/d-unit)

40

200

12,000 gal/15 days

115

400

700

DesignFlow

(gal/d-unit)

40

200

20,000

12,000 gal/15 days

400

700

Activity

1 PCA(

0.1 PCA

100% ofregenerantwasteactzvxty

100% ofregenerantwasteactivitySee chemicaldrain tankinputs

0.002 PCA

0.01 PCA

Total 2,255 22,255

Low TDS HolduTank

Turbine buildingfloor drains

Secondary system

samples

7,200

300

, 7,200

300

100% of main,steamactivity

„„100% of main,'steam.activity

a. PCA = Primary Coolant Activity.

December 1981 11.2-2110-20-81 Amendment 7

PVNGS FSAR


Table 11.2-8WASTE INPUTS TO THE LRS (Sheet 2 of 2)

4

LRS Inputs

Low TDS HolduTank (cont.)

Condensatepolisherregenerants

Expected DesignFlow ,. Flow

(gal/d-unit) (gal/d-unit)

36,000

Activity

100% ofregenerantwasteactivity

Blowdowndemineralizerregenerants

12,000 gal/15 days

12,000 gal/15 days

100% ofregenerantwasteactivity

Total 8,300 44,300

Chemical DrainTanks

Decon stationwaste plusshowers (includeslaundry waste)

Primary systemsamples

100

15

100 SeeNUREG 0017,Table 2-20

1 PCA

Total 115 115

Amendment 711.2-2210-20-81 December 1981

w

PVNGS FSAR

11.4 SOLID WASTE MANAGEMENT. SYSTEM

Solid waste management is provided by the .solid radwaste system(SRS) which is designed to provide'oldup, solidification, andpackaging of radioactive wastes generated by plant operation,and to store these wastes until they are shipped offsite forburial. The system is located in the radwaste building, whichis designed to withstand an operating basis earthquake.

11.4.1 DESIGN BASES

The design bases of the solid waste management system are:

A. The SRS provides the capability for solidifying andpackaging concentrated'waste solutions from themiscellaneous waste evaporator, spent resins from .

radioactive ion exchangers, and chemical drain tankwastes.

B. The SRS provides a means for packaging and disposal ofspent radioactive cartridge filters and solid wastesfrom the LRS, CVCS, and laundry (unit 1 only).

C. The SRS provides a means of compacting and packagingmiscellaneous dry radioactive materials, such as paper,rags, contaminated clothing, gloves, and shoe coverings,and a means for packaging contaminated metallic mater-ials and incompressible solid objects, such as smalltools and equipment parts.

D. The SRS provides an alternate method of disposal of theliquid and crud from the backflushable filter crud tank.

, Note that the crud is normally removed by a disposablefilter and the liquid is normally processed by thechemical and volume control system discussed insection 9.3.4.

December 1981 11.4-1,10-20-81

Amendment 7

e

I

c

PVNGS FSAR

SOLID WASTE, MANAGEMENT SYSTEM

E. The SRS provides a method of solidifying and packagingblowdown demineralizer "resin and condensate polishingresin in the event that they become contaminated.

The maximum and expected input volumes to the SRS from each'

source of solid waste material are presented in table 11.4-1.The SRS input activities associated with the expected inputvolumes are presented in table 11.4-2.

Codes and standards applicable to 0he solid radwaste system arelisted in table 3.2™1.

Collection, solidification, packaging, and storage of radio-active wastes will be performed so as to maintain any potentialradiation exposure to plant personnel to "as low as is reason-ably achievable" (ALARA) levels, consistent with the recommen-dations of Regulatory Guide 8.8 and within the dose limits of10CFR20. Some of the design features incorporated to maintainALARA criteria include remote system operation, remotely actu-ated flushing, quick disconnect, equipment layout permittingthe shielding of components containing radioactive materials,and use of shielded casks for in-plant movement of high activitywaste. Additional ALARA provisions of the SRS are described insection 12.1.

Packaging and transport of radioactive wastes will be in con-formance with 10CFR71. Packaged wastes will be shipped in con-formance with 49CFR170-178. Collection, solidification, packag-ing, and storage of radioactive wastes will be performed inconformance with 10CFR50.

Laundry is cleaned by a dry-cleaning system. Solid wastes aremanually transfered to the SRS for packaging. Refer tosection 12.5.2.

Amendment 7 11.4-210-20-81

December 1981

I 0

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