ML17297A982

Forwards Draft FSAR Clarifications Re Facility Sampling Parameters (Table 9.3-3),secondary Sys Drain Sampling (Section 9.3.2.2.3),revised Pages 11.2-20 Through 22 & Pages 11.4-1 & 11.4-2.Info Will Be Included in FSAR Amend

ML17297A982
Person / Time
Site:	Palo Verde
Issue date:	10/28/1981
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Tedesco R Office of Nuclear Reactor Regulation
References
ANPP-19292-JMA, NUDOCS 8110300289
Download: ML17297A982 (43)

Text

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:STN 50 528 Pa>>1 or Ve'rdei Nucl ear>> Statiloni, Uhit>> 1P Ar>>izone Publ i STN 50 529 Palo; Ve'rdeI Nucle'eri StationP Unit" 2'P Arizona Publi STN"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."

O'ISTRXBUTEONi CODE>>: BDDIS'OPIEB RECEEVED:.LITRNCL>> J" SIZE'!ITLEI::

PSARr/FSAR AMDTS and Reil ated Cbr re'spondence iVOTES'.Stendiardized Plant;1 cy.'CI Gr ime's

~

Stenderdized Plant,i cy.'Cl Grimes'tenderdi zed Pl ant;1-cy: CI Grimes'5090528 05090529 05090530 REC'IPX EN Tr IOI CODE'/t>>IAMEI

, ACTKON::

A'/Dr L>>I CEiVSNG.

L>>ICI BRr 43>> LA INTERNAL>>

ELOI HiYD'/GEOI BR>>

30; IE'/E P D 8 I 35<

L>>ICI QU'ALr BRI 3?!

MP Al NRR'/DE'/EQB 1.3>>

NRR!/DE!/MTEBI NRRr/DBIVAS BI 27 NRR'/DS I>>/CSBI 09 NRR'/DS II/ICSB 16'RRr/D S Ti/l.G8!

3 3>>

PO'rlERr SYS'R 19 QA>>

l 2'f i KGi FILEI 04'VG, BR25I EXTERNALS" ACRS 41>>

FERA'EP DI.V 39 NRCI PDRI 02'.

NT'I8 COPIES LiTTR" E>>VCLr 1 ~

0 Q

1 0

2!

2' 1

1-1 1

0 3>>

3" f.

f.

]i 1 ~

1

~

1 1

1 1

1 1

f>>

1 1

1 1

16'6 1

1 1

1>>

1 RECIPIENT" ID CODE'/NAMEI LIICI BRr 43I BC; KERR>>IGANBJB, 01>>

HUM'ACiTiENG. 40 IE El 06" IEr/EPLBI 36" MKCHr ENG BR"'8 iVRR'/DEl/CEB 11.

NRR'/DEI/GBI 28 NRR'/DS I'/AEB'6" NRR"/DS I'/CPB 10'VRR'/DS I'/EITSB, 12',

>>VRR'/DS I'/RAB>>

22'P:

L>>ICr. BR" 34 PROC/TST'EV 20 REACi SYS'R 25>>

SXll'~ ANALt BR 2'4 B>>V L>>( AMD>>TS 'NL>>Y) lP DRi 0 3>>>>

>>VSI Cl 05" COP IKB'IT!TRI ENCLI 1

0.

1 f>>

1 f<

3 3i 3<

3$

1 1>>

1 f>>

2i 2>>

1>>

f<

1 1>

1 1>>

1

~

1>>

1 1 ~

1 f>>

1 1<<

TOiTAL" iNUNBER>> OF COPIES'EQUIRED:: l.ll'TR i

ENCL>>,

'I v

I

~

8

~,

e N

4DZKDEM STA.

Ãult&IICIKSIEPllt5lltl CKSKMEF P.o. BOX 21666 PHOENIX, ARIZONA85036 October 28, 1981 ANPP-19292 JMA/WFQ Mr. R. L. Tedesco Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555

~~)

p g4

( (')

Subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3

Docket Nos.

STN-50-528/529/530 File:

81-056-026; G.1.10

Dear Mr. Tedesco:

Attached please find draft FSAR clarifications regarding PVNGS sampling parameters (Table 9.3-3),

secondary systems drain sampling (Section 9.3.2.2.3),

revised pages 11.2-20 thru 22 and pages 11.4-1, 11.4-2.

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

Very truly yours, EEVBJr/WFQ/av Attachment 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 Projects ANPP Project Director p~c 1

(/i 8ll0300289 8110&8

~

PDR ADDCK 05000528 I

q A PDRy

~

~

STATE OF ARIZONA

)

) ss.

COUNTY OF MARICOPA) l f

I, John M. Allen, represent that I am Nuclear Engineering Manager of Arizona Public Service Company, that the foregoing document has been signed by me for Edwin E. Van Brunt, Jr., Vice President Nuclear Projects, on behalf of Arizona Public Service Company with full authority so to do, that I have read such document and know its contents, and that to the best of my knowledge 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 9.3-3 SAMPZING SYSTEM DESIGN PARAMETERS (Sheet 2 of 13)

/

Sample Origin Type of Sample cooler Typical Discrete Sample Analysis(b)

Pressurized Sample Capability

'ontinuous On Line Analysis Provided Mode of Sample Removal and Location Nominal Pressure (psig)

Tempera-ture ('F)

Figure No.

)7 Primar Sam lin S stem Cont'd

'Pressurizer Surge Line Reactor Drain Pump Discharge Before Filter Reactor Drain Pump Discharge After Filter Rough None None Boron Conductivity pH, Cl Boron Conductivity pI), Cl Boron No No No None None None Remote Aux Bldg E1-140'ocal Aux Bldg El-120'ocal

'Aux Bldg El-120'500 65 65 700 120 120

5. 1-1 9.3-2 9.3-13 9.3-13 Q C)

4) 4)

Q I

I 00 ~

Pre-holdup Ion Exchanger Outlet None Holdup Tank Inlet None Boric Acid Conden-None sate,Ion Exchanger Inlet Conductivity pH

.Conductivity pH, Boron, Cl Conductivity pH, Boron No No No None None None Local

~ Aux Bldg El 120'ocal Aux Bldg El-120' k Local Aux Bldg El-120'5 60 60 120 130 140 9.3-13 9.3>>13 9.3-13 Boric Acid Conden-sate Ion Exchanger Outlet None Conductivity pH, Boron No None Local Aux Bldg El-120'0 140 9.3-13 Reactor Makeup Water None Pump Discharge Reactor Makeup Water None Pump Recirculation.

Conductivity pH, Boron, Cl Conductivity pH, Boron No No None None Local Aux Bldg El-120'ocal Aux Bldg El-120'30 130 120 120 9.3-13 9.3-13 Boric Acid Makeup Pump Recircula-tion None Boron No None t,ocal Aux Bldg El-120'30 120 9.3-13 M

M

SHAFT

~ ~

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

C Sample Origin Type of Sample Cooler Typical Discrete Sample Analysis(b)

Pressurized Sample Capability Continuous On Line Analysis Provided Node of Sample Removal and Location Nominal Pressure (psig)

Tempera-ture ('F)

Figure No.

Ioe I

o (.

Primar Sam lin

~sstem Hot Leg Loop 1 Pressuriier Steam Space Shutdown Cooling Suction Lines 1

& 2 ESF A&B Train Safety Injection Pump Mini Flow Line Purification Filter Inlet Purification Filter

Outlet, Ion Exchanger Inlet Purification Ion Exchanger Outlet Rough Rough Rough Rough None None None pH ~ 02'2

'otal Dissolved

Gas, NH3, Lithium, Boron, Cl,

F

, Radio-activity 82 Boron, Radio-activity Boron, Radio-activity pH, NH3, Lithium, Boron, Cl F, Radio-activity Suspended Solids pH, Lithium, Boron Cl F

Radioactivity Yes Yes No No No No No None None None None None Radio-activ-ity<<)

None Remote Aux Bldg El-140'emote Aux Bldg E1-140

'emote Aux Bldg El-140'emote Aux Bldg El-140'emote Aux Bldg El 140'emote Aux Bldg El-140 s Remote Aux Bldg E1-140'485 2500 435 2050 60 50 50 621 700 350 350 120 120 120 5.1-1 9.3-2 5.1-1 9.3-2 6.3-1 9.3-2 6.3-1 9.3-2

/,

~

9.3-13 9.3 2

9.3-13 9.3-2 9.3-13 9.3 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.

Table 9.3-3 SAMPZING SYSTEM DESIGN PARAMETERS (Sheet 3 of 13) r Sample Origin Type of Sample Cooler Typical Discrete Sample Analysis(b)

Pressurized Sample Capability Continuous On Line Analysis Provided Node of Sample Removal and Location Nominal Pressure (psig)

Tempera-ture (4F)

Figure No.

O l

~

W 4l O

I (m

CO Primar Sam lin S stem Cont'd Boric Acid Makeup Pump Discharge Boric Acid Batching Tank Reactor Makeup Water to Volume Control Tank Volume Control Tank Drain to Recycle Drain Header CVCS Letdown Shutdown Cooling Heat Exchanger Outlet Safety injection Tanks 1,2,3,4 Secondar Sam le Po ill'ts Hotwell 1A, 2A, 18, 2B, lC, and 2C None Portable None None None Portable None Fine Boron Boron conductivity pH, Boron Cl Conductivity pH, Boron Boron Boron, Radio-activity Conductivity, pH, Boron Yes Cation Conductivity Sodium No No No No No No No No None None None None Yes Boron None None Yes Cation Conduc-tivity sodium Local Aux Bldg E1-120'ocal Aux Bldg El 120'ocal Aux Bldg E1-120'ocal Aux Bldg El-120'emote Aux Bldg El-120'ocal Aux Bldg E1-120'ocal Containment El-80'emote Hotwell Analysis Sta-tion Turbine Bldg 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 10.4-9 9.3-3 M

LM

a (0n (090'-

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

Sample Origin Secondar Sam le Points cont' Type of Sample Cooler Typical Discrete Sample Analysis(b)

Pressurized Sample Capability Continuous On Line Analysis Provided Mode of Sample Removal and Location Nominal Pressure (psig)

Tempera-ture (4F)

Figure No.

S/G 1 and 2 Hotleg Blowdown S/G 1 and 2 Coldleg Blowdown Rough &

Fine Rough 6 Fine Yes Conductivity pH & Radio-activity Yes Conductivity pH & Radio-activity No

Yes, Con-ductivity pH, Radio-activ-ity(c)

Yes, Con-ductivity pH, Radio-activ-i,ty(c)

'emote Cold Lab Aux Bldg E1-140'emote Cold Iab Aux Bldg El-140'179 1179 554 450 10.3-1 9.3-3 10.3-1 9.3-3 S/G 1 and 2

Downcomer Blow-down Condensate LP Heater Train A, B, and C

Outlet FW Pump A and B

Suction HP Heater Train A and B Outlet Rough 6

Fine Yes Conductivity pH 6 Radio-activity Portable Yes Conductivity Portable Yes Conductivity Portable Yes Conductivity No No No No

Yes, Con-ductivity pH &

Radio-activ-ity(c)

\\

None None None Remote Cold Lab Aux Bldg E1-140'ocal Turbine

Bldg, El-140'ocal Turbine Bldg El-140'ocal Turbine Bldg E1-140'179 400 400 1225 554 396 396 450 10.3 1

9.3-3:

10.4-9 10.4-10 10.4-10 MSR A, B, C and D Drain Portable Yes Conductivity Iron, Copper No None Local Turbine Bldg El 140'02(')

383 10.2 2

First Stage RHTR Drain Tank A, B, C and D

Portable Yes Conductivity Iron, Copper No None Local Turbine Bldg El-140'32(')

452 10.2 2

Second Stage RHTR Drain Tank A, B, C and D

Portable Yes Conductivity Iron, Copper No None Local Turbine Bldg E1-140'85(

)

543 10.2 2

0

Table 9.3-3 SAMPLING SYSTEM DESIGN PARAMETERS (Sheet 5 of 13)

Sample Origin Type of sample cooler Typical Discrete Sample Analysis(>>

Pressurized Sample Capability Continuous On Line Analysis Provided Nominal Node of Sample Removal and Pressure Location (psrg)

Tempera-ture (4F)

Figure No.

IOe

~ lA O) co O Seconda Sam le Pornts Cont'tr Drain Tank A and B Drain Htr Drain Pump A and B Discharge Spray Pond Water Circulating Water Outlets Condensate Tank Sample Portable Portable None Fine None Conductivity Iron, Copper Conductivity Iron, Copper Hardness

~ Alkalinity pH, TDS Conductivity Conductivity pH, Chlorine Conductivity pH, Chlorides Fluorides, Dissolved Solids.

Silica No No No No No None None Yes Conduc-tivity Yes Conduc-tivity pH Chlorine None Local Turb Bldg El 100'ocal Turb Bldg El 100'emote YarYa Area Remote Cold Lab Aux Bldg 140'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 10.4-4 9.3-3 9.2-8 U

(8n (0

Essential chiller A and B Outlets Essential cooling Water Pumps A

and B Discharge None None Normal Chillers None A, B, and C Outlet Headers pH, Chromate pH, Chromate pH, Chromate No No No None Radio-activ-ity(c)

None Local Control Bldg El 74'5 Local Aux Bldg 45 Roof El 15'>>

Local Aux Bldg 105 El70'9 9.2-11 9.2 4 9.2 10 M

M

0

Table 9.3-3 SAMPLING SYSTEM DESIGN PARAMETERS (Sheet 6 of 13) 4 Sample Origin Secondar Sam le Pornts Cont'd Type of Sample Cooler Typical Discrete Sample Analysis (b)

Pressurized Sample Capability Continuous On Line Analysis Provided Nominal Mode of Sample Removal and Pressure Location (psig)

Tempera-ture ('F)

Figure No.

f7 Nuclear Cooling Hater Pump Discharge Header None pH, Chromate No Radio-actjv-ity(c)

Local Aux Bldg El-88'0 105 9.2-5 shutdown Cooling Heat Exchanger Room A and B

Drain None pH Ho Hone Local Radwaste Atmos.

BldgEl-88'20 9'-7 LRS Hold-Up Tank Leak Drain None Radio-activity No None Local LRS Hold-up Tank Area El-100'tmos.

120 9.3-7 LRS Recycle Monitor Tank Leak Drain None Radio-activity No None Local LRS Hold-up Tank Area El-100'tmos.

120 9.3-7 Main Turbine Lube Oil Centrifuge Outlet None Suspended Solids No None Local Turbine Bldg El-100'5 120 FWPT Lube Oil Centrifuge Outlet Cooling H20 Hold-up Tank None Hone Suspended Solids Radioactivity pH, Chromate No Hone None Local Turbine Bldg El-100'ocal Aux Bldg El-40'0 75 52 120 9.3-10 f7 I

C)

I Chemical waste Neutralizer Tank (1 Sample Point at Each Tank)

None Condensate Polishing None Demineralizer (LO-TDS) Sump (2 Sample Points)

Radioactivity pH, Chromate Radioactivity No None None Local Yard Area E1-100'V088-V195)

Local Yard Area El-100'V028, V031) 10 60 75 100 9.3-10 9.3-10 0O Ul M

0 l

Table 9.3-3 SAMPLING SYSTEM DESIGN PARAMETERS (Sheet 7 of 13)

Sample Origin Secondar Sam le Pornts Cont'd Type of Sample Cooler Typical Discrete Sample Analysis(b)

Pressurized Sample capability Continuous On Line Analysis Provided Mode of Sample Removal and Location Nominal Pressure (psig)

Tempera-ture ('F)

Figure No.

Condensate Polishing None Demineralizer (HI-TDS) Sump (2 Sample Points)

Radioactivity No None Local Yard Area El-100'V034, V037) 60 100 9.3-10 O Q e

lV LO O

I I M co M I

Retention Basin (Holdup Prior to Evaporation Pond)

(2 Sample Points)

Spent Regeneration Sump (Water Reclamation Facility)

TCW Heat Exchanger A and B Outlet ESF Sump Pump A and B Discharge Non-ESF Sump Discharge Blowdown Demineral-izer Effluent (1)

Blowdown Demineral-izer Effluent (2)

Blowdown Demineral-izer Strainer Influent (1)

Blowdown Demineral-izer Strainer Influent (2)

None None None None None Rough Rough None Hone pH, Conductivit Radioactivity pH Chlorine Chlorine Chlorine Na, Si, pH, Conductivity Radioactivity, Na. Si, pH Conductivity Radioactivity Conductivity conductivity No No No No No Yes Yes Yes Yes None Yes pH Yes Chlorine None None

Yes, Na, pH.Si,Con-ductivity

Yes, Na, Si,pH,Con-ductivity Yes conduc-tivity Yes Conduc-tivity South of Unit 3 El-100'V089, V090) water Rec Facility Remote Yard Area Local Aux Bldg E1-40'ocal Aux Bldg El-40'emote Yard Area Remote Yard Area Remote Yard Area Remote Yard Area 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

a n

(080 Table 9.3-3 SAMPZING SYSTEM DESIGN PARAMETERS (Sheet.

8 of 13)

Sample Origin Type of Sample Cooler Typical Discrete Sample Analysis (bI Pressurized sample Capability Continuous On Line Analysis Provided Mode of Sample Removal and Location Nominal Pressure (psig)

Tempera-ture (4F)

Figure No.

Secondar Sam lin r

I I

co Lo I

Blowdown Demineral-izer Waste (High TDS)

Blowdown Demineral-izer Waste (Iow TDS)

Blowdown Demineral-izer Caustic Day Tank Effluent Blowdown Demineral-izer Acid Day Tank Effluent Diesel Fuel Oil Storage Tank A and B

Condenser Sump (North and South)

Pump Discharges Turbine Building Sump TCW Pump A and B

Discharge Auxiliary Steam Condensate Receiver Tank Auxiliary Steam None None None None None Hone None None Portable Rough Conductivity Radioactivity Conductivity Radioactivity Conductivity Conductivity

Apjo, Viscosity,

HVV, Sediment pH, suspended

'olids, Radio-activity pH, Suspended

Solids, Radio-activity pH Chloride, ions pH, Conductivity pH, Conductivity Yes Yes Yes Yes No No No No No No Yes Conduc-tivity Yes Conduc-tivity Yes Conduc-tivity Yes Conduc-tivity None None None None Radio-activ-ityIc)

None Remote Yard Area (V182, V204)

Remote Yard Area (V172, V169)

Remote Yard Area Remote Yard Area Local Outside by D.G. Bldg El-100'ocal Turb Bldg El-100'V075, V078)

Local Turb Bldg El-100'V076)

Local Turb Bldg E1-105'ocal Turb.

Bldg El-100'ocal Yard Area 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 9.3-3 SAMPLING SYSTEM DESIGN PARAMETERS (Sheet:

9 of 13)

Sample Origin Type of Sample Cooler Typical Discrete Sample Analysis(b)

Pressurized Sample Capability Continuous On Line Analysis Provided Mode of Sample Removal and Location Nominal Pressure (psig)

Tempera-ture ('F)

Figure No.

l7 IQS bJ 4)

Q I

I C0 +

Seconder Sam lin Points Cont d Circulating Water Cooling Towers Demineralized Water Surge-Rinse Tank Demineralized Water Storage Tank Fuel Pool Clean-up Pump (1 & 2)

Discharge (Spent Fuel Pool or Refueling Pool)

Fuel Pool Cleanup Filter 1 and 2

Outlet (Spent Fuel Pool or Refueling Pool)

Fuel Pool Cleanup Demineralizer 1

2 Outlet (Spent Fuel Pool or Refueling Pool)

Radwaste Sam lin Points Evaporator Feed from LRS Holdup Pumps Chemical Drain Pump Discharge None None None None None None None None Water Chemistry Water Chemistry pH, Chloride, ions, Fluoride ions, Boric Acid Hydrazine, Ammonia, Lithium

~Radioactivity IConductivity, pH, Chloride

ions, Suspended

Solids, Sodium, Radioactivity Conductivity, pH, Chloride

ions, Suspended

Solids, Sodium, Radioactivity pH pH, Conductivity No No No No No No Yes Yes Foam None None None None None None None Local Cooling Tower Area Wtr Treatment Area Local Yard Area Local Fuel Bldg El-100'ocal Aux Bldg El-120s Local Aux Bldg E1-120'ocal Radwaste Bldg El-100'ocal Radwaste Bldg El-40'tmos.

20 288" H20 90 50 50 107 psia 88 psia 108 Ambient Ambient 125 125 125 60 to 120 60 to 120 10.4 4

9.2-6 "9.2-6 9.1-9

~9'1-9 t

9. 1-9 11.2-2 11.2-2

)6 M

W M

IC

Table 9.3-3 SAMPLING SYSTEM DESIGN PARAMETERS (Sheet:

10 of 13)

Sample Origin Radwaste Sam lin Pornts Cont'd Type of Sample Cooler Typical Discrete Sample Analysis (b)

Pressurized Sample Capability Continuous On tine

'Mode of Sample Analysis Removal and Provided Location Nominal Pressure (psig)

Tempera-ture ('F)

Figure No.

Hi-Lo TDS Holdup Pump Recycle None pH, Conduc-tivity Boric Acid Concentration Yes None Local Radwaste Bldg El 100'i-TDS 55 psia LO-TDS 42 psia eo-120 11.2 2

Evaporator Concen-trate Pumps Recycle to Vapor Body Portable Boric Acid Con-centration, pH,

,, Wtg "Solids Yes None Local Radwaste Bldg El-120'24 11.2-2 Ioe m LO O

I I

CO Ol Cas Sam lin S stem Gas Surge Tank Gas Decay Tank None Hone Radioactivity, H2, 02 Radioactivity, H2, 02 No Yes H2,02 (d)

H2,02 (d)

Remote Rad-waste Bldg El-140'emote Rad-waste Bldg El-140'80 380 200 200 11.3>>2 9.3-2 1'1'.3-2 9.3-2 Cas Stripper None Radioactivity, H2, 02 Yes H2,02 (d)

Remote Rad-waste Bldg El-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 Radioactivity, H2, 02 Radioactivity, H2, 02 No No No H2,02 (d)

H 0 (d) 2' H2,02 (d)

Remote Rad-waste Bldg El-140'emote Rad-waste Bldg El-140'emote Rad-waste Bldg E1-140'0 120 120 120 9.3-13 9.3-2 9.3-13 9.3-2 11.3-2 9.3-2

Table 9.3-3 SAMPLING SYSTEM DESIGN PARAMETERS (Sheet 11 of 13)

Sample Origin Holdup Tank Type of Sample Cooler None Typical Discrete Sample Analysis(b)

Radioactivity, H2, 02 Pressurized Sample Capability No Continuous On I.ine Analysis Provided H2,02 (d)

Mode of Sample Removal and Location Remote Rad-waste Bldg El-140'ominal Pressure (psig)

Tempera-ture ('F)

Atmos.

120 Figure No.

9.3-13 9.3-2 (7

Containment Atmosphere Containment Purge Exhaust None None Radioactivity Radioactivity No No Radio-activ-ity(c)

Radio-actjv-ity(c)

Local Aux Bldg 100'evelNE Quad Iocal Aux.

Bldg 140'evelNE Quad Atmos.

122 120

9. 4-13 9.4-13 oe

)

~

o

)M co Ql Plant Vent Containment Atmosphere Control Building Outside Air Intake Post-Accident Sam Inn S stem None None None Radioactivity Moisture (4 points)

Radioactivity

Smoke, C12, 2 points each No No No Radio-activ-ity(c)

Yes Moisture (4 points)

Radio-activ-ity(c)

Smoke, C12, 2 points each Local Turb Bldg 160'evel Local 1 at

'El-104'-6" NW Quad; 1 at El 124>-9 NW Quad; 2 later Remote Con-trol Bldg, 140'evel in Outside Air Chase Atmos.

120 122 Atmos.

113 9.4-13 9.4-12 9.4-1 Hot Leg Loop 1 Rough

Isotopic, Gross

Gamma, pH, Oxy-

gen, Hydrogen, Chloride, Boron Yes

Isotopic, Gross

Gamma, pH,

Oxygen, Hydrogen,

Chloride, Boron Remote Aux Bldg, Eleva-tions 140'nd 70'yringe Grab Sample 2485 621 9.3-2A MtM

Table 9.3-3 SAMPZING SYSTEM DESIGN PARAMETERS (Sheet 12 of 13)

Sample Origin Type of Sample Cooler Typical Discrete Sample Analysis (b)

Pressurized Sample Capability Continuous On t.ine Analysis Provided Mode of Sample Removal and Location Nominal Pressure (psig)

Tempera-ture ('F)

Figure No.

7 Post-Accident Sam lan S stem

~CoC '

Hot I.eg Loop 2 Rough Isotopic.

Gross

Gamma, pH, Oxy-

gen, Hydrogen,

Chloride, Boron Yes

Isotopic, Gross

Gamma, pH,

Oxygen, Hydrogen,

Chloride, Boron Remote Aux Bldg, Eleva-txons 140'nd 70'yringe Grab Sample 2485 621 9.3-2A ESF A&B Safety Injection Sumps ESF A&B Safety Injection Hini Flow Line Containment Radwaste.Sumps Rough Rough Rough

Isotopic, Gross

Gamma, pH, Oxy-

gen, Hydrogen,

Chloride, Boron

Isotopic, Gross

Gamma, pH, Oxy-

gen, Hydrogen.

Chloride, Boron

Isotopic, Gross

Gamma, pH,- Oxy-

gen, Hydrogen,

Chloride, Boron Yes Yes Yes

Isotopic, Gross

Gamma, pH

Oxygen, Hydrogen,

Chloride, Boron

Isotopic, Gross

Gamma, pH,

Oxygen, Hydrogen,

Chloride, Boron

Isotopic, Gross

Gamma, pH,

Oxygen, Hydrogen,

Chloride, Boron Remote Aux Bldg, Eleva-tions 140'nd 70'yringe Grab Sample Remote Aux Bldg, Eleva-tions 140'nd 70'yringe Grab Sample Remote Aux Bldg, Eleva-tions 140'nd 70'yringe Grab Sample 60 2050 60 350 350 120 9.3-2A r.~

9.3 2A 9.3-2A 0A MN C

M M

M W

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

Sample Origin Post-Accident

~sx s st.

cont Type of Sample Cooler Typical Discrete Sample "Analysis(>>

Pressurized Sample capability Continuous On Line Analysis Provided Node of Sample Removal and Location Nominal Pressure (psig)

Tempera-ture ('F)

Figure No.

O

~

bD I

Auxiliary Building Sumps Containment Air Rough Rough

Isotopic, Gross

Gamma, pH, Oxy-

gen, Hydrogen,

Chloride, Boron

Isotopic, Gross

Gamma, Oxygen (Hydrogen provided by Containment Hydrogen Control System)

Yes Yes

Isotopic, Gross

Gamma, pH,

Oxygen, Hydrogen.

Chloride, Boron

Isotopic, Gross

Gamma, Oxygen (Hydrogen provided by Con-tainment Hydrogen control System)

Remote Aux Bldg, Eleva-tions 140'nd 70'yringe Grab Sample Remote Aux Bldg, Eleva-tions 140'nd 70'yringe Grab Sample 50 60 120 350 9.3-2A 9.3 2A 0n W

PVNGS FSAR 9.3.2.2.2 Post-Accident PROCESS AUXILIARIES Liquid samples are taken from both RCS hot legs, containment sumps, auxiliary building sumps and the ESF A6B mini-flow line.

All samples are routed to a liquid;input header.

After sample selection, isotopic analysis is performed.

The sample is then depressurized and cooled to allow chemical analyses to be performed.

At this point a syringe grab sample can be taken; or the sample can be discharged to the RDT or EDT.

Upon completion of the analysis, the source is isolated, and the system is then purged with demineralized water, then nitrogen gas.

Gas samples are taken from containment air via the containment hydrogen control system.

Samples are routed to a gas input header.

Isotopic analysis is performed then the sample is depressurized and cooled to STP conditions in order to perform 02 analysis.

A syringe grab sample can be taken or the sample is returned to the containment.

The. normal hot lab counting room at the 140-foot elevation in the auxiliary building is shielded to provide low background post accident.

The counting chamber can be purged with instrument air or bottled gas.

When the analysis is complete, the source is isolated, and the system is 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 provide information on isotopic content, gross

gamma, gaseous oxygen,'nd hydrogen (from hydrogen monitor of the containment hydrogen control system).

9.3.2.2.3 Secondary Systems Drain Sampling There are eight sumps in or near Turbine Building Structures with potential for transferring radioactivity to flow paths leading to the retention basins/evaporation ponds.

There are Amendment 7

9. 3-31A 10-20-81 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 has an analysis point on its discharge piping and can transfer fluids to the liquid radwaste system (LRS), either of two chemical waste neutralizing tanks (CWNT), or to an oil/water separator.

Each CWNT has separate analysis points,and can be sampled prior to discharge.

Each CWNT can discharge-to the LRS 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 significant radioactivity to these

sumps, and it, is not likely that the sumps would be aligned to discharge radioactivity to the retention basins.

The following are the sources to these sumps:

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 drain Turbine cooling water heat exchanger drain (nonradioactive)

Turbine cooling water surge tank drain (nonradioactive)

Heater blowdown stack Condensate storage tank December 1981 9.3-31B 10-20-81 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 drains Condenser evacuation drain Steam seal exhauster drain Isophase bus cooler drain (nonradioactive)

H2 seal oil cooler (nonradioactive)

Condensate pump drainage Turbine Buildin Sum Feedwater pump lube oil reservoir drains (nonradioactive)

Feedwater pump drain Turbine 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 or blowdown.

No regenerant chemicals are present.

Thus, any radioactivity which is present must be at least as dilute as the 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 will detect abnormal activity in the secondary as it is diverted to the blowdown processing equipment.

The condenser gland seal exhauster monitors 13-J-SQN-RU-141 and RU-142 (low and high range) 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 paths will be aligned to transfer to.the LRS or the CWNT's with sub-sequent alignment to the LRS.

However, if it is determined during operating (by sampling or monitoring) that the sumps do not contain significant radioactivity, they may be realigned to 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 dissolved solids (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 for grab sampling.

For either processing stream, initial regener-ant eluent is fed to the resin and subsequently directed to the high TDS sumps.

These discharge to the CWNT's.

As noted previously, the CWNT's,can discharge to the LRS or retention basins and are sampled prior to discharge.

Only after the TDS level of the regenerant has drops (associated with activity levels),

as measured by on-line conductivity cells, would flow be directed to the low TDS sumps, or the circulating water system (and thence to the evaporation ponds via blowdown).

Thus, the systems are designed to send radioactive waste to the LRS and yet recover clean liquid for recycle to the greatest extent practical.

To ensure that abnormal levels of activity are not sent to clean systems, design provisions for sampling are being clarified.

FSAR Table 9.3-3 is being revised to show the sampling capabilities at these sumps.

Operationally, when significant activity is present in the secondary (as detected by the steam generator blowdown or condenser gland seal exhaust monitors) the low TDS sumps will be aligned to dis-charge to the high TDS sumps.

A grab sample analysis for radioactivity will be required prior to changing this alignment, to allow discharge to the circulating water.

December 1981 9.3-31D 10-20-81 Amendment 7 7

PVNGS FSAR PROCESS AUXILIARIES In summary, the secondary systems are continuously monitored for activity. If abnormal activity is present, this will lead to alignment of leakage and cleanup stream discharge to the LRS. If after grab sampling, no abnormal activity is present in,effluents they can be directed to the circulating water or 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 is divided into identical compartments.

The compartments have sloping sides and are approximately 172' 98't top and 121' 47't. bottom.

Nominal depth is 6-1/2 feet with 2 feet freeboard; The top of the dikes are 4-1/2 feet above grade to provide flood protection.

The basins act as storage in the event the effluent is not within the standards for pH, conductivity, and radioactivity prior to discharge to the evaporation pond.

One retention basin can store the normal waste effluent of 800 gal/min for a 10-hour period.

The offline basin is monitored, chemically treated (if necessary) and discharged to the evaporation pond.

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

If a portable ion exchanger is used to purify the retention

basin, expended resins will be disp'osed of in one of two ways.

If resins are radioactive, they will be transferred by truck or drum to the solid radwaste system of either Unit 1, 2, or 3.

If resins are not radioactive but do not meet chemistry limits (excess chromate or other ions), resins will be hauled to a licensed disposal site.

Regeneration is not currently contemplated due to the low frequency projected for this operation.

Amendment 7'.3-31E 10-20-81 December 1981

PVNGS FSAR LIQUID WASTE MANAGEMENT SYSTEMS Table 11.2-7 FPCCS EXPECTED PROCESS POINT ACTIVITIES (pCi/g) (Sheet 3 of 3)

Radionuclide Spent Fuel Pool Refueling Pool Fuel Pool IX No.

1 Outlet(

Fuel Pool IX No.

2 Outlet (a)

CE-144 PR-143 PR-144 NP-239 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 See table 11.1-5 11.1-5 1.7E<<7 S.SE-S 1.5E-6 2.2E-7 8.8E-9 4.8E-9 0.0 6.9E-8 1.6E-7 See table 3.3E-S 1.2E-10 5.0E-11 0.0 2.1E-10 1.9E-9 1.9E-9 2.3E-9 1.1E-9 1.9E-S 3.0E-9

~7 through the LRS than necessary, non-radioactive turbine build-ing drains are processed by the chemical waste system.

Besides the low TDS tank, an additional holdup tank is provided to accommodate 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 uniformly mixes the contents of each holdup tank prior to and during processing.

Acidic or caustic agents may be added for pH

control, and anti-foaming agents may be added if surfactants exist in the tank contents.

Decontamination facility wastes from Unit 1 only (including laundry liquid waste) and radio-chemistry laboratory wastes are collected in the chemical drain tanks prior to processing.

Refer to section 12.5.2 for further details on laundry system wastes.

Amendment 7

11.2-20 10-,20-81 December 1981

1~

PVNGS FSAR LIQUID WASTE MANAGEMENT SYSTEMS Table 11.2-8 WASTE INPUTS TO THE LRS (Sheet 1 of 2)

LRS Inputs Hi h TDS Holdu Tanks Containment sump Auxiliary build-ing floor drains Condensate polisher regenerants Blowdown demineralizer regenerants Chemical drain tank (includes laundry inputs)

Laboratory drains Miscellaneous sources Expected Flow (gal/d-unit) 40 200 12,000 gal/

15 days 115 400 700 Design Flow (gal/d-unit) 40 200 20,000 12,000 gal/

15 days 400 700 Activity 1 PCA(

0.1 PCA 100% of regenerant waste actzvxty 100% of regenerant waste activity See chemical drain tank inputs 0.002 PCA 0.01 PCA Total 2,255 22,255 Low TDS Holdu Tank Turbine building floor drains Secondary system samples 7,200 300

, 7,200 300 100% of main

,steam activity 100% of main

,'steam

.activity a.

PCA = Primary Coolant Activity.

December 1981 11.2-21 10-20-81 Amendment 7

PVNGS FSAR LIQUID WASTE MANAGEMENT SYSTEMS Table 11.2-8 WASTE INPUTS TO THE LRS (Sheet 2 of 2) 4 LRS Inputs Low TDS Holdu Tank (cont.)

Condensate polisher regenerants Expected Design Flow Flow (gal/d-unit) (gal/d-unit) 36,000 Activity 100% of regenerant waste activity Blowdown demineralizer regenerants 12,000 gal/

15 days 12,000 gal/

15 days 100% of regenerant waste activity Total 8,300 44,300 Chemical Drain Tanks Decon station waste plus showers (includes laundry waste)

Primary system samples 100 15 100 See NUREG 0017, Table 2-20 1 PCA Total 115 115 Amendment 7

11.2-22 10-20-81 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, and packaging of radioactive wastes generated by plant operation, and to store these wastes until they are shipped offsite for burial.

The system is located in the radwaste building, which is 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 and packaging concentrated'waste solutions from the miscellaneous waste evaporator, spent resins from.

radioactive ion exchangers, and chemical drain tank wastes.

B.

The SRS provides a means for packaging and disposal of spent radioactive cartridge filters and solid wastes from the

LRS, CVCS, and laundry (unit 1 only).

C.

The SRS provides a means of compacting and packaging miscellaneous 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 small tools and equipment parts.

D.

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

, Note that the crud is normally removed by a disposable filter and the liquid is normally processed by the chemical and volume control system discussed in section 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 packaging blowdown demineralizer "resin and condensate polishing resin 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 input volumes are presented in table 11.4-2.

Codes and standards applicable to 0he solid radwaste system are listed in table 3.2'1.

Collection, solidification, packaging, and storage of radio-active wastes will be performed so as to maintain any potential radiation 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 of 10CFR20.

Some of the design features incorporated to maintain ALARA criteria include remote system operation, remotely actu-ated flushing, quick disconnect, equipment layout permitting the shielding of components containing radioactive materials, and use of shielded casks for in-plant movement of high activity waste.

Additional ALARA provisions of the SRS are described in section 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 in conformance with 10CFR50.

Laundry is cleaned by a dry-cleaning system.

Solid wastes are manually transfered to the SRS for packaging.

Refer to section 12.5.2.

Amendment 7

11.4-2 10-20-81 December 1981

I 0