ML17277B178

Forwards Supplemental Info Re Equipment Justification Number 1.Equipment Qualified for LOCA Conditions & Can Be Expected to Perform Safety Function If Needed to Mitigate Accident Condition

ML17277B178
Person / Time
Site:	Columbia
Issue date:	12/12/1983
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
References
GO2-83-1139, NUDOCS 8312190155
Download: ML17277B178 (6)

Text

REGULATORY ORNATION OISTRISUTION SYS>> (RIOS)

ACCESSION NBR:8312190155 DOC ~ DATE: 83/12'/12 NOTARIZED: NO DOCKET FACIL:50-397 NPPSS Nuclear Pr oJect~ Unit"'2< Washington"Public Powe'5000397 AUTHrNAME AUTHOR AFFILIATION SORENSEN~G,CD Washington Public Power Supply System RECIP ~ NAME RECIPIENT AFFILIATION SCHNENCERgA, Licensing. Branch Forwards supplemental info ve equipment">>Justification Number' 2'UBJECT:

~ Equipment -qualified for LOCA conditions' can beI expected

-"to per form: safety function if needed to mitigate accident condition.

DISTRIBUTION CODE ~ 8001S 'COPIES RECEZQED ~ LTR /,">>ENCL>> SIZE ~,=

TITLE: Licensing -Submittal:;PSAR/FSAR Amdts 8 Related Carrespondeoce NOTES!

RECIP IENT COPIES RECIPIENT >>COPIES IO CODE/NAME, LTTR ENCL ID* CODE/NAME LTTR ENC NRR/OL/ADL NRR LB2 BC 1 NRR L82 LA 1 AULUCKgR ~ 01 1 INTERNAL: ELD/HDS2 1 IE .FILE>> 1 IE/DEPER/EPB I IE/DEPER/IRB 35 1 21

• 36'E/DEQA/QAB 1 NRR/DE/AEAB 1 11 'R"/OE/CEB 1 NRR/DE/EHEB 1 NRA/DE/EQB 13* 2 NRR/DE/GB 28 2 NRR/DE/MEB 18 1 NRR/DE/MTEB 17 1 NRR/DE/SAB 24 1 NRR/DE/SGEB 25 1 NRR/DHFS/HFEB40- 1 NRR/DHFS/LQB 1.

NRR/OHFS/PSRB 1 32'RR/DL'/SSPB 1

NRA/DS I/AEB 26 1 NRR/DS I/ASB 1 NRA/DSl/CPB 10 1 NRR/DS I/CSB 09. 1 NRR/DSI/I CSB 16 NRR/DSI/METB 12 1 NRR/DSI/PSB 19 1 NRR 8 22'E>>

1 NRR/DSI/RSB 23~ 1 04 1 RGN5 3 /9 MI8 1 EXTERNALS ACRS 6 BNL (AMDTS ONlY) 1 DMS/DSS (AMOTS) 1- FEMA~REP DIV 39 1.

LPDR 03 1 NRC PDR 02 1 NSIC 05. 1 NTIS 1 53 ENCL Q

)TOTAL NUMBER OF COPIES REQUIRED LTTR

e b II, f

) jf

! I ff p lff I I > 'P '1 I ) F lf 'p)I $ ff) ill,

)Plt,'1 I., 'ill Plfr f>>c>tffff,}f>"fr ) I>r" P ff, ae g p,'yp '1 f:p e} Q ffp fr f p>') III p, 1'4 I 'l>>0)pf lf ff'II )

IP>) ) c}s') rpII, } ll, q I'pef>p>> },If } ff

) )F)f~l ll)gp t I}

'} l.g P'

'p plFpfp>>

) Niff>PP > )>qt><<)F>p} fr I ()fr>i < QApp)'f,t'>> fr( >'.

",Pq> >

~ e) <<<<e <<<<eg e e~ p),,'

Fl +I/ 'fPF'I P rl Itr, 0,,'4}I~'e>e 'fll 3 P I II >> I ) e) i]f r 1(,) 'I p ) 'pp, 'lf >> I

,k I.f /If pf I

a I

iw f'Pp H.

I I'I ll II e l

(]I )

'" ~ ') I t>> If) P

/ 'I )rf"

Washington Public Power Supply System P.O. Box 968 3000George Washington Way Richland, Washington 99352 (509) 372-5000 Docket No. 50-397 December 12, 1983 G02-83-1139 Director of Nuclear Reactor Regulation 83g2190155 831212 Attenti on: Mr . A. Schwencer, Chi ef PDR ADOCK 05000397 A PDR Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PROJECT NO. 2 JUSTIFICATION FOR INTERIM OPERATION kl CIA PROGRAMMER

References:

a) G02-83-1089, G. C. Sorensen to A. Schwencer, "Valve Nitorgen Supply," dated November 23, 1983.

b) G02-83-842, G. C. Sorensen to A. Schwencer, "Environ-mental gualification Report for safety Related Equip-ment, September 1983," dated September 16, 1983.

In response to your staff's request for additional information and con-clusions regarding the subject equipment, please find attached a dis-cussion of equipment features and our conclusions regarding equipment qualification.

The equipment is qualified for LOCA accident conditions. We confidently conclude that the equipment can be expected to perform its safety func-tion if it is needed to mitigate an accident condition. We hope this supplemental discussion will assist you in reaching the same conclusion.

Very truly yours,

~a G. C. Sorensen, Manager Regulatory Programs GCS:KRW.st Attachment cc: R. Auluck, NRC W. S. Chin, BPA A. Toth, NRC Site g QQ>0 0 co)

SUPPLEMENTAL INFORMATION ON EQUIPMENT JUSTIFICATION i'll EPN'IA-PROG-lA Additional information has been obtained to qualify and further justify the programmer. This data is summarized below:

LOCA - During the LOCA, the programmer is exposed to a maximum of T = 128 F, R. H. = 65% and the six-month integrated dose is 1.2x104 rad. Review of the materials of construction show that the programmer is not susceptible to these conditions. It should be noted that the programmer does not contain any integrated circuits.

The programmer is qualified for the LOCA conditions.

HELB - The worst case HELB conditions include a maximum T = 180o F and R. H. = 100%. I/hi le steam test results are not currently avail-able, the following data strongly indicates that the programmer will perform its required function:

1) The programmer is hermetically sealed.

2) The long-term humidity of Profile 21X is not a steam condition, but is due to hot water on the reactor building floor. R. H. =

100% is a conservative representation of this condition.

3) The equipment would be accessible soon after a HELB for mainte-nance.

4) In any one HELB accident, one of the programmers would not be exposed to temperatures in excess of 128o F.

It is concluded that the programmer will perform its safety function for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and access for maintenance can then be accom-plished.

Additional information has also been obtained on operation of the ADS sys-tem. The charged accumulator tanks on the safety;relief valves are sized to operate each valve five times, instead of once as previously stated.

This number of operations should be sufficient to depressurize the reactor without use of the CIA system for additional valve cycling.

4 p

'