ML17277A936

Forwards Rev 0 to Dissolved Gas Analysis. Implementation of post-accident Sampling Sys & Final Dissolved Gas Sampling Procedure Contingent Upon Receipt of Mod Equipment from GE to Be Delivered by 831130

ML17277A936
Person / Time
Site:	Columbia
Issue date:	10/13/1983
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML17277A937	List: ML17277A936 ML17277A938
References
GO2-83-918, NUDOCS 8310180449
Download: ML17277A936 (5)

Text

Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 October 13, 1983 G02-83-918 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PROJECT NO. 2 POST ACCIDENT SAMPLING AND ANALYSIS OF DISSOLVED GASES

References:

1) Letter, G02-83-557, G. D. Bouchey (SS) to A.

Schwencer (NRC), "Post Accident Sample Analysis and Core Damage Evaluation Procedure", dated June 23, 1983

2) Letter, OG3-83-209, GE to BWR Owners Group PASS Committee Members, dated August 18, 1983

-3) Letter, T. J. Dente (BWROG Chairman) to D. G. Eisenhut (NRC), "Implementation of Dissolved Gas Measurement Capability for the GE Post-Accident Sampling System (PASS)", dated August 19, 1983 Enclosed is a copy of the Wlp-2 interim. Plant Procedure 12. 10.8, " 'olved Gas lysis". This procedure is based on the General Electric "Interim Pr cedore for a pl.ing Dissolved Gases Using GE Post Accident Sampling'ystem (PASS)",

transmitted per Reference 2, which will allow interim plant operation to proceed while the GE modifications for the PASS are implemented (Reference 3). Implementa-tion of the system and.a final dissolved gas sampling procedure is contingent upon Po>l Il 83iOi80449 8310iS PDR ADOCK 05000397 A PDR

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I REGULATORY (FORMATION DI'STRIBUTION 'S EM (RIDS)

- 'ACCESSION 83/10/13 NOTARXZED>> NO DOCKET '0 NBR:8310180449 DOC,DATE>>

FACII.!'50 397 NPPSS Nuclear='Projects Unit 2i Hash{rigton'IPubl ic .Powe 05000397

'RUTH, NAME AUTHOR AFFILIATION GSORENSEN>G,'O. We>>Winston ipubl,lc:Power 'SuPPly 'System I GREC IP," NAME RECIPIENT, AFFIL'IATION

>SCHHENCERrA ~ Lticensing Branch'2

'SUBJECTS Forwards Rev 0 <<to "Dissolved Gas Analysis,," Implementation of post-accident samplin'g sys 8 final dissol.ved gas.sampling, lpr ocedur e contingent upon receipt of mod iequipment ft om GE to be delivered by 831130 CODE: 8001'S COPIES "RECEIVEDCLTR . 'IENCL

'DISTRIBUTXON

'SIZES '

.TITLE: Licensing 'Submittal >> ~PSAR/FSAR Amdts '8 >Related Conrespondence>

NOTES:

RECIPIENT >COPIES 'RECIPIENT >COPIES

=-ID LTTR'ENCL ID >CODE/NAME LT'TR ENCL' NRR L'82 'BC CODE/NAME'RR/DL/ADL 1 0 NRR LB2 LA 1 0 AULUCKrR~ 01 1 1 INT>ERNAL~ >ELD/HDS2 1 0 IE FILE IE/DEPER/EPB 3 >3 IE/DEPER/IRB '35 21 36'E/DEQA/QAB 1 1 NRR/DE/AEAB NRR/DE/CEB 1 1 NRR/DE/EHEB NRR/DE/EQB 13 2 '2 NRR/DE/GB 28 NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 NRR/DE/SAB .24 1 1 NRR/DE/SGEB 25 NRR/DHFS/HFE840 1 1 NRR/DHFS/lQB NRR/DHFS/PSRB 1 1 32'RR/DL/SSPB NRR/DSI/AEB 26 1 1 NRR/DS I/ASB NRR/DSI/CPB 10 1 1 NRR/DSI/CSB 09 NRR/DSI/ICS8 16 1 NRR/DS I'/MEIT8 1'2 NRR/DSX/PSB 19 AB FI 04 22'REG NRR/DSI/RS8 23 1 1 RGN5 AMI/MI8 EXTERNAl>> ACRS 41 6 .6 BNL(AMDTS ONLY) 1 1 DMB/DSS (AMDTS) 1 1 FEMA>>>>REP DIV >39 1 1 LPDR 03t 1= 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1

,'TOTAL NUMBER OF .COPIES REQUIRED; L'TTR 53. ENCL 46

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A. Schwencer Page Two October 13, 1983 POST ACCIDENT SAMPLING AND ANALYSIS OF DISSOLVED GASES receipt of modification equipment from GE which is scheduled for delivery to NNP-2 by November 30, 198~3. The equipment is expected to be installed, tested and operational by February 1, 1984, at which time the final procedure for the, sampling and analysis of dissolved-gases will be transmitted. It is the position of the Supply System that the enclosed procedure is acceptable for unrestricted plant operation while the modifications to the PASS are imple-mented as stated in Reference 3. Our commitment to transmit the interim procedure as discussed in Reference 1 is complete per enclosure.

If there are any questions, please contact, Mr. P. L. Powell, Manager, WNP-2 Licensing.

Very truly yours, G. C. Sorensen, Acting Manager Nuclear Safety and Regulatory Programs BDP/tmh Attachment cc: R Auluck NRC WS Chin - BPA A Toth - NRC Site