ML17286B087

Forwards Primary Containment 1991 Integrated Leakage Rate Test Final Rept.

ML17286B087
Person / Time
Site:	Columbia
Issue date:	10/10/1991
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17286B088	List: ML17286B087 ML17286B089
References
GO2-91-184, NUDOCS 9110160224
Download: ML17286B087 (3)

Text

"'ACCELERATED D RIBUTION DEMONST TION 'SYSTEM REGULATORY INFORMATION .DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9110160224 DOC.DATE: 91/10/10 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION SORENSEN,G.C. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards "Primary Containment 1991 Integrated Leakage Rate Test Final Rept."

DISTRIBUTION CODE. A017D COPIES RECEIVED..LTR TITLE: OR Submittal: Append J Containment Leak Rate Tes Q ENCL SIZE..

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NOTES: 5WW/~~Mf 7r"

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RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL A PD5 LA 1 0 PD5 PD 1 1 ENG,P.L. 2 2 D INTERNAL: ACRS 6 6 NRR/DST/SPLB SD 1 1 D

OC/LFMB 1 0 OGC/HDS 1 1 1 1 1 RES/DE/SEB 1 1 R)f -

R/SAIB 1 1 RES/DSR/RPSB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 R

D A

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 17

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 96B ~ 3000 George Washington Way ~ Richland, Washington 99352 October 10, 1991 G02-91-184 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST

Reference:

1) WNP-2 Final Safety Analysis Report, Washington Public Power, Supply System

2) Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors, Code of Federal Regulations, Title 10, Part 50, Appendix J

3) Leakage Rate Testing Containment Structures for Nuclear Reactors, American National Standards Institute, Inc., New York, NY; ANSI N45.4-1972

4) Letter, DM Crutchfield (NRC) to GC Sorensen (SS),

"Issuance of Exemption to a Provision of Appendix J and Amendment No. 41 to Facility Operating License No. NPF-21, WPPSS Nuclear Project No. 2 (TAC No. 60740)",

dated April 29, 1987 In accordance with the reporting requirements stipulated in Reference 2, and in compliance with the testing commitments, regulations and guidelines specified in References 1, 2, 3 and 4, the Reactor Containment Building Integrated Leak Rate Test, 1991 is submitted.

Very truly yours, G. C. Sorensen, Manager Regulatory Programs JRC/bk Attachment cc: JB Martin - NRC RV NS Reynolds - Winston S Strawn PL Eng - NRC DL Williams - BPA/399 NRC Site Inspector - 901A

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