ML17277A871

Forwards Four Oversize Drawings,Closing Out NUREG-0892,SER Outstanding Issue 29 Re Vacuum Breaker Valves.Valve Response Meets Containment Design Bases for Response Time & Flow Capacity.Aperture Cards Are Available in PDR

ML17277A871
Person / Time
Site:	Columbia
Issue date:	09/28/1983
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML17277A872	List: ML17277A871 ML17277A873 ML17277A874 ML17277A875 ML17277A877
References
RTR-NUREG-0892, RTR-NUREG-892 GO2-83-872, NUDOCS 8310110276
Download: ML17277A871 (6)

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REGULATORY NFORMATION DISTRIBUTION SY M (RIDS)

ACCESSION NBR;8310110276 DOC ~ DATE'5/09/28 NOTARIZED; NO 'OCKKT PACIL:30-397 NPP00 Nuclear Project, Unit 2o washington Public Powe 03000307 AUTH",NAME AUTHOR AFFILIATION SORENSENiG AC, Nashington Public Power Supply System RECIP.NAME RECIPIENT AFFIl,IATION SCHAENCERiA, Licensing Branch 2 SUBJECT! For wards four oversize drawings~closing out NUREG-0892'USER Outstanding Issue 29 re vacuum breaker valves'a'Ive response.

meets containment design- bases for response time 8 flow capacity. Aperture cards are available in PDR ~

DISTRIBUTION CODE B001S COPIES RECEIVED:LTR .g, ENCL SIZE!. cP-~.

TITLE: Licensing Submittall PSAR/FSAR Amdts 8, Related Correspondence' NQTESe RECIPIENT COPIES RKC IPIENT COPIES ID CODE/NAME, LTTR ENCI. IO 'CODE/NAME LTTA ENCL NR"/DL/ADL 1 0 NRR LB2 BC 1 NRR LB2 I.A 1 0 AULUCKgR 01 1 INTERNALe ELD/HDS2 1 0 IK FILE 1 1 IE/DEPER/EPB 36 3 IK/OKPER/IRB 35 1 IK/DEQA/QAB 21 1 NRR/DE/AEAB 1 0 NRR/DE/CEB 1 NRR/DF/EHEB 1 1 NRR/DE/EQB 13 2', 2 NRR/DE/GB 28 2 2 NRA/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 NRR/DE/SAB 24 ] 1 NRR/DE/SGEB 25 .1 1 NRA/DHFS/HFEB40 1 1 NRR/DHFS/LQB 32 1 NRR/DHFS/PSRB 1 1 NRR/DI./SSPB 1 0 NRR/DSI/AEB 26 1 1 NRR/DS I/ASB 1 1 NRR/DS I/CPB 10 ei 1 NRR/DSI/CSB 09 1 NRR/DSI/ICSB 16 1 1 NRR/DS I/METB 12 1 1 NRR/DS I/PSB 19 1 NRR/OS I/RAB 22 1 NRR/DSI'/RSB 23 1 1 REG FI 04 1 1 RGN5 R n /MIB 0 EXTERNALe ACRS 41 6 6 BNL(AMDTS ONLY) 1 DM8/DSS (AMDTS) 1 1 FEMA REP DIV 39 1 1 LPOR 03 1 NRC POR 02, 1 1 NSIC 05 1 NTIS 1 1 o

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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 September 28, 1983 G02-83-872 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

Dear Mr. Schwencer:

Subject:

NUCLEAR PROJECT NO. 2 VACUUM BREAKER VALVES, NUREG-0892, CLOSURE OF SAFETY EVALUATION REPORT, OUTSTANDING ISSUE NO. 29 USNRC Letter No. 29488, F. Eltawila/J. Kudrick to W. R. Butler, "Meeting Summary Vacuum Breaker Performance, Discussion with Representatives of Susquehanna Steam Electric Station (SSES}, Limerick

.Generating Station (LGS}, Shoreham Nuclear Power Station (SNPS} and Washington Public Power Supply System (WNP,-2)", dated June 20, 1983 On June 7. 1983, Continuum Dynamics Inc. (CDI} and the Supply System presented to members of the Containment System Branch, the results of our program to document design adequacy of the WNP-2 drywell-to-wetwell vacuum breaker valves for service under all containment transients. The presentation (as appended to the cited reference} reviewed the Supply System's program of analysis, redesign, remanufacturing, and full scale static and dynamic. testing of these valves. At the time of the presentation, CDI had not completed final calibration of the vacuum breaker valve dynamic models using the test. results obtained in May at Anderson Greenwood 8 Co.'s flow facility.

The vacuum breaker models as described in NEDE-.22178-P have now been fully calibrated and verified by CDI using the cited WNP.-2 valve unique flow test data. The critical. result.,'f this work is that the loading bases used to redesign the valve are, in all cases, fully bounding over the test calibrated dynamic model results. Additionally, the valve disc impact velocities and response times are well within design basis limits and remain as reported in our presentation of. June 7. In short, under worst case combined faulted loading conditions, the valve.'response is fully elastic, operable (i.e., limited valve component deflections), and meets all containment design bases for response time and flow capacity.

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A. Schwencer Page Two September 28, 1983 VACUUM BREAKER VALVES, NUREG-0892, CLOSURE OF SAFETY EVALUATION REPORT, OUTSTANDING ISSUE NO. 29 In suranary, stemming from a program of comprehensive analysis, redesign, and testing the Supply System concludes that the WNP-2 drywell-to-wetwell vacuum breaker valves now have fully documented design packages for service under all containment transient loads.

For your information, reduced size layout drawings of the final valve configuration are attached. The salient design enhancements were covered in our presentation of June 7.

With this submittal the Supply System considers Outstanding Issue No. 29 of the WNP-2 Safety Evaluation Report, NUREG-0892, to be closed.

If you have any further questions, please contact Mr. P. L. Powell, Manager, WNP-2 Licensing.

Very truly yours, G. C. Sorensen, Acting Manager Nuclear Safety and Regulatory Programs DMB/tmh Attachments: 1) Assembly Drawing No. 4-3825, Sheets 1 5 2

2) Auxiliary Equipment Drawing No. 4-3800, Sheets 1 8 2 cc: R Auluck - NRC WS Chin - BPA A Toth - NRC Site

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