ML17277A656

Forwards Proposed Snubber Tech Spec for Review as Followup to 830314 & 0624 Telcons.Changes Will Not Lessen Assurance of Structural Integrity & Functionality of safety-related Sys.Fuel Load Scheduled for Sept 1983

ML17277A656
Person / Time
Site:	Columbia
Issue date:	07/08/1983
From:	Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML17277A657	List: ML17277A656 ML17277A659 ML17277A661
References
GO2-83-611, NUDOCS 8307190213
Download: ML17277A656 (6)

Text

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ACCESSIONNBRt8307190213 DOC.DATE 83/07/08 NOTARIZED: NP DOCKET FACIL,:50-397 WPPSS Nuclear Pr alecto Unit 2r Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION, BOUCHEY.G.D. Washington Public Power Sunnily Svstem RECIP.NAME RECIPIENT AFFILIATION J 'CHWENCER n A Licensing Branch 2 I wl

SUBJECT:

Forwards orooosed snubber Tech Soec for review as followup to 830314 8 0624telrqns.Changes will, notlessen assurance of structural intearity 8, functionalitv of safetv related svs.Fuel load scheduled for Scot 1983.

DISTRIBU]'ION CODE: B091S COPIES RECEIVED:LTR

,,;f,;l,g i I ENCL ~ SIZE; TITLE: Licensina Submittal: PSAR/FSAR Amdts 8 Related Correspondence NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME I TTR ENCL ID CODE/NAME LTTR ENCL NRR/DL/ADL 1 0 NRR LB2 BC 1 0 NRR LB2 LA 1 0 AULUCKnR ~ 01 1 1 INTERNAL: ELD/HDS2 1 . 0 IE FILE 1

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IE/DEPER/EPB 36 3 3 IE/DEPER/IRB 35 1 1 IE/DEQA/QAB 21 1 1 NRR/DE/AEAB 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EHEB 1 1 NRR/DE/EQB 13 2 2 NRR/DE/GB 28 2 2 NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB 24 1 1 NRR/DE/SGEB 25 1 1 NRR/DHFS/LQB 32

'4 NRR/DHFS/HFEB40 1 1 1 1 NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 1 0 NRR/DSI/AEB 26 1 1 NRR/DS I/ASB 1 1 NRR/DSI/CP8 10 1 1 NRR/DS I/CSB 09 1 1 NRR/DSI/ICSB 16 1 1 NRR/DSI/METB 12 1 1 NRR/DSI/PSB 19 1 1 B 22 1 1 NRR/DSI/RSB 23 1 1 G 1 RGN5 3 3 RM/DDAMI /MI8 1 0 EXTERNAL: ACRS 41 6 6 BNL(AMDTS ONLY) 1 1 DMB/DSS (AMDTS) 1 . 1 FEMA REP DI V 39 1 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 53 ENCL 46 f

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Washington Public Power Supply System P.O. Box 968 3000George Washington Way Richland, Washington 99352 t509) 372-5000 Docket No. 50-397 Responds to: N/A July 8, 1983 Response required by: N/A G02-83-611 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 PROPOSED SNUBBER TECHNICAL SPECIFICATION The proposed Snubber Technical Specification for WNP-2 is enclosed for your review as a follow-on to the telephone, conversations between Horace Shaw and Larry Prill of the Supply System on March 14, and June 24, 1983.

A summary of the differences in this proposed specification in com-parison with the standard technical specification is as follows:

1. The first visual examination scheduled to occur at 4 to 10 months following power operation will be done as part of the WNP-2 Pre-seryice Component Support Inspection Program. This post-shakedown inspection is to be performed following plant operation at power and after at least three full thermal cycles of plant systems which meets the intent of the standard technical specification.

A copy of the Preservice Component Support Inspection Program is included as Attachment A.

2. Paragraph 4.7.4.d, entitled "Functional Testing," has been ex-panded to include three sample optional plans, all of which pro-vide 95% probability that 90 to 100% of the safety-related plant snubbers are operational. The additional sample plan options are identical to those currently in the staff approved McGuire Unit Technical Specifications and, thus, should provide no 1

difficulty in receiving staff approval.

830708 8307190213 05000397 PDR *DOCK PDR A

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Mr. A. Schwencer Page Two July 8, 1983 PROl'OSED SNUBBER TECHNICAL SPECIFICATION

3. Paragraph 4.7.4.e has the added specification that functional testing of snubbers be performed at greater than or equal to 10% snubber rated load. Additionally, the clarification is made in this paragraph that an increase in snubber drag force counts as a failed snubber only when the drag force exceeds the maximum specified drag force for the snubber.

It is the Supply System's position that these changes will not lessen the assurance of structural integrity and functionality of NNP-2 safety-related systems but will reduce the impact of this technical specification on WNP-2.

Fuel load is scheduled for September 1983 and your expeditious review of the enclosed is appreciated. Please call Messrs. P. Powell at (509) 377-2501 extension 2909 L. Pri ll at (509) 377-2522 extension 4523 with your questions or comments.

G.~ D.~ ouchey (370)

Manager, Nuclear Safety and Regulatory Programs LRP/arg Attachments: 1. Proposed Snubber Technical Specification for l<NP-2

2. Preservi ce Component Support Inspection Program cc: Mr. R. Auluck - NRC Mr. U. S. Chin - BPA Mr. H. Shaw - NRC Mr. A. Toth - NRC Site (917())

Mr. D. Hoffman - NRC

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