ML19312E685

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Responds to NRC Re Deviation Noted in IE Insp Repts 50-460/80-04 & 50-513/80-04.Corrective Actions: Engineering Evaluations Determined That Use of Electrode Is Acceptable Based on ASME III Guidelines
ML19312E685
Person / Time
Site: Washington Public Power Supply System
Issue date: 05/15/1980
From: Renberger D
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To: Spencer G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML19312E684 List:
References
GO1-80-151, NUDOCS 8006090404
Download: ML19312E685 (2)


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P W shington Public Power Supply System A JOINT OPERATING AGENCY P, O. Box 96 8 3000 Geo. WasusNaroM WAY RicHLa Mo. W AsHINGTON 99352 PHONE (509) 375 5000 May 15,1980 G01 151 Nuclear Regulatory Commission Region V Suite 202, Walnut Creek Plaza 1990 N. California Boulevard Walnut Creek, California 94596 Attention: Mr. G. S. Spencer, Chief Reactar Construction and Engineering Support Branch

Dear Mr. Spencer:

Subject:

WPPSS NUCLEAR PROJECTS NOS. 1/4 NRC INSPECTION - WNP-1/4 DATES OF INSPECTION - MARCH 1-31, 1980 DOCKET NOS. 50-460 AND 50-513 CONSTRUCTION PERMIT NOS. CPPR-134 AND 174

Reference:

Letter from G. S. Spencer to N. O. Strand, NRC Inspection at WNP-1/4 Site, dated April 15, 1980.

The referenced correspondence delineated the results of the March 1-31, 1980 inspection of activities authorized by NRC Construction Permits Nos. CPPR-134 and 174.

Further, the refer-enced correspondence identified certain activities which were not conducted in full compliance with PSAR requirements set forth in the Notice of Deviation enclosed as Appendix A.

This item of deviation has been categorized into a level as described in your correspondence to all NRC licensees dated December 31, 1974.

This letter is submitted in response to the referenced correspondence.

The srecific deviation, as identified, and the Supply System response is provided herewith as Appendix A.

Very truly yours, D. L. Renberger Assistant Director, Technology jds Attachment cc:

CR Bryant, BPA SB Barnes, UE&C Phil.

BD Redd, UE&C Phil.

J. Freeman, UE&C Phil.

AD Toth, NRC, WNP-1/4 Site 8006090YD4 s

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l APPENDIX A Nuclear Regulatory Commission Region V Suite 202, Walnut Creek Plaza 1990 N. California Boulevard 4

Walnut Creek, California 94596 Docket No. 50-460 Construction Permit No. CPPR-134 J.

j NOTICE OF DEVIATION Based on the results of an NRC inspection conducted during the period of March 1-31, 1980, it appears that one of your activities was not conducted in full conformance with your commitments to the Commission as indicated below:

Contrary to the licensee's commitment in paragraph 5.2.3.1 and Table 5.2-5 of the PSAR that weld material specification SFA-5.5 would govern the special E-7018 welding electrodes used for reactor coolant pressure boundary welds, welding electrodes qualified under specification SFA-5.1 rather than SFA-5.5 were used for welding the pipe-to-steam generator reactor coolant pressure boundary welds.

1 SUPPLY SYSTEM RESPONSE TO THE DEVIATION i

Engineering evaluations have determined that the use of this type of electrode is acceptable for pipe to component welds as long as ASME III requirements are met.

The Engineering evaluation was completed April 22, 1980.

1 A Deviation (No. 5.2-1 (WP)) has been filed to the Preliminary Safety Analysis Report permitting the use of welding electrodes qualified under specification SFA-5.1.

The deviation was approved May 9,1980.

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