ML20206G803

Forwards Safety Evaluation Granting Inservice Insp Program Relief Requests PRR-8 Re Surface & Volumetric Exam of RHR Sys HX Nozzles & PRR-9 Re Exam of 100% of Required Vol for nozzle-to-vessel Welds,Per Util 860415 & 1212 Ltrs

ML20206G803
Person / Time
Site:	Pilgrim
Issue date:	03/26/1987
From:	Rajender Auluck Office of Nuclear Reactor Regulation
To:	Lydon J BOSTON EDISON CO.
Shared Package
ML20206G807	List: ML20206G803 ML20206G814
References
TAC-61370, NUDOCS 8704150159
Download: ML20206G803 (2)

Text

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/ o,, UNITED STATES 8" o NUCLEAR REGULATORY COMMISSION

$ r $ WASHINGTON, D. C. 20555

%...../ March 26, 1987 Docket No. 50-293 Mr. James M. Lydon Chief Operating Officer Boston Edison Company 800 Boylston Street Boston, Massachusetts 02199

SUBJECT:

REQUEST FOR RELIEF FROM CERTAIN INSERVICE INSPECTION (ISI)

REQUIREMENTS - SECOND TEN YEAR INTERVAL INSPECTIONS (TAC 61370)

Re: Pilgrim Nuclear Power Station On August 13, 1985, the NRC staff issued a Safety Evaluation (SE) evaluating Pilgrim Nuclear Power Station's ISI program and Requests for Relief from certain ISI requirements. In letters dated April 15 and December 12, 1986, the licensee provided additional information and clarification on its ISI Program and relief requests PRR-1, 3, 4, 6, 8, 9 and 10. The enclosed SE addresses only PRR-8 and PRR-9.

i Relief request PRR-8 pertains to the surface and volumetric examination of the four 16-inch diameter nozzles of the two residual heat removal system heat exchangers. Relief request PRR-9 pertains to the examination of 100%

of required volume for 21 nozzle-to-vessel welds located within the biological shield wall and to the relief from Item B3.100 of the Code for nozzle N18.

- The staff's review concludes that the required examination and testing is impractical to perfonn and the alternate methods of examination, discussed in the SE, provide the necessary added assurance of structural integrity of the nozzles. The Commission's regulations allow the granting of relief where the Code requirements are impractical and will not endanger life or property, or the comon defense and security and is otherwise in the public interest considering the burden that could result upon Boston Edison Company if the Code requirements were imposed upon the Pilgrim Nuclear Station. Accordingly, pursuant to 10 CFR 50.55a(g)(6)(1) of the Comission's regulations, Boston l

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8704150159 870326 I PDR ADOCK 05000293 G PDR

l Mr. James M. Lydon March 26, 1987 Edison Company is granted the relief requested in its requests PRR-8 and PRR-9.

This is relief from the examination and testing requirements for residual heat removal system heat exchangers welds, nozzle N1B and the nozzle-to-vessel welds discussed above. Please note that the enclosed SE states, for each of the PRR-8 and PRR-9 relief requests, that certain actions must be taken by you in the inservice inspections of the welds and nozzle. A copy of our SE is enclosed.

4 j Sincerely, j Original signed by j Rajender Auluck, Project Manager BWR Project Directorate #1 Division of BWR Licensing

Enclosure:

Safety Evaluation cc w/ enclosure:

See next page DISTRIBUTION oDocket File, RAuluck NRC PDR BWD1 PD j Local PDR OGC-BETH BWD1 Reading Edordan HDenton BGrimes RBernero JPartlow

ORAS NThompson CJamerson TBarnhart(4)

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