ML20138N780

Safety Evaluation Granting Util 840706 Relief Requests for Second 10-yr Inservice Insp Interval.Review of Requests for Relief from ASME Code Section XI Requirements Summarized in Encl Tables

ML20138N780
Person / Time
Site:	Point Beach
Issue date:	10/31/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20138N777	List: ML20138N776 ML20138N780
References
TAC-55500, TAC-55501, NUDOCS 8511060026
Download: ML20138N780 (3)

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/ o UNITED STATES E ~ ,), NUCLEAR REGULATORY COMMISSION 5 e j WASHINGTON, D. C. 20555 i k...+,/

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i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO REQUEST FOR RELIEF FROM INSERVICE INSPECTION REQUIREMENTS FOR SECOND 10-YEAR IN5ERVICE INSPECTION INTERVAL WISCON5IN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT UNIT 5 1 AND 2 DOCKET N05. 50-266 AND 50-301 Introduction By letters dated August 20, 1982 and January 19, 1983, the licensee, Wisconsin Electric Power Company, had submitted relief requests for the second 10-year in-service inspection interval. The staff had reviewed the licensee's requests for relief and issued its Safety Evaluation (SE) on March 29, 1984 The staff had granted relief from the examination requirements where we had determined the examination to be impractical to perform and we had denied relief in those cases where the necessary findings could not be made.

By letter dated July 6,1984, the licensee, submitted supplemental relief requests for the second 10-year inspection interval. In addition, the licensee also pro-vided an amplifying discussion concerning the implementation of previously granted relief from the requirements of 1977 Edition through Summer 1979 Addenda of Sec-tion XI of the ASME Code. A partial response to your July 6,1984 letter was issued on September 10, 1984. The remainder of your relief requests not evaluated in our September 10, 1984 SE are evaluated below.

Evaluation The requests for relief from certain regt.irements of Section XI which have been determined to be impractical to perform have been reviewed by the staff as summarized in the tables of Attachment 1.

Based on the review, the staff concludes that relief granted from the examina-tion requirements and alternate methods imposed through this document give reasonable assurance that the piping and component pressure boundary integrity will be maintained.

Conclusion The staff has concluded, based on the considerations discussed above, that relief granted from the examination and testing requirements and alternate methods imposed through this document give reasonable assurance of the piping and component pressure bound integrity, that granting relief where Code require-ments are impractical is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest considering the burden that could result if they were imposed upon the facility.

Date: October 31, 1985 Principal Contributors:

l B. Turovlin T. Colburn 8511060026 851031 PDR ADOCK 05000266

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5 TABLE 2 CLASS 2 COMPONENTS (UNITS 1 AND 2)

LICENSEE PROPOSED IWC-2600 IWC-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS C2.20 C-B Residual Nozzles Surface Surface Exam Granted Heat RHR-A-N1 and on entire Removal RHR-A-N2 Volumetric reinforcing Heat RHR-B-N1 plate weld Exchanger RHR-B-N2 every 10 years.

Visual (VT-2) exam for leakage each inspection period during system pressure test.

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, TABLE 1 CLASS 1 COMPONENTS (UNITS 1 AND 2)

LICENSEE PROPOSED IWB-2500-1 IWB-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS B3.160 B-D Regenerative Nozzle Inside Volumetric None Granted with Heat Exchanger Radius conditions RHE-N1-IRS see note.

RHE-N4-IRS RHE-N5-IRS-RHE-N8-IRS RHE-N9-IRS RHE-N12-IRS Note: Granted provided that a visual (VT-2) exam for leakage each inspection period during system pressure test. Visual (VT-1) during each inspection interval during hydrostatic test.

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