ML20196G537

Informs That Util Submittals Adequately Resolve Initial NRC Comments & Interim Approval of Second 10-yr Inservice Testing Program Given

ML20196G537
Person / Time
Site:	Rancho Seco
Issue date:	03/03/1988
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT
References
NUDOCS 8803090230
Download: ML20196G537 (3)

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Mr. G. Carl Andognini Chief Executive Officer, Nuclear Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald, California 95638-9799

SUBJECT:

INSERVICE TESTING PROGRAM, INTERIM APPROVAL i

By letter dated June 25, 1987, the Sacramento Municipal Utility District (SMUD), the licens2e, submitted the Inservice Testing (IST) Program Plaa for the second ten-year IST interval.

In a second letter on this subject, dated November 10, 1987, SMUD provided rationale why interim approval for the second-ten-year program should be given while the proposed program is being evaluated by the NRC staff. The staff responded to the SMUD letters or, December 2,1987 and outlined the steps necessary to obtain interim approval of the second ten-year program.

Interim NRC approval was to be predicated on resolution of comments generated following the initial staff review of the propored program.

The staff coments were discussed with SMUD during a working nieeting' at Rancho Seco on January 6 and 7, 1988. Based on this meeting, SMUD submitf.ed revisions to the proposed program by letters dated January 28 and February 5, 1988.

The staff finds that these submittals adequately resolve the initial staff comments and interim approval of the second ten-year IST program is brMiry given.

Yi;e IST program is required by 10 CFR 50.55a to comply with the ASME Boiler and Pressure Vessel Code,Section XI,1980 Edition through the Winter 1981 l

Addenda.

Pursuant to 10 CFR 50.55a(g)(5), the licensee requested relief from certain ASME Code testing requirements for specific pumps and valves where the Code requirements are impractical within the limits of design and plant operational requirements. The licensee's request for relief includes an explanation and justification for the relief and a proposal for alternative tcst procedures.

The IST program provides for periodic inservice testing of pumps and valves in accordance with the Code requirements The staff has verified that where relief from the code testing requirements was requested, the licensee demonstrated that it is impractical to perirm the test, l

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Mr. G. Carl Andognini Rancho Seco Nuclear Generating Chief Executive Officer, Nuclear Station Sacramento Municipal Utility District 14440 Twin Cities Road Herald, California 95638-9799 cc:

Mr. David S. Kaplan, Secretary Mr. John Bartus and General Counsel Ms. JoAnne Scott

-Sacramento Municipal Utility Federal Energy Regulatory Commission District 825 North Capitol Street, N. E.

6201 S Street Washington, D.C.

20426 P. O. Box 15830 Sacramento, California 95813 Mr. Barclay S. Lew Pacific Gas and Electric Company Thomas A. Baxter, Esq.

77 Beale Street (333/A613)

Shaw, Pittman, Potts & Trowbridge San Francisco, CA 94106 2300 N Street, N.W.

Washington, D.C.

20037 Mr.

,ven Crunk Manager, Nuclear Licensing Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Ferald, California 95638-9799 Mr. Robert B. Borsum, Licensing Representativc Babcock & Wilcox Nuclear Power Division 1700 Rockville Pike - Suite 525 Rockville, Maryland 20852 Resident Inspector / Rancho Seco c/o V. S. N. R. C.

14440 Twin Cities Road Herald, Califc.rnia 95638 Regional Administrator, Region V U.S. Nuclear Regulatory Conmission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Jack McGurk, Acting Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, Catiforr.ia 95814 Sacramento County Board of Supervisors 700 H Street, Suite 2450 Sacramento, California 95814 Ms. Helen Hubbard P. O. Box 63 Sunol, California 94586

., Our preliminary evaluation has identified no inconsistencies and on this basis we have determined that an interim approval of the IST program is appropriate until the staff can fully complete its assessment. The interi.n approval is intendc:i to provide interim operating guidance for SMUD while the staff completes its review and nrepres the safety evaluation (SE).

Since this interim approval does not represent the results of the final program review, the final SE could contain relief request denials or identify components that should be added to the IST program. We expect to issue the final SE in the near future.

If you have any questions regarding this letter, please communicate with the NRC project manager assigned to your plant.

Sincerely, Original signed by Gary M. Holahan, Assistant Director for Regions III & V Reactors Division of Reactor Projects - III, IV, Y and Special Projects Offica of Nuclear Reactor Projects cc: See next page im ?NRilTION

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