ML20128G756

Forwards Safety Evaluation Supporting Exemption from Inservice Insp Requirements for Reactor Coolant Pumps. Exemption Based on 850305 Info

ML20128G756
Person / Time
Site:	Rancho Seco
Issue date:	06/17/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT
Shared Package
ML20128G757	List: ML20128G756 ML20128G764
References
TAC-57126, NUDOCS 8507090311
Download: ML20128G756 (2)

Text

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JUN 171985 Docket No. 50-312 DISTRIBUTION e Decitet Mie ,

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'NRC PDR ACRS-10 L PDR RIngram Mr. Ronald J. Rodriguez ORB #4 Rdg SMiner ,

Gray File Assistant General Manager, Nuclear HThompson Sacramento Municipal Utility District OELD EBrach 6201 S Street EJordan H0rnstein P. O. Box 15830 BGrimes Sacramento, California 95813

Dear Mr. Rodriguez:

l

SUBJECT:

RANCHO SEC0 NUCLEAR GENERATING STATION - REQUEST FOR RELIEF FROM INSERVICE INSPECTION REQUIREMENTS FOR REACTOR COOLANT PUMPS By letter dated January 28, 1983, we sent you a Safety Evaluation with an i attached Technical Evaluation Report in which requests for relief from certain examination and testing requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (the Code) were evaluated. The recuests were either denied or granted. One of the requests that was deniec was relief from examination of the reactor coolant pumps. By letter dated March 5,1985, you transmitted a revision to your original request. We have completed our review of the revised relief request and have concluded that your proposed alternative examinations of the reactor coolant pumps will provide the necessary assurance of the pumps' structural l integrity.

We have detennined that the Code requirements are impractical and that the relief request is authorized by law and will not endanger life or property or the coninon defense and security and is otherwise in the public interest giving due consideration to the burden that could result if the requirements were imposed on your facility. Therefore, pursuant to 10 CFR 50.55(a)(g)(6)(1), we hereby grant the requested relief from Section XI of the Code requirements for the Reactor Coolant Pump casing welds and internal surfaces.

Our Safety Evaluation is enclosed for your information.

Sincerely, e cw.u,u.m .-~ a t J w n . S m :,'

John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing

Enclosure:

Safety Evaluation cc w/ enclosure:

See next page

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6/ 6 /85 6/6 785 6// /B5 6/f /85 8507090311 850617 PDR ADOCK 05000312 O pon

4 b 4 Mr. R. J. Rodriguez Rancho Seco Nuclear Generating Station Sacramento Municipal Utility District cc:

Mr. David S. Kaplan. Secretary Sacramento County ,

and General Counsel Board of Supervisors Sacramento Municipal Utility 827 7th Street, Room 424 District Sacramento, California 95814 6201 S Street P. O. Box 15830 Ms. Helen Hublerd Sacramento, California 95813 P. O. Box 63 Sunol, California 94586 Thomas Baxter, Esq.

Shaw, Pittman, Potts & Trowbridge 1800 M Street, N.W.

Washington, D.C. 20036

' ~

'Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division '

Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector / Rancho Seco c/o U. S. N. R. C. '

14410 Twin Cities Road Herald, California 95638 Mr. John B. Martin, Regional Administrator U.S. Nuclear Regulatory Commission, */

Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Director Energy Facilities Siting Division Energy Resources Conservation &

Development Comission 1516 - 9th Street  !

Sacramento, California 95814 Mr. Joseph 0. Ward, Chief Radiological Health Branch State Department of Health Services 714 P Street Office Building #8 Sacramento, California 95814 Mr. Joseph Findaro California State Office 444 North Capitol Street, N.W., Suite 305 Washington, D.C. 20003

/ UNITED STATES

• [ } l ,., \' g NUCLEAR REGULATORY COMMISSION  :

5. p W ASHINGTON, D. C. 205b5

...../

ENCLOSURE SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUESTS FOR RELIEF FROM ASME CODE SECTION XI EXAMINATION REQUIREMENTS FOR REACTOR COOLANT PUMP CASING WELDS AND INTERNAL SURFACES  ;

SACRAMENTO MUNICIPAL UTILITY DISTRICT .

RANCHO SECO NUCLEAR GENERATING STATION l DOCKET NO. 50-312

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1. BACKGROUND Technical Specification 4.2.2 for the Rancho Seco Nuclear Generating

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Station states that inservice examination of ASME Code Class 1, 2, and  !

3 components shall be performed in accordance with the requirements of i Section XI of the ASME Boiler and Pressure Vessel Code and applicable  !

adoenda as requ red by 10 CFR 50.55a(g) except where specific written L relief has been granted by the Commission. By letter dated January 28 1983, the NRC transmitted to the Sacramento Municipal Utility District !

(SMt0) a Safety Evaluation with an attached Technical Evaluation Report in which requests for relief from certain examination and testing require- , [

ments of Section XI for Rancho Seco were evaluated and the requests either  ;

granted or denied. The granting or denying of the requests was based on j information submitted to the NRC by SMUD by letters dated July 18 and  ;

December 10, 1979, and April 19, 1982, in the inservice inspection program, i revisions, or additional information related to requests for relief from I the Code requirements for Ranch Seco.

i By letter dated March 5, 1985, SMUD transmitted to the NRC a revision to [

the request for relief from examination of the reactor coolant pumps at I Rancho Seco. This request had been denied in the Safety Evaluation / Technical

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