ML19318B136

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Responds to NRC Re Violation Noted in IE Insp Rept 50-312/80-10.Corrective Actions:Held Training Session W/Crane Operators & Reviewed & Updated Maint Procedures
ML19318B136
Person / Time
Site: Rancho Seco
Issue date: 06/02/1980
From: Walbridge W
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML19318B133 List:
References
NUDOCS 8006250054
Download: ML19318B136 (2)


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SACRAMENTO MUNICIPAL UTILITY DISTRICT C) 6201 S Street, Box 15830, Sacramento, Catitornia 95813; (916) 452-3211 June 2, 1980

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R. II. Engelken, Director Region V Office of Inspection & Enfc-cement

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U. S. Nuclear Regulatory Conmission ci 1990 North California Boulevard

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Walnut Creek Plaza, Suite 202 egp !

f Walnut Creek, California 94396 Re:

NRC Inspection 50-312/80-10 Docket No. 50-312 License No. DPR-54 Rancho Seco Nuclear Generating Station Gentlemen:

In reply to your inspection conducted by Mr.11. Canter March 3-31, 1980, we offer the following corrective actions to assure full compliance with NRC requirements.

Appendix A of your letter notes the following infraction:

" Technical Specification 6.5.1.6.a reads, in part, 'The Plant Review Committee (PRC) shall be responsible for review of 1) all procedures required by Specification 6.8 and changes thereto,...'

" Contrary to the above requirements, the procedures required for controlling certain uses of the polar crane had not been reviewed by the PRC prior to February 19, 1980, when the procedures were used to move a large 3,000 pound calibration block over the fuel transfer canal with the reactor vessel head removed and irradiated fuel in the reactor building."

SMUD REPLY The dropping of the ARIS (Automated Reactor Inspection Service) calibration block was reported to your office via LER 80-14.

It revealed a procedural inadequacy in the area of a specific procedure for the operations involved. As stated in the LER, the immediate corrective action included holding training sessions for all individuals associated with directing or operating the cranes in the Reactor Building. The training sessions specifi-cally addressed the requirements of Technical Specifications Section 3.11.

Additionally, during the exit interview held March 31, 1980, the District agreed to assure that an appropriate procedure will be written and approved prior to the next time an ARIS inspection is scheduled.

The District has retained an engineer from the NSSS vendor to assist in the review, update, 8 0 06250 cgi l}{-

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R.-H. Engelken

- Page 2 June 2, 1980-and writing of new maintenance' procedures to assure that procedural inadequacies.

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are-minimized in the future. Those procedures' involving Technical Specification

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Section 3.11 will ba reviewed by the Plant Review Committee and approved by the Plant Superintendent. All requirements as stated in your letter and the Techni-cal-Specifications will be~followed.

Sincerely,.

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War.'.C. Walbridge~-

I General Manager JJ11:Hil:jin i

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