ML20151V540

Forwards Synopsis of Major Activities & Related Commitments Made During Phase I of Enhanced Operational Insp for Power Ascension.Sys Engineering Action Plans & Procedure Development Project Action Plan Encl

ML20151V540
Person / Time
Site:	Rancho Seco
Issue date:	04/18/1988
From:	Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20151V543	List: ML20151V540 ML20151V587 ML20151X287 ML20151X321
References
GCA-88-258, NUDOCS 8805030093
Download: ML20151V540 (3)

Text

af ,8 kSMUDSACRAMENTO MUNICIPAL UTILITY DISTRICT O P. O. Box 15830, Sacramento CA 90052-1830,(916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA APR 1 B 1938 GCA 88-258 id I 3 '

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U. S. Nuclear Regulatory Commission Attn: J. B. Martin, Regional Administrator Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596 Docket No. 50-312 Rancho Seco Nuclear Generating Station  !

License No. DPR-54 ,

ENHANCED OPERATIONAL INSPECTION FOR POWER ASCENSION PHASE I STATUS l

Dear Mr. Martin:

This letter provides a synopsis of the major activities and l related commitments made to the NRC during Phase I of the subject inspection, headed by Mr. Jesse Crews, Region V. These commitments responded to issues raised by the inspection team and in all cases either corrective actions were taken immediately or corrective action plans were initiated. For those commitments with corrective actions not fully implemented, a schedule / action plan is provided.

Rancho Seco and the NRC were in accord as to the objective of this inspection: to evaluate the operating staff and support l organizations to Operations. The District acknowledges the NRC l Teams findings and observations for enhancement. The District recognizen those which may be enhancements will provide added assurance for optimum plant safety during the restart evolution i and return to full power operation. l Please contact me if you have any questions. Members of your staff with questions requiring additional information or clarification may contact Mr. Steve Crunk at (209) 333-2935, extension 4913. '

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Sincerely, '

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'G Carl Andoggini zl$fnE l l

Chief Executive Officer, I g50ggo O 2 Attachments o cc with attachments:

G. Kalman, NRC, Rockville A. D'Angelo, NRC, Rancho Seco F. J. Miraglia, NRR, Rockville i g RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 332 2935 l TC-N

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l ATTACHMENT I I GCA 88-258  !

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l NRC Reactor Trip Breakers (RTB) Undervoltage l Observation: Device Malfunction and Attendant Trouble Shooting j and Root Cause Determination. j Rancho Seco Numerous sub-issues on the RTB's were Response: addressed during the inspection. The following is a synopsis of the items:

o Control Rod Drive (CRD) Breaker Action Plan, Rev. O, dated March 27, 1988 was developed by System Engineering to establish a course of action to be taken to determine the root cause of the failure and ensure all RTBs in service (two AC and four DC) are procured qualified CRD circuit breakers. Revision 1

• to the CRD Action Plan was reviewed and approved by management on March 30, 1988 (attached).

o An Action Plan, Evaluation of Commercial Grade Itelas in the Reactor Protection Systen (RPS), being developed by Nuclear Engineering will give priority attention to evaluate the impact of past procurement practices on the RPS. The Action Plan addresses the eight relay panels previously reviewed as part of the Procurement Engineering Assessment Plan submitted to NRC by Letter GCA 88-065, dated February 3, 1988, as well as equipment associated with the generation of RPS input signals, and the equipment that carries out the reactor trip function.

The proposed evaluation will assure that those equipment items included do not make use of commercially procured parts which cannot be dediccted, or otherwise shown to be unimportant to the RPS safety function. If any parts are discovered which were commercially procured and cannot be shown to be acceptable, they will be identified and dispositioned using the normal PDQ process.

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, ATTACHMENT I (continued) , .

o EM 175, CRD Breaker Preventive Maintenance, was revised to incorporate new inspection criteria established during the General Electric (GE)/ Babcock & Wilcox (B&W) visit to" the. site March 26 through 28, 1988. It should be noted that all industry problems known to SMUD relating to the AK-2-25 breaker have been incorporated into EM 175 and reviewed by B&W and GE, with comments incorporated.

o A 10 CFR 21 Report (88-02) was signed by the CEO on April 7, 1988 and a copy provided to the NRC on that same day. The foundation for this report is a memorandum signed by J. M.

Austin of GE and H. H. Stevens of B&W, depicting the root cause based upon their thorough inspection of the breaker /UVD.

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