ML20237F610

Provides Clarification to 870507 Response to Violation Noted in Insp Rept 50-312/87-06,per NRC 870526 Request. Corrective Actions:Each Crew Will Receive Extensive Plant Simulator Training & Sys Mods Implemented

ML20237F610
Person / Time
Site:	Rancho Seco
Issue date:	08/18/1987
From:	Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
GCA-87-365, NUDOCS 8709010358
Download: ML20237F610 (5)

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I SMUD g/ SACRAMENTO MUNICIPAL UTILITY DISTRICT accavto Cl P. O. Box 15830, S QQ1830, (916) 452 3211 AN ELECTRIC SYSTEM SERVR hiEVHEART OF CALIFORNIA 1931 f.UG 20 P 12: tt2 AUG 181987 GCA 87-365 J. B. Martin, Regional Administrator Region V Office of Nuclear Reactor Regulation l U. S. Nuclear Regulatory Commission

1450 Maria Lane, Suite 210 Walnut Creek, CA 94596 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 ADDITIONAL RESPONSE TO NOTICE OF VIOLATION (NRC INSPECTION REPORTS NO.

50-312/87-06)

Dear Mr. Martin:

By letter dated April 7,1987, the Nuclear Regulatory Commission issued a Notice of Violation concerning activities at the Rancho Seco Nuclear Generating Station. In accordance with 10 CFR 2.201, the District responded to the Notice of Violation by letter, dated May 7, 1987. The response letter l

acknowledged the violation cited and described the District's intended corrective actions for each specific item listed in the Notice of Violation.

On May 26, 1987, Mr. A.E. Chaffee of the Commission requested the District to i

provide further clarification of our May 7,1987, response regarding the l " programmatic weaknesses" in the District's QA program and the " preparation of l the operating staff to operate the facility after an extended outage and the need for providing all crews with an opportunity to exercise the new plant systems during the plant testing program."

This letter provides the District's response to the NRC's May 26, 1987 request.

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8709010358 870818 2 DR ADOCK 0500 ff-O/

RANCHO SLCO NUCLEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95638 9799;(209) 333-2935 I

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GCA 87-365 J.B. Martin ggg ,

If there are any questions concerning this report, please contact Mr. Ron H. Colombo at (916) 452-3211, extension 4236.

Sincerely, Y/  :. ,we G. Carl hndogni'ni Chief Executive Officer, Nuclear Attachment l 6 6

cc w/atch:

G. Kalman, NRC, Bethesda (2)

A. D'Angelo, NRC, Rancho Seco J. B. Martin (2)

A. E. Chaffee, Acting Chief, Reactor Projects Branch INP0 I&E

,. ATTACHMENT 1 DISTRICT RESPONSE TO NRC INSPECTION 87-06

.- NAIJLE OF VIOLATION NRC Reauest for Clarification-The forwarding letter for Inspection Report 50-312/87-06 requested that the District, in the response to the Notice of Violation, discuss measures being taken to correct programmatic weaknesses observed in the QA program related to corrective action measures and weaknesses in the 10 CFR 50.72 and 10 CFR 50.73 reporting systems. In addition,.the letter also expressed a concern regarding preparation of the operating staff to operate the facility after an extended outage and-the need for providing all crews with an opportunity to exercise the new plant systems during the plant testing program. In our review of your response to the Notice of Violation of Inspection Report 50-312/87-06, we are unable to clearly identify your response to the requests of the report' cover letter.

Please provide us with further clarification on this subject.

District Resoonse to Item 1 i

The District has established a management process development and review program to establish control of management processes. Major management processes are reviewed by top level management to identify and to correct programmatic weaknesses on a weekly basis.

This program establishes the Management System Control Center (MSCC) Group to review the mechanics of plant management processes. If programmatic weaknesses are identified, the process owner is required to develop a comprehensive action plan to reestablish programmatic control of the process. The MSCC group determines the effectiveness of the corrective actions through the review and trending of appropriate quantitative or qualitative procets indicators.

The deficiency identification, reporting, and correction processes at Rancho Seco will undergo a rigorous programmatic review by the MSCC group to identify and to correct programmatic weaknesses in these processes.

The specific process breakdowns identified in NRC Inspection Report No.

50-312/87-06 will be included as data points in the review and evaluation of these processes by the MSCC Group. The District anticipates that ini-tial reviews of these processes will be accomplished by August 31, 1987.

This NOV will be reviewed by the Independent Investigation / Review Group.

Based on that review an appropriate investigation will be performed. The response to this NOV will be updated as required based on the results of this review or investigation.

,. District Resoonse to Item _2' In response to your expressed concern regarding preparation of the operating staff to operate the Rancho Seco plant after the current outage the following information is provided:

• Each crew will receive extensive plant simulator training prior to plant restart (simulator training will include familiarization with the newly installed EFIC system).

• System modifications implemented during the restart program have been identified. During the scheduling of Functional Testing of these .:

systems, the operating crews will be adjusted to ensure the involvement of as many operating crews and individuals as possible.

• System tests involving the actual loss of a system or component will .

be run more than once if practical to provide an even greater opportunity for operator involvement and training. An example of these tests include Loss of ICS Test, Loss of NNI Test, and Remote Shutdown Test.

• The scheduling of each test will be carefully coordinated with the ,

responsible system engineer to ensure that the tests are held in a time frame that will allow maximum operator participation.

In view of the ongoing operator systems training being held at Rancho Seco, simulator training, and the timely adjustment of system testing and operator schedules, the District has taken or is planning actions to alleviate the concerns of the NRC with regard to operator performance following this shutdown.

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