ML20129F078

Forwards Further Evaluation of Conformance to IE Bulletin 80-06 Re ESF Reset Control & Deletion of SER License Condition 6,per Util .License Condition 6 Closed & Will Be Documented in Next Sser

ML20129F078
Person / Time
Site:	Perry
Issue date:	07/08/1985
From:	Youngblood B Office of Nuclear Reactor Regulation
To:	Edelman M CLEVELAND ELECTRIC ILLUMINATING CO.
References
IEB-80-06, IEB-80-6, NUDOCS 8507170209
Download: ML20129F078 (5)

Text

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, 2 Docket Nos.: 50-440 and 50-441 JUL 0 61985 Mr. Murray R. Edelman, Vice President Nuclear Operations Group The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101

Subject:

Deletion of SER License Condition (6), IE Bulletin 80-06 Engineered Safety Features Reset Control -- Perry Nuclear Power Plant (Units 1 and 2)

Enclosed is the staff's further evaluation of Perry's conformance to IE Bulletin 80-06 which we propose to incorporate in the next Perry SER supplement. Based on its review of the information provided by your letter dated May 29, 1985 concerning IE Bulletin 80-06, the staff considers the matter resolved. Therefore, License Condition (6), is considered to be closed and will be documented as such in the next SER supplement.

Sincerely, B. J. Youngblood, Chief Licensing Branch No. 1

. Division of Licensing

Enclosure:

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r JUL 0 t, bo5 Mr. Murray R. Edelman Perry Nuclear Power Plant The Cleveland Electric Units 1 and 2 Illuminating Company cc:

Jay Silberg, Esq. Mr. Larry 0. Beck Shaw, Pittman, & Trowbridge The Cleveland Electric 1800 M Street, N. W. Illuminating Company Washington, D. C. 20006 P. O. Box 97 E-210 Perry, Ohio 44081 Donald H. Hauser, Esq.

The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 Resident Inspector's Office U. S. Nuclear Regulatory Commission

. Parmly at Center Road Perry, Ohio 44081 Regional Administrator, Region III U. S. Nuclear Regulatory Comission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Donald T. Ezzone, Esq.

Assistant Prosecuting Attorney 105 Main Street Lake County Administration Center Painesville, Ohio 44077 Ms. Sue Hiatt OCRE Interim Representative 8275 Munson Mentor, Ohio 44060 Terry J. Lodge, Esq.

618 N. Michigan Street Suite 105 Toledo, Ohio 43624 John G. Cardinal, Esq.

Prosecuting Attorney Ashtabula County Courthouse i Jefferson, Ohio 44047

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. Enclosure 7.3.2.5 IE Bulletin 80-06, " Engineered Safety Features Reset Control" (LRG-II Generic Issue 4-ICSB)

The staff asked the applicant to review schematic level drawings for all systems serving safety-related functions to determine whether or not, upon reset of an engineered safety features actuation signal (ESFAS), the safety-related equipment remains in its emergency mode and to propose corrective action for those equipment items which do not. Additionally, the applicant was asked to verify by testing, that all equipment remains in the emergency mode upon removal of actuating signal and/or manual resetting of the various isolating or actuating signals.

In reviewing the Nuclear Steam Supply System (NSSS), the applicant identified two possible problem areas as follows:

(1) RCIC/RHR steam supply valves E51-F063 and F064 change state with reset as fo' lows: Valve E51-F063 will automatically reopen when the Division II RCIC steam isolation signal is reset, if the valve's' control switch is left in the open position. Valve E51-F064 will automatically reopen when the Division I isolation signal is reset, if the valve control switch is left in the open position.

(2) Valves E12-F060A, B and E12-F075A, B (RHR sample line valves) and B33-F019 and B33-F020 (reactor water sample valves) will reopen upon resetting from an isolation signal if they were open originally.

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The applicant agreed to revise the design of these valve control circuits to require operator action to reopen the valve after the appropriate reset button is pushed.

In reviewing the Balance of Plant (B0P) systems, the applicant identified four systems that were found to have conditions in which equipment did not remain in the emergency mode when the isolation actuation signals were reset. The applicant agreed to revise the design to alleviate the B0P concerns identified in this review.

Upon completion of these design changes, the applicant was required as a con-finnatory item to formally submit them for staff review and, in addition, pro-vide verification that the changes would be implemented prior to plant opera-tion. Furthermore, asa ' license condition, the applicant was required to comit to and/or perfonn preoperational tests to demonstrate that all equipment remains in its emergency mode upon removal of the actuating signal and/or re-setting of the various isolating or actuation signals.

By letter dated May 29, 1985, the applicant submitted information that included the a'pplicable drawings regarding the required design changes noted above. In addition, the applicant committed to perfonn preoperational testing that will demonstrate that all safety-related equipment will remain in its emergency mode upon removal of the actuating signal and/or resetting of the various actuation signals. Furthermore, the applicant stated that this testing would be satisfactorily completed prior to fuel load.

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Upon reviewing the above infonnation and the commitments made by the applicant, the staff concluded that the confirmatory item relating to IE Bulletin 80-06 (engineered safety features reset control) is resolved and in addition, that the license condition relating to IE Bulletin 80-06 (engineered safety features reset control) can be deleted.

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