U-600365, Forwards Clinton Power Station Inservice Insp Pump & Valve Testing Program, Per SER (NUREG-0853) Confirmatory Issue 68.Program Describes How Requirements of ASME Boiler & Pressure Vessel Code,Section XI Will Be Met

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Forwards Clinton Power Station Inservice Insp Pump & Valve Testing Program, Per SER (NUREG-0853) Confirmatory Issue 68.Program Describes How Requirements of ASME Boiler & Pressure Vessel Code,Section XI Will Be Met
ML20138Q978
Person / Time
Site: Clinton Constellation icon.png
Issue date: 12/26/1985
From: Spangenberg F
ILLINOIS POWER CO.
To: Butler W
Office of Nuclear Reactor Regulation
Shared Package
ML20138Q979 List:
References
RTR-NUREG-0853, RTR-NUREG-853 U-600365, NUDOCS 8512300162
Download: ML20138Q978 (2)


Text

U-600365 L30-85(12-26)-L 1A.120 ILLIN0/8 POWER 00MPANY CLINTON POWER STATION. P.o. BOX 678. CLINTON. ILLINOIS 61727 Docket No. 50-461 Director of Nuc1 car Reactor Regulation Attention: Dr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Clinton Power Station Inservice Inspection - Pump and Valve Testing Program (Confirmatory Issue #68)

Dear Dr. Butler:

Per the request of Mr. B. L. Siegel (NRC Clinton Licensing Project Manager) of your Staff, the attached material, entitled "Clinton Power Station Inservice Pump and Valve Testing Program," dated November 1985, is provided for the Staff's review. This program describes how safety-related pumps and valves will be tested to satisfy the requirements of the ASME Boiler and Pressure Vessel Code Section XI,

" Rules for the Inservice Inspection of Nuclear Power Plant Components,"

1980 Edition, Winter 1981 Addenda. The requirements of this edition and addenda will be used during the first ten-year inspection period or until a later edition is selected to be used. Later editions must be endorsed in 10CFR50.55a or approved by the appropriate enforcement and regulatory agencies prior to their use.

The requirements of the pump testing program shall be applied to Class 1, 2 and 3 pumps which are required to perform a specific function in shutting down the reactor or in mitigating the consequences of an accident and are provided with an emergency power source. The pumps which are included in this program are listed in Table 1. Provided in Appendix A to the attached program are four (4) specific relief requests to these pump testing requirements.

The requirements of the valve testing program apply to Class 1, 2, and 3 valves (and their actuating and position indicating systems) which are required to perform a specific function in shutting down the reactor or in mitigating the consequences of an accident. Certain categories of valves which are exempt from these requirements are identified in Section III.A of the attached program. The valves which are to be tested under this program are listed in Appendix B.

In addition, Appendix B provides 54 specific relief requests to these valve testing requirements (Relief Requests 002, 006, 007, 009, 012-016, 018, 020, 022-026, 029, 031, 034 and 039 have been deleted as they are no longer applicable; for a total of 34 actual relief requests on valve testing). Es (uAW) 8512300162 851 -

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U- 600365 L30- 85 ( 12-26)-L 1A.120

.lllinois Power Company considers the attached program to be adequate to' resolve any remaining NRC concerns relative to Safety Evaluation Report (NUREG-0853) Confirmatory Issue #68 regarding inservice testing of ASME Code pumps and valves. Please contact me if <

the Staff has any questions on this program.

Sincerely yours, F. A nber Manager - Licensi g and Safety TLR/ckc Attachment cc: B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety t

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