05000369/LER-1981-084, Forwards LER 81-084/01T-0.Detailed Event Analysis Encl

Forwards LER 81-084/01T-0.Detailed Event Analysis Encl

ML20009C315
Person / Time
Site:	McGuire
Issue date:	06/09/1981
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20009C316	List: 05000369/LER-1981-084, Forwards LER 81-084/01T-0.Detailed Event Analysis Encl 05000369/LER-1981-084-01, /01T-0:on 810526,during Mode 5 Initial Fuel Loading & Check Valve Testing,Soft Seats on Containment Isolation Valves Were Damaged.Caused by Reverse Pressurization.Damaged Seat Disc Assembly Will Be Replaced
References
NUDOCS 8107200456
Download: ML20009C315 (2)

LER-1981-084, Forwards LER 81-084/01T-0.Detailed Event Analysis Encl

Event date:
Report date:
3691981084R00 - NRC Website

text

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June 9, 1981 373..o.3 Mr. James P. O'Reilly, Dhector

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U.S. Nuclear Regulatory Commission 4

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Region II

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3 101 Marietta Street, Suite 3100 JUL 171981* 1 Atlanta, Georgia 30303

,A Re: McGuire Nuclear Station Unit 1 u.s. e' d Docket No. 50-369 D.

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Dear Mr. O'Reilly:

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Please find attached Reportable Occurrence Report R0-369/81-84. This report

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concerns damage of several safety related containment isolation valves. This incident was considered to be of no significance with respect to the health and safety of the public.

Very truly yours, M

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William O. Parker, Jr.

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Director Mr. Bill Lavallee Office of Management & Program Analysis Nuclear Safety Analysis Center U.S. Nuclear Regulatory Commission P. O. Box 10412 Washington, D.C.

20555' Palo Alto, CA 94303 Ms. M. J. Graham Resident Inspector - NRC McGuire Nuclear Station m

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r McGUIRE NUCLEAR STATION INCIDENT REPORT Incident Identification No:

81-84 Report Date: June 9, 1981 Facility: McGuire Nuclear Station Unit 1

_ _...___ __ Identification of Deficiency:

Safety Related Containment Isolation Valves 1NI264, IN1266, 1NI267 Type C leakage deficiency.

Identification of Deficiency: During the secondary UHI accumulator check valve testing on valves 1NI248 and INI249, to verify Reactor Coolant System pressure boundary integrity, the containment isolation valves 1NI264, INI266 and INI267 were used as system isolation valves and experienced reverse pressurization of approximately.2485 PSIG. This reverse pressurization resulted in an equivalent seating torque in excess of design requirements for the containment isolation function for--valves 1NI264,1NI266 and 1NI267. As a result, the soft seats were damaged to a point such that subsequent Type C testing results exceeded containment isolation leakage criteria.

Analysis of Safety Implications: E this deficiency not been identified, con-tainment isolation leakage could have exceeded 10CFR50, Appendix J requirements under certain postulated accident conditions.

Corrective-Action: This problem will be resolved by replacing the damaged soft seat disc assembly with a new type soft seat disc aeaembly designed for these conditions.

This action is scheduled to be completed by June 22, 1981.

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