ML20081D245
| ML20081D245 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/07/1983 |
| From: | Manno S NIAGARA MOHAWK POWER CORP. |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| RTR-NUREG-0588, RTR-NUREG-588 10CFR-050.55E, 10CFR-50.55E, 7524, NUDOCS 8311010086 | |
| Download: ML20081D245 (2) | |
Text
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M V NIAGARA RUMOHAWK NBAGARA 000 HAWK POWER CORPORATION /300 ERIE BOULEVARD WEST, SYRACUSE, N.Y.13202/ TELEPHONE (315) 474-1511 SAMUEL F. MANNO VICE PRESIDENT NUCLEAR CONSTRUCTION October 7, 1983 (7524)
Mr. R. W. Starostecki, Director U. S. Nuclear Regulatory Commission Region I Division of Project and Resident Programs 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Starostecki:
RE: Nine Mile Point - Unit 2 Docket No. 50-410 Enclosed is a final report in accordance with 10CFR50.55(e) for the problem concerning failure of safety relief valve actuator during environmental qualification testing. 'Ihis condition was reported via tel-con to Mr. H. Kister of your staff on May 3,1983. An interim report was submitted via our letter dated June 1,1983.
Very truly yours, NIAGARA MOHAWK P0hTR CORPORATION Sa/muel. Nanno Vice President Nuclear Construction SFM/IRL:1f Enclosure xc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 Mr. R. A. Granus, Resident Inspector
, Q}l l 8311010086 831007
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1 NIAGARA M0 HAWK POWER CORPORATION NINE MILE POINT - UNIT 2 DOCKET NO. 50-410 Final Report for a Problem Concerning Failure of SRV Actuator
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l Description of the Problem The Nine Mile Point Unit 2 Main Steam Safety Relief Valve System uses Dikkers safety relief valves. The electropneumatic actuator assembly attached to the Dikkers safety relief valve failed to perform its safety-related function (i.e., fully open the safety relief valve and not leak in excess of 1.0 scfh) subsequent to being exposed to the accident radiation levels during a test program for compliance with NUREG-0588, Category I, requirements. High radiation values established for qualification testing (beta - 2.3 x 10 rads TID, gamma - 2.9 x 10 rcds TID) were responsible for the actuator assembly's failure.
Analysis of Safety Implication General Electric has confirmed that the electropneumatic actuators were environmentally qualified to the original GE environmental requirements.
Therefore, those safety relief valves actuators were in compliance with the applicable GE specifications and IEEE-323 Standard prior to the TMI event and the issue of NUREG-0588. Compliance with NUREG-0588 is beyond the original requirements for the safety relief valves provided by General Electric for Boiling Water Reactor (BWR) application. However, actions will be taken to qualify these valves to the requirements of NUREG-0588.
Based on the above, the original design criteria and bases stated in the preliminary safety analysis report or construction permit have not been violated. Therefore, the criteria for reportability under 10CFR50.55(e) have not been met.
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