ML20106F483
| ML20106F483 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/15/1984 |
| From: | Mangan C NIAGARA MOHAWK POWER CORP. |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| (55(E)-84-23), (NMP2L-0203), (NMP2L-203), NUDOCS 8410300262 | |
| Download: ML20106F483 (2) | |
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NUMOHAWK Y NIAGARA.
NIAGARA MOHAWK POWER CORPORATION /300 ERIE BOULEVARD WEST. SYRACUSE, N Y.13202/ TELEPHONE (315) 474-1511 October 15, 1984 (NMP2L 0203)
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 Re: Nine Mile Point - Unit 2 Docket No. 50-410
Dear Mr. etarostecki:
Enclosed is a final report in accordance with 10CFR50.55(e) for the problem concerning simulated post-weld heat treatment qualification of main steam isolation valves furnished by Gulf & Western / Fluid Systems Division.
This problem was reported via tel-con to Mr. S. Collins of your staff on June 15, 1984 An interim report was submitted to you in our letter dated July 13, 1984.
Very truly yours, N
C. V. Mangan Vice President Nuclear Engineering and Licensing l
CVM/GG/pbd xc: Director of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 R. A. Gramm, NRC Resident Inspector Project File (2) 0410300262 841015 PDR ADOCK 05000410 S
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NIAGARA M0 HAWK POWER CORPORATION NINE MILE POINT - UNIT 2 DOCKET N0. 50-410 Final Report for a Problem Co:cerning Simulated PWHT Qualificatior of Main Steam Isolation Valves (55(e)-84-23)
Description of the Problem During a review of documentation, it was observed that the certified material test reports provided by the valve manufacturer did not document the test coupon heat treatment duration and temperature for the valve bodies as required by ASME Section III, NB-2211.
Subsequent investigation by the material manufacturer, Cameron Iron Works, Inc., has produced evidence of post weld heat treatment simulation on the test material for valve bodies of seven of eight valves.
The one remaining valve is the outermost MSIV in steam line A, bearing Mark No. 2 MSS *HYV7A.
Analysis of Safety Implication We performed an evaluation of the effect of simulated post weld heat treatment on the results of the tests required by the ASME Code.
Our evaluation concludes that the valve body is technically adequate as is and will provide an acceptable level of quality and safety and vould not adversely affect the safety of operations of the plant.
Niagara Mohawk is requesting approval of the acceptability of this valve from the Nuclear Regulatory Commission's Office of Nuclear Reactor Regulation, Division of Licensing.
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