ML20141N719
| ML20141N719 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/03/1986 |
| From: | Mangan C NIAGARA MOHAWK POWER CORP. |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| (55(E)-84-40), (NMP2L-0647), (NMP2L-647), NUDOCS 8603180008 | |
| Download: ML20141N719 (1) | |
Text
I.
NIAGARA MOHAWK POWER CORPORAT10N/300 ERIE DoVLEVARD WEST SYRACUSE, N.Y.13202/ TELEPHONE (315) 4741511 March 3, 1986 (NMP2L 0647)
Mr. R. W. Starostecki, Director U.S. Nuclear Regulatory Commission Region I Division of Reactor Projects 631 Park Avenue King of Prussia, PA 19406 Re: Nine Mile Point - Unit 2 Docket No. 50-410
Dear Mr. Starostecki:
Enclosed is a final report, in accordance with 10CFR50.55(e), f6r the problem concerning the qualification of containment purge system (CPS) isolation valves for seismic and hydrodynamic loadings.
This problem was reported via tel-con to S. Collins of your staff on September 19, 1984, and an interim i
l report was submitted on October 19, 1984.
Very truly yours, C. V. Mangan Senior Vice President CVM/GG/cla (1478H) xc:. Director of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 R. A. Gramm, NRC Senior Resideiit Inspector NMPC Project File 8603180000 860303 PDR ADOCK 05000410 S
PDR iI,
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NIAGARA M0 HAWK POWER CORPORATION NINE MILE POINT - UNIT 2 DOCKET N0. 50-410 Final Report for a Problem Concerning Containment Purge System Isolation Valves - Seismic Loading (55(e)-84-40)
Description of the Problem The problem pertains to containment purge system isolation valves.
An analysis of this system indicates that the calculated accelerations which these valves may encounter when subjected to dynamic loads could exceed those specified in the purchase specifications.
Analysis of Safety Implications The calculated valve accelerations are obtained from the initial pipe stress analysis.
This initial analysis is subject to verification to reflect as-built configurations.
As a result of this verification, the loadings for tFe subject valves were found to be higher than the generic loads used as a criteria for the original specification.
In the case of valves 2 CPS *A0V 104,
- 105, 110 and
- 111, the new loadings will be incorporated into the specifications, and additional supports will be added.
It is recognized that design changes and field modifications can rcsult in as-built conditions significantly different than the initial design.
Project Procedure 93 ("Cetegory I Pipe Stress and Supports Final Reconciliation")
requires reconciliation of the design loadings to the final loadings resulting from the as-built analysis.
Since conditions of this type are expected to occur and a method of identi-fying and correcting these conditions is provided, we feel no design or construction deficiency exist.
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