ML20207J334
| ML20207J334 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/23/1986 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation |
| References | |
| 86-843, NUDOCS 8701080396 | |
| Download: ML20207J334 (3) | |
Text
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VInOINIA EI.ncTunc Ann Powna COMI*ANY RicuxoNie, VIHUINIA 20261 December 23, 1986 Vers Pune.ouwt Na:cLzan OPE RATIONS Mr. Harold R. Denton, Director Serial No.86-843 Office of Nuclear Reactor Regulation N0/JDH:vlh Attn:
Mr. Lester S. Rubenstein, Director Docket Nos.
50-280 PWR Project Directorate No. 2 50-281 Division of PWR Licensing-A License Nos.
NPF-/r 3 1 U. S. Nuclear Regulatory Commission NPFJ 3'1 Washington, D. C.
20555 Centlemen:
VIRCINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 IMPACT OF DECEMBER 9, 1986 SURRY 2 EVENT ON 40 YEAR CPERATING LICENSE AMENDMENT REQUEST On December 19, 1986, you requested that we provide information regarding the December 9, 1986 feedwater pump suction line rupture event at Surry Unit 2 and evaluate its impact on our license amendment request (August 22, 1986, as supplemented) to extend the Surry license period to forty years. Our response is provided below.
Question:
i What safety significance does the recent pipe failure event at Surry 2 due to corrosion / erosion have on the license extension request?
Response
We have evaluated the safety significance of the December 9,
1986 event at Surry Unit 2 snd have concluded that the event has no impact on our Surry license amendment request. The basis for our conclusion is sented oelow.
Current Technical Specifications and Inservice Inspection Programs as required by 10 CFR 50.55a for Surry require periodic inspection of safety-related systems and components and provide a high degree of assurance that any significant degradation of safety related piping would be promptly identified and corrected. These programs would continue during the extended license period.
In addition, the majority of safety-related piping is stainless steel rather than carbon steel and is not readily susceptible to the erosion / corrosion phenomena.
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Loss of normal feedwatei events have been analyzed for Surry and the recent Surry 2 event was bounded by those analyses.
It is not expected that any piping modifications that might be implemented as a result of this incident would affect those analyses. This would be verified as part of the design change review which includes assessments of impacts on accident analyses.
These actions would be taken independent of our license amendment request.
Question:
Is Virginia Electric and Power Company taking any special actions because of the incident that bears on the proposed license amendment request for Surry?
Response
Periodic inspection of certain non-safety related systems and components are covered by existing programs at to assure prompt identification and appropriate corrective actions for significant degradation.
As a result of the Surry incident, the scope of these programs will be expanded to include portions of systems and piping susceptible to the erosion-corrosion phenomena.
This action is being implemented independent of our forty year license amendment request and has no direct bearing on it.
However, these inspection
- programs, implemented during the current license period, would be continued during the extended license period and the same benefit from the programs would be derived during the additional years of operation.
Very truly
- urs, d
h f
W. L.
wart 1
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cc:
Dr. J. Nelson Grace Regional Administrator NRC Region II Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate No. 2 00: LN OC 330 98.
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