ML20236F665
| ML20236F665 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/26/1998 |
| From: | Oheim H BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 50-293-97-13, BECO-2.98.087, GL-89-10, NUDOCS 9807020272 | |
| Download: ML20236F665 (2) | |
Text
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Boston Edison GL89-10 Pdgnrn Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360 i
Henry V. Oheim -
General Manager Technical Section June 26,1998 BECo Ltr. #2.98.087 i
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U.S. Nuclear Regulatory Commission i
Attention: Document Control Desk I
Washington, DC 20555 I
Docket No. 50-293 License No. DPR-35 SUPPLEMENTARY INFORMATION RELATED TO CLOSURE OF GENERIC LETTER 89-10
References:
1.
, BECo Letter No. 2.97.129, " Supplementary Information Related to Closure of Generic Letter 89-10," dated December 11,1997.
j 2.
NRC Letter to Boston Edison, " Pilgrim inspection Report 50-293/97-13 and Notice of Violation," dated February 6,1998 (BECo Letter No.
1.98.006)
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This letter provides supplementary information related to closure of Generic Letter 89-10. It l
addresses issues raised during NRC Inspection 97-13 concerning motor operated valve (MOV) close-out activities.
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Discussions with the NRC during the MOV close-out inspection confirmed that the EPRI l
MOV Performance Prediction Methodology (PPM) could provide bounding estimates of
. thrust requirements for MOVs that could not be acceptably tested at design basis conditions.
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This reinforced our planned initiative to implement the EPRI PPM to strengthen our current
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Justification for valves with weak valve factor justifications, consistent with the intent of GL O
89-10. As described in Reference 2, Boston Edison committed to obtain, as part of our long term MOV program, additional industry information or analyses to strengthen certain va!ve factor assumptions. By Reference 1, we committed to complete implementation of this effort by June 30,'1998, in Reference 2, the NRC also noted several MOVs with relatively small gfu design margins which should be addressed for long-term consideration, and Boston Edison T
intended to inform the NRC of the plans for these valves by June 30,1998.
Boston Edison has begun a program to implement the EPRI PPM for a number of MOVs.
1 The scope of valves that is included has expanded beyond that which we had envisioned
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when the original commitment was made. In addition to those MOVs whose valve factor assumptions require strengthening, valves with small design margins are also being
. evaluated using the EPRI PPM. We have also considered our MOV periodic verification
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program and included additional valves to be evaluated using PPM. We are in the process of obtaining the detailed valve design information required for use in the PPM. We have contracted engineering services for performance of the PPM evaluations. Once the PPM evaluations are complete for all of the subject valves, the need for further engineering evaluation or modifications will be determined. We expect to complete this effort by November 15,1998.
As part of our current effort, we will give priority, to the extent possible, to completing the PPM evaluations for those valves which were identified as having small design margins. By November 15,1998, we will inform you of the results of the PPM evaluations for all valves addressed in the close-out inspection report.
This will include a description of any modifications which will be done to improve margins and a schedule for completing the modifications, as well as a listing of any valves which were determined to be adequate without modification.
Should you have any questions regarding the above subject matter, please con act Walter Lobo at 508-830-7940.
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H.V. Oheim WGL/lb/89-10 Bel cc:
Mr. Alan B. Wang, Project Manager Project Directorate 1-1 Office of Nuclear Reactor Regulation Mail Stop: 1482 U. S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Region'l 475 Allendale Road King of Prussia, PA 19406 Senior Resident inspector Pilgrim Nuclear Power Station 2
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