ML18095A664
| ML18095A664 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/21/1990 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR GL-90-06, GL-90-6, NLR-N90234, NUDOCS 9101070048 | |
| Download: ML18095A664 (5) | |
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Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations DEC 2 1 19~Q NLR-N90234 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
GENERIC LETTER 90-06 RESOLUTION OF GENERIC ISSUE 70 AND GENERIC ISSUE 94 SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 On June 25, 1990, the Nuclear Regulatory Commission (NRC) issued Generic Letter 90-06, concerning power operated relief valve (PORV) and block valve reliability and additional low-temperature overpressure protection (LTOP) for light-water reactors.
Public Service Electric and Gas Company (PSE&G) hereby provides its response to Generic Letter 90-06 for Salem Units 1 and 2.
Salem Units 1 and 2 commit to include PORVs and block valves within the scope of an operational quality assurance program that is in compliance with 10 CFR Part 50 Appendix B.
In accordance with these requirements:
the PORVs and block valves are included in the plant operational Quality Assurance List, a maintenance/refurbishment program for PORVs and block valves, based on the manufacturer's recommendations has been implemented by trained plant maintenance personnel (a discussion of the basis for the present preventative maintenance schedule is provided in ), and replacement parts and spares as well as complete components, when required, for the PORVs and block valves (and associated control systems) will be procured in accordance with the original construction codes' and standards.
Salem Units 1 and 2 commit to include PORVs, valves in PORV control air systems, and block valves within the scope of the Inservice Testing (IST) Program. Procedural modifications, needed to implement the required testing, will be completed by the end of the upcoming Salem Unit 1 refueling outage.
The block valves will also be included in the expanded Motor Operated Valve (MOV) test program in accordance with Generic Letter 89~10.
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Document Control Desk NLR-N90234 2
DEC 2 1 1990" Salem Units 1 and 2 commit to submitting Technical Specification changes similar to the Technical Specification changes recommended in the generic letter.
PSE&G will perform plant specific Probabilistic Risk Assessment (PRA) analysis to evaluate the effects of extending the Allowed Outage Times (AOT) recommended in the Generic Letter.
(The specific changes which will be analyzed for extended AOTs are described in Attachment 2)
The PRA analysis will be completed by the end of March 1991.
The results of this analysis will be used to formulate PSE&G's License Change Request. PSE&G will submit a Technical Specification change for LTOP which agrees with the requirements of the Technical Specification change recommended in the generic letter.
Due to the effect of the upcoming outage on plant resources, the License Change Request will be submitted within 60 days of the conclusion of the Salem Unit 1 refueling outage.
Sincerely, Attachments c Mr. J. c. Stone Licensing Project Manager Mr. T. P. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
REF:
NLR-N90234 STATE OF NEW JERSEY
)
)
SS.
COUNTY OF SALEM
- s. LaBruna, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated DEC 2 1 1990
, concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.
Subscribed and sworn t~}>efore
.this c:< I day of ~
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Notary Public of New Jersey My Commission expires on
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' 1990
ATTACHMENT 1 MAINTENANCE OF PORV AND BLOCK VALVES Presently the preventative maintenance schedule for the PORVs and block valves is based on a combination of the vendor recommendations and plant experience.
PSE&G is performing a Reliability Centered Maintenance Analysis to evaluate various maintenance tasks for applicability and schedule based on industry information, vendor recommendations and plant specific historical performance.
The purpose of the analysis is to optimize maintenance tasks and schedules to provide the most reliable service of plant components.
The PORVs and block valves will be analyzed using Reliability Centered Maintenance techniques.
This analysis will be completed by December 31, 1991.
NLR-N90234
ATTACHMENT 2 MODIFICATION TO GENERIC LETTER RECOMMENDED TECHNICAL SPECIFICATION CHANGE REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITIONS FOR OPERATION ACTION b. With one PORV inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODIFICATION: Analysis will be done using plant specific PRA to justify extending the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Allowed Outage Time to 7 days.
ACTION c. With both PORVs inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore at least one PORV to OPERABLE status or close its associated block valve and remove power from the block valve and be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODIFICATION: Analysis will be done using plant specific PRA to justify extending the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Allowed outage Time to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION d. With one or both block valves inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the block valve(s) to OPERABLE status or place its associated PORV(s) in manual control.
Restore at least one block valve to OPERABLE ~tatus within the next hour if both block valves are inoperable; restore any remaining inoperable block valves to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN with in the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODIFICATION: Analysis will be done using plant specific PRA to justify extending the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Allowed outage Time to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and extending the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Allowed Outage Time to 7 days.
NLR-N90234