ML18089A246
| ML18089A246 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/22/1983 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18089A247 | List: |
| References | |
| GL-83-28, NUDOCS 8307270402 | |
| Download: ML18089A246 (4) | |
Text
OPStiG
- Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department July 22, 1983 Director of Nuclear Reactor Regulation
- u. s. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch l Division of Licensing Gentlemen:
RESPONSE TO GENERIC LETTER 83-28 NO. 1 AND 2 UNITS SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 PSE&G hereby submits its response with respect to Salem Generating Station, to Generic Letter 83-28, dated July 8, 1983, concerning required actions based on generic implications of the Salem reactor trip breaker failures on February 22 and February 25, 1983.
1.1 POST-TRIP REVIEW (PROGRAM DESCRIPTION & PROCEDURES)
The Salem post-trip review program is described in our letters to the NRC of March 8, 14 and April 7 and 8, 1983, submitted in conjunction with the restart of Salem 1 after the February events.
The detailed instructions are provided in Administrative Directive AD-16, which was submitted with our letter of March 14, 1983.
The latest revision of AD-16 is enclosed.
1.2 POST-TRIP REVIEW (DATA & INFORMATION CAPABILITY)
The Salem units have an existing sequence of events recorder installed which is capable of correctly sequenc-ing and timing plant events leading to unscheduled reactor trips, and indicating the proper actuation of safety related equipment.
The sequence of events recorder is driven by the plant computer and powered from a vital bus.
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The Energy People 95-21 68 (80 M) 11-82
r Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 2.1 EQUIPMENT CLASSIFICATION & VENDOR INTERFACE (REACTOR TRIP SYSTEM COMPONENTS) 7/22/83 Equipment classification and vendor interface programs are described in our letters of March 8, 14, 23 and April 7 and 8, 1983.
2.2 EQUIPMENT CLASSIFICATION & VENDOR INTERFACE (PROGRAMS FOR ALL SAFETY-RELATED COMPONENTS)
Equipment classification and vendor interface programs are described in our letters of March 8, 14, 23 and April 7 and 8, 1983.
3.1 POST-MAINTENANCE TESTING (REACTOR TRIP SYSTEM COMPONENTS)
Actions 3.1.1 and 3.1.2 of this position have been implemented as described in our letters of March 8, 14, and April 7 and 8, 1983.
3.2 POST-MAINTENANCE TESTING (ALL OTHER SAFETY RELATED COMPONENTS)
Actions 3.2.1 and 3.2.2 of this position have been implemented as described in our letters of March 8, 14 and April 7 and 8, 1983.
4.1 REACTOR TRIP SYSTEM RELIABILITY (VENDOR-RELATED MODIFICATIONS)
Vendor-recommended reactor trip breaker modifications have been implemented as described in our letters of April 7 and 8, 1983.
4.2 REACTOR TRIP SYSTEM RELIABILITY (PREVENTATIVE MAINTENANCE AND SURVEILLANCE PROGRAM FOR REACTOR TRIP BREAKERS)
Descriptions of the Salem preventative maintenance and surveillance programs have been provided in our letters of March 8, 14 and April 7 and 8, 1983.
The life testing program for the reactor trip breakers is described in our letter of May 31, 1983.
4.3 REACTOR TRIP SYSTEM RELIABILITY (AUTOMATIC ACTUATION OF SHUNT TRIP ATTACHMENT FOR WESTINGHOUSE AND B&W PLANTS)
This item is addressed in our letter of July 15, 1983 (attached).
r-Director of Nuclear Reactor Regulation
- u. S. Nuclear Regulatory Commission 4.4 REACTOR TRIP SYSTEM RELIABILITY (IMPROVEMENTS IN MAINTENANCE AND TEST PROCEDURES FOR B&W PLANTS)
This item does not apply to Salem.
4.5 REACTOR TRIP SYSTEM RELIABILITY (SYSTEM FUNCTIONAL TESTING) 7/22/83 On-line functional testing is described in our letters of March 8, 14 and April 7 and 8, 1983, and in our License Change Request, LCR 83-08, submitted on June 20, 1983.
This response provides our current status of conformance with the positions described in Generic Letter 83-28.
Acceptance of our corrective action program is documented in your safety evaluation (NUREG-0995), transmitted with your letter of April 29, 1983, authorizing restart of the Salem units.
We are undertaking a detailed review of Generic Letter 83-28 to determine what, if any, further actions may be required.
The results of this review will be submitted for your review no later than November 7, 1983.
Should you have any questions, do not hesitate to contact us.
Attachments CC:
Mr. Donald C. Fischer Licensing Project Manager Mr. Leif Norrholm Senior Resident Inspector Sincerely, E. A. Liden Manager -
Nuclear Licensing and Regulation
STATE OF NEW JERSEY
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SS.
COUNTY OF SALEM
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RICHARD A. UDERITZ, being duly sworn according to law deposes and says:
I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our response to Generic Letter 83-28, dated July 22, 1983, concerning generic implications of the Salem ATWS events, are true to the best of my knowledge, information and belief.
Subscribed and sworn to before me
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