ML18092A815
| ML18092A815 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/20/1985 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8509270123 | |
| Download: ML18092A815 (3) | |
Text
Public Service Electric and Gas Company Corbin A. McNeil!, Jr.
Vice President -
Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 Nuclear September 20, 1985 U.S. Nuclear Regulatory Commission Off ice of Nuclear Reactor Regulation Division of Licensing Washington, D. c.
20555 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch, No. 1 Gentlemen:
REQUEST FOR ADDITIONAL INFORMATION FOLLOWING PRELIMINARY STAFF REVIEW OF LICENSEE RESPONSES TO GENERIC LETTER 83-28 SALEM UNITS 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Pursuant to the subject request for additional information dated July 22, 1985, PSE&G herewith submits its response in the attachment to this letter.
Should you have any questions we will be pleased to discuss them with you.
Attachment C
Mr. Donald c. Fischer Licensing Project Manager Mr. Thomas J. Kenny Senior Resident Inspector Sincerely, r~s:il5~0~9;;2~7;:;0;-:1~2~3:-:-::e:-:5:-:o~~92=-=c;=-=o~---~
PDR ADDCK.05000272 p ----'
SALEM UNITS 1 AND 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON GENERIC LETTER 83-28 Item 2.1.1 -
Incomplete Licensee responded that reactor trip breakers were identified as safety-related equipment but needs to supply a statement confirming that reactor trip system components were reviewed and that (sic) are identified as safety-related on documents, procedures, and information handling systems.
Response
Reactor Trip System equipment has been reviewed and is identified as safety-related on documents, procedures and information handling systems used in the plant to control safety-related activities.
In our letters of March 14, April 7, and April 8, 1983, use of the Master Equipment List (MEL) as the document to classify maintenance work orders and procurement documents was described.
Additionally, the plant procedures used for testing the Reactor Trip System have been reviewed and found to be properly classified as safety-related.
Item 2.2.1 -
Incomplete Licensee responded to items 2.2.1.1 to 2.2.1.5, but needs to submit additional information as requested in items 2.2.1.1 (criteria for identifying components as safety-related) and 2.2.1.6 (equipment classification program for safety-related components).
Response
Item 2.2.1.1 The criteria utilized in classifying equipment for the Salem Master Equipment List was 10CFRlOO Appendix A, "Seismic and Geological Siting Criteria for Nuclear Power Plants", ANSI Nl8.2, "Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants", and IEEE 308-1971, "Criteria for Class lE Electric Systems for Nuclear Power Generating Stations.
11 Item 2.2.1.6 Per the August 7, 1985 telephone conversation between our Mr. R. w. Beckwith and Mr. D. c. Fischer -
NRC Licensing Project Manager, it has been determined that a response to this item is not required since regulations related to this subject already exist.
Item 3.1.3 & 3.2.3 -
Incomplete Licensee needs to state if he has found any post-maintenance testing requirements for either RTS components or other safety-related equipment that may degrade safety.
If any such are identified, the applicant shall describe actions to be taken including submitting needed T.S. changes.
Response
PSE&G has not found any post-maintenance testing requirements for either Reactor Trip System components or other safety-related equipment that may degrade safety.