ML20137F292
| ML20137F292 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/22/1985 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, SBN-861, NUDOCS 8508260187 | |
| Download: ML20137F292 (2) | |
Text
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g, George S. Thomas p
L Vice President-Nuclear Production ruene s.*:. or u.w mnpee.
N:w Hampshire Yankee Division SBN-861 T.F. B4.2.99 August 22, 1985 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) USNRC Letter dated June 18, 1985, " Request for Additional Information Following Preliminary Staff Review of Public Service Company of New Hampshire's Response to Generic Letter 83-28", G. W. Knighton to R. J. Harrison Subj ect: Additional Information Regarding Generic Letter 83-28 Items 2.1 and 3.2.3
Dear Sir:
In response to the referenced request for additional information, enclosed please find our response to items 2.1 and 3.2.3.
Responses to Generic Letter 83-28 items 4.5.2 and 4.5.3 will be supplied in a future submittal, consistent with the schedule set forth in Reference (b).
Very truly yours, A
<Q y'
George S. Thomas GST/WJH/cj b Enclosure cc: ASLB Service List 0
8508260187 850822
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PDR ADOCK 05000443 j
A PDR P.O. Box 300 + Seabrook,NHO3874 Telephone (603)474-9521
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Item 2.1 Respoese Based on an engineering review of design documents, operating and maintenance procedures, and controlled engineering lists, New Hampshire Yankee hereby confirms that the Seabrook Station reactor trip system components are identified and classified as safety related.
Item 3.2.3 Response l
Testing and maintenance programs for the reactor trip system at Seabrook Station are currently under development with expected completion by the end of October, 1985. These programs will be reviewed to identify any post.
maintenance testing that may degrade rather than enhance safety and will be revised as necessary based on the results of these reviews.
No post-maintenance testing requirements are included in the current proposed Seabrook Technical Specifications. However, any needed Technical Specifica-tion changes identified during development of these programs will be submitted to the NRC as necessary.
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