ML20206H667
| ML20206H667 | |
| Person / Time | |
|---|---|
| Site: | Seabrook |
| Issue date: | 06/24/1986 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20206H672 | List: |
| References | |
| GL-83-28, SBN-1137, NUDOCS 8606260256 | |
| Download: ML20206H667 (2) | |
Text
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~.mI George S. Tnomas Vice President Nuclear Product;on June 24, 1986 Put2c Service of New Hampshir9 SBN-1137
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New Hampshire Yankee Division United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. Vincent S. Noonan, Project Director PWR Project Directorate #5
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter (SBN-576), dated November 4,1983,
" Response to Generic Letter 83-28", J. DeVincentis to G. W. Knighton (c) PSNH Letter (SBN-961), dated March 6, 1986,
" Additional Information Regarding Generic Letter 83-28, Item 1.2, Post Trip Review (Date and Information Capability)", G. S. Thomas to V. S. Noonan Subj ect:
Additional Information Regarding Generic Letter 83-28 Item 1.1
Dear Sir:
In our original response to Generic Letter 83-28 [ Reference (b)], New Hampshire Yankee committed to address those items identified under Item 1.1,
" Post Trip Review" (Program Description and Procedure), with a post trip safety assessment procedure. Our initial commitment was to implement the procedure covering Item 1.1, three months prior to core load.
Seabrook Station has established a " Post Trip Review" procedure (Procedure No. OS1000.08) which establishes the requirements for performing formal post trip reviews for all reactor trip and safety injection events, and the criterion which must be met prior to starting up af ter a trip.
As it was recently requested by members of your staf f, please find enclosed a copy of Seabrook Station's " Post Trip Review" procedure. As discussed in a previous response to Staff concerns [See Reference (c)}, the data and information used during a post trip review will be retained in hard copy for the duration of the Seabrook Station operating license per the requirements of Technical Specification 6.9.3(e).
Additionally, your Staff requested clarification of the post trip review process regarding evaluations with respect to the plant Technical Specifications and FSAR. Our post trip review information will be analyzed for protection system response and overall plant behavior, and this will be comphred with expected plant response (s) as described in the Technical Specifications and/or FSAR.
8606260256 860624 PDR ADOCK 05000443 A
PDR P.O. Box 300 Seabrook,NH03874 Telephone (603)474-9521
'T United States Nuclear Regulatory Commission June 24, 1986 Attention:
Mr. Vincent S. Noonan Page 2 1
J We trust that this information provides the requested documentation to satisfactorily resolve our commitment to Item 1.1 of Generic Letter 83-28.
Very truly yours, 5
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George. Thomas Enclosure cc: ASLB Service List i
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