ML17261A432
| ML17261A432 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/10/1987 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Lear G NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17261A434 | List: |
| References | |
| GL-85-09, GL-85-9, NUDOCS 8703180185 | |
| Download: ML17261A432 (5) | |
Text
ACCESSION NBR:
FAC IL:50-244 AUTH. NAl]E KOBERi R. W.
REC IP. NA'NE LEARN Q. E.
REGULATORY 'RNATION DISTRIBUTION SY (R IDS) 8703180185 DOC. DATE: 87/03/10 NOTARIZED: YES DOCKET 0 Robert Emmet Qinna Nuclear Planti Unit ii Rochester Q
05000244 AUTHOR AFFILIATION Rochester Gas 8c Electric Corp.
RECIPIENT AFFILIATION Document Control Branch (Document C'ontrol Desk)
PWR Prospect Directorate 1
SUBJECT:
Forulards application for amend to License DPR-.18 5 proposed Tech Specs re testing oF reactor trip breakersi per D DiIanni 870109 request. Fee paid.
DISTRIBUTION,CODE:
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TITLE: OR/Licensing Submittal:
Salem ATWS Events GL-83-28 NOTES: License Exp date in accordance arith 10CFR2i 2. 109'(9/19/72).
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TYATC ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 1464g-pppg ROGER W. KOBER VICE PIICSIOCNT CLCCTIIICPIIOOVCTION March 10, 1987 TCLCPHONC AIIcAcooc Tlc 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Mr. George E. Lear, Chief PWR Project Directorate No.
1 Washington, D.C.
20555
Subject:
Technical Specifications for Reactor Trip Breakers>
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Lear:
An NRC letter from Mr. Dominic DiIanni dated January 9c 1987 requested that RG&E submit proposed Technical Specifications concerning testing of reactor trip breakers.
In response to that request the following materials are enclosed:
An Application for Amendment to Operating License to amend Appendix A of that license to reflect requirements for the operating and testing of reactor trip breakers.
Included in this application are Attachments A and B
which set forth the requested change in Technical Specifications, its safety evaluationc and the basis for determining that the change does not involve a significant hazards consideration.
2.
A check for
$ 150 in accordance with 10CFR170.12 In a letter of March 197 19857 from Roger W. Kober of RG&E to John A Zwolinski of the NRCT questions from the staff were answered concerning Generic Letter 83-28.
The response to item 12 of the attachment to that letter contained commitments on the subject of response time testing.
In addition, an RG&E letter dated November 19c 1985 from Kober to Zwolinski proposed response time testing and criteria to initiate additional action in lieu of on-line reactor trip breaker testing.
The enclosed proposed Technical Specifications supercede the proposals in the November 19 letter.
Future response time testing will be performed only to establish acceptable breaker operating times necessary to meet accident analysis assumptions.
8703180185 870'>0 PDR ADDCK 05000244 P
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Because the modifications to the reactor trip breakers and the associated trip logic necessary for on-line testing have been completed, these proposed changes to the Technical Specif ications should be effective one month following notification to RGGE of approval by the NRC.
This one month period will allow for surveillance procedures to be finalized and implemented by the Ginna staff.
Ver truly yours<
Roger W. Kober Enclosures xc Nr. Jay Dunkleberger<
New York State Energy Office U.S. Nuclear Regulatory Commission Region 1
631 Park Avenue King of Prussia<
PA 19406 Ginna Resident Inspector