ML17261A364
| ML17261A364 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/09/1987 |
| From: | Diianni D Office of Nuclear Reactor Regulation |
| To: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17261A365 | List: |
| References | |
| GL-83-28, GL-85-09, GL-85-9, TAC-53174, NUDOCS 8701140360 | |
| Download: ML17261A364 (2) | |
Text
Jaw 0 9 1987 Docket No. 50-244 Mr. Roger W. Kober, Vice President Electric and Steam Production Rochester Gas II Electric Corp.
89 East Avenue Rochester, New York 14649
Dear Mr. Kober:
SUBJECT:
REVIEW OF DESIGN FOR AUTOMATIC SHUNT TRIP FOR REACTOR TRIP BREAKERS (GENERIC LETTER 83-28 ITEM 4.3)
By letter dated August 19, 1985, the Commission issued the safety evaluation dealing with the response provided by Rochester Gas and Electric Corporation for Item 4.3 (Reactor Trip Reliability) of Generic Letter 83-28 for the R.
E.
Ginna Nuclear Power Plant.
The conclusion section of the safety evaluation summarized confirmatory items to be resolved in order to complete our review of this issue.
By letters dated November 19,
- 1985, May 15, and November 20, 1986 and by telecon discussions on May 28, June 19 and June 30, 1986 you responded to all of our outstanding concerns except for submission of the technical specification change request.
The staff has reviewed this information and finds it acceptable.
Based on committed design modifications by Rochester Gas and Electric Corporation, we find the design of the reactor trip system to include the automatic actuation of the shunt trip attachment on the reactor trip breakers meets the requirements of Item 4.3 of GL 83-28 and, therefore, is acceptable.
By this action, we have completed our design review effort of the reactor trip system at R.
E. Ginna and TAC No.
53174 will be closed.
We request that you submit within 60 days from the date of this letter proposed changes to the technical specifications.
The technical specification change request should meet the guidance given in Generic Letter 85-09 or be equivalent to the Prairie Island Amendment Nos.
75/68 issued by letter dated June 26, 1985.
Your technical specification change request should also address the effective date of the specifications, considering the installation completion date of the modifications, and the time necessary to complete an NRC audit by the R.
E. Ginna Resident Inspector.
A copy of our supplemental safety evaluation is enclosed.
Sincerely, S70ii4Oa~O awOSOV F oR coact.osoooaie.'," I
Enclosure:
As Stated Dominic C. DiIanni, Project Manager Project Directorate 81 Division of PWR Licensing-A cc's:
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- SEE PREVIOUS CONCURRENCE Office:
LA/PADP1 Surname:
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Nr. Roger W. Kober Rochester Gas and Electric Corporation R.
E. Ginna Nuclear Power Plant CC:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and HacRae 1333 New Hampshire
- Avenue, N.W.
Suite 1100 Washington, D.C.
20036 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R.E.
Ginna Plant c/o U.S.
NRC 1503 Lake Road
- Ontario, New York 14519 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road
- Ontario, New York 14519 Jay Dunkleberger Division of Policy Analysis
& Planning New York State Energy Office Agency Building 2
Empire State Plaza
- Albany, New York 12223