ML17255A603
| ML17255A603 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/09/1984 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17255A604 | List: |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR NUDOCS 8401170152 | |
| Download: ML17255A603 (4) | |
Text
REGULATOR NFORMATION DI'STRIBUTION 8 EM (RIDS)
AC'CESSION NBR; 8401170152 DOC ~ DATE! 84/01/09 NOTARIZED.. NO DOCKET ¹ FACIE:.50 244 Rober t Emmet Ginna Nuclear Plant~
Uni;t ir Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MAIERrJeEe Rochester Gas 8 Electric Corp RECI'P ~ NAME
'RECIPIENT AFFIL'IATION CRUTCHFIKLDrD, Operating Reactors Branch 5
SUBJECT:
Forwards "Seismic Structural Kvaluation of.Main Contr ol Boar dr" 'documenting, testing/analysis. requested by, NRC dur'ing r eview of "SEP
. opic II 6
~Seismic Considerations,."
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ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 YORK SYAYK JOHN E. MAICR Vice PnRRioent YKLKRiYONK ARKA COOK 7le 546.R700 January 9,
1984 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief
, Operating Reactors Branch No.
5 U.S. Nuclear, Regulatory Commission Washington, D.C.
20555
Subject:
SEP Topic III-6, Seismic Considerations R.
E. Ginna Nuclear Power Plant Docket No.
50-244
Dear Mr. Crutchfield:
During the review of SEP Topic III-6, "Seismic Design Considerations",
the NRC required that RGGE perform a seismic analysis of the main control board structure.
This report was to be submitted by the end of 1983.
Enclosed is a report entitled "Seismic Structural Evaluation of the Main Control Board",
November
- 1983, documenting the testing and analysis performed by URS/Blume on the Ginna main control board.
As a result of this effort, it has been determined that the main control board is expected to survive the SSE with some local yielding of the structural steel cover plates and stiffeners.
RG&E has decided to enhance the structural integrity of the main control
- board, as suggested in section 5 of the report, assuming NRC con-currence with the methodology and acceptance criteria presented.
This modification is presently scheduled to be performed during the Spring 1984 refueling outage.
Very truly yours, f
PDR 840ioe
- "5+OKiPci 50 R
Aoooii 050000ee PDR Jo n E. Maier
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