ML17262A765
| ML17262A765 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/16/1977 |
| From: | Case E Office of Nuclear Reactor Regulation |
| To: | White L ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17262A766 | List: |
| References | |
| NUDOCS 9203130310 | |
| Download: ML17262A765 (7) | |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM F
II REGULATORYINFORMATION DISTRIBUTION S%TEM (RIDE)
ACCESSION NBR:9203130310 DOC.DATE: 77/12/16 NOTARIZED:
NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION CASErE
~ G ~
Office of Nuclear Reactor Regulation, Director RECIP.NAME RECIPIENT AFFILIATION WHITE,L.D.
Rochester Gas
& Electric Corp.
SUBJECT:
Forwards "SER on ECCS Evaluation Model for Westinghouse Two-Loop Plants." for Nov 1977.
DISTRIBUTION CODE:
DF01D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Direct Flow Distribution:
50 Docket (PDR Avail)
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NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 S
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NOTE TO ALL"RIDS" RECIPIENTS:
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Vv Jfy*y4 UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20566 December 16, 1977 DEC 19 1977 L ~
Docket No. 50-244 Rochester Gas and Electric Corporation ATTN:
Mr. Leon D. White, Jr.
Vice President - Electric and Steam Production 89 East Avenue Rochester, New York 14604
/
I Distr. to Ginna NSARB
Response
instructions:
Gentlemen:
As you know, we have been re-evaluating the acceptability of the calculational model used to evaluate the performance of the emergency core cooling system (ECCS) in Westinghouse designed two reactor coolant loop plants, such as your R.
E. Ginna Atomic Power Station. Results of our evaluation of the model are presented in our Safety Evaluation Report on ECCS Evaluation Model for Westinghouse Two-Loop Plants, a copy of which is provided as Enclosure 1.
This evaluation concludes that the presently approved model does not appropriately account for ECCS water injected above the core.
In addition, we have performed analyses to determine the immediate safety significance of this conclusion for operating two-loop facilities and the nature and timing of any corrective action that may be needed.
A discussion of these analyses and our conclusions are presented in our Safety Evaluation Report on Continued Safe Operation of Westinghouse Designed Two-Loop Plants, a copy of which is provided as Enclosure 2.
We have concluded that operation of your two-loop facility may continue safely for a limited period of time while we determine, after discussions with you, the proper application of the staff re-evaluation of the Westinghouse two-loop model to your plant.
Accordingly, interim bases for continued safe operation of your facility must be developed within the next 30 days, taking into account the apparent deficiencies in the Westinghouse two-loop models described in our Safety Evaluation Reports.
We believe that such interim bases are likely to in-volve some additional operating limits to compensate for these model de-ficiencies.
In addition, a permanent resolution of the problems giving rise to these model deficiencies should be developed and provided to us, along with a schedule for its implementation, as soon as possible, but not later than 60 days after this 30 day period.
l 9203130310 771216 PDR ADOCK 0500024))
P PDR
Rochester Gas and Electric Corp. December 16, 1977 Therefore, pursuant to 10 CFR 50.54(f) of the Commission's regulations, you are requested to propose, within 30 days from the date of this letter, appropriate
- bases, including any necessary operating limitations, to justify continued operation of your facility beyond this 30 day period.
Any subsequent action that may be required will be based on our evaluation of your submittals.
If you do not choose to propose alternative
- bases, the staff will prepare suitable operating limitations based on its reassess-ment.
We will be happy to meet with you or any of your representatives to dis-cuss this matter.
Please contact your NRC Project tlanager if you wish such a meeting or if you have any questions.
Sincerely,
Enclosures:
1.
Safety Evaluation Report on ECCS Evaluation Model for Westinghouse Two-Loop Plants 2.
Safety Evaluation Report on Continued Safe Operation
'f Westinghouse Designed Two-Loop Plants cc w/enclosures:
See next page Edson G. Case, cting Director Office of Nuclear Reactor Regulation
Rochester Gas
& Electric Corporation 3
December 16, 1977 cc:
Lex K. Larson, Esquire
,LeBoeuf, Lamb, Leiby 5 MacRae 1757 N Street, N.
W.
Washington, D.
C.
20036 Mr. Michael Slade 1250 Crown Point Drive
- Webster, New York 14580 Rochester Committee for Scientific Infomation Robert E. Lee, Ph.D.
P. 0.
Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza
- Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Westinghouse Electric Corporation ATTN:
Mr. C. Eicheldinger, Manager Nuclear Safety Department PWR Systems Division Box 355 Pittsburgh, Pennsylvania 15230 Rochester Public Library 115 South Avenue Rochester, New York 14627