ML19246C400

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Forwards NRC to Westinghouse Requesting Addl Info Re Small Break LOCA Analyses & Analysis Methods. Documentaion Re Applicability of Westinghouse Results to Analyses at Facility Will Eventually Be Required by NRC
ML19246C400
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 06/11/1979
From: Schwencer A
Office of Nuclear Reactor Regulation
To: Counsil W
CONNECTICUT YANKEE ATOMIC POWER CO.
References
TASK-15-19, TASK-RR NUDOCS 7907240544
Download: ML19246C400 (2)


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gv.....f JUNE 1 1 UI9 Docket No. 50-213 Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270 Hartford, Connecticut 06101

Dear Mr. Counsil:

SU3 JECT:

INFORMATION COPY OF REQUEST FOR ADDITIONAL INFORMATION REGARDING WESTINGHOUSE SMALL BREAK LOCA ANALYSIS As we discussed with you during our meeting on May 30, 1979, the NRC staff is evaluating certain aspects of the NRC licensing process in light of the Three Mile Island Unit 2 (TMI-2) accident of March 28, 1979.

One of the aspects being addressed by the staff in its evaluation is the status of the models used in safety analyses, especially with regard to transients and small break LOCAs.

Enclosed is a copy of an NRC letter, d1ted June 4,1979, requesting infomation frcrn your nuclear steam s'>pply vendor, the Westinghouse Electric Corporation regarding small break LOCA analysas and analysis methods.

This enclosure is provided for your information.

It is our understanding that you are participating in this effort as it applies to your licensed power plant through an owners group.

At some point in this effort we will require that you document the applicability of the results of these Westinghouse analyses to your plant.

To tham end, a copy of all correspondence to Westinghouse and the cwners group on this matter will be provided to you and placed in our files on your specific plant.

Please contact P. D. O'Reilly, the statf's assigned project manager for this matter, if you have any questions.

Si nce rely, UAv-MA i

D. Zieinann, Chief Operating Reactors Branch #2 Division of Operating Reactors

Enclosure:

NRC June 4, 1979 letter to !!estinghouse cc: w/ enclosures See next page 7 9072409W.

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Mr. W. G. Counsil CC Day, Berry & Howard Counselors at Law One Constitution Plaza Hartford, Connecticut 06103 Superintendent Haddam Neck Plant RFD #1 Post Office Box 127E East Hampton, Connecticut 06424 Mr. James R. Himmelwright Northeast Utilities Service Company P. O. Box 270 Ha-tford, Connecticut 06101 Russell Library 119 Broad Street Middletown, Connecticut 06457 364 2733 O

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JUN 4 1979 Mr. Tom M. Anderson, Manager Nuclear Safety Department Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230

Dear Mr. Anderson:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING SMALL BREAK LOCA ANALYSIS As you are aware, the NKC staff is evaluating certain aspects of the NRC licensing process in light of the Three Mile Island Unit 2 (TMI-2) accident, of March 28, 1979. One of the aspects being addressed in this evaluation is the status of models used in safety analyses, especially those used to analyze transients and small break LOCA's.

In order for the staff to complete its evaluation of the response of currently operating Westinghouse-designed plants to postulated small break LOCA's, additional information is required. These information needs, which pertain to expected system behavior following postulated small break LOCA's and small break LOCA analysis methods and results, are identified in the enclosure to this letter.

Please provide, within seven days of the date of receipt of this lette',

your schedule for responding to the items contained in the enclosure. We recognize that some of the requested information may have already been provided to the staff in the course of other reviews.

In lieu of refer-encing already submitted material, we would prefer, in order to facilitate our review, that the responses be provided in one complete document.

The information contained in the enclosure was discussed with your repre-sentatives at our May 31,1979 meeting.

If you have any question regarding the contents of this i.etter, please contact P. D. O'Reilly, the assigned project manager.

Si n ce rel y,

lj DUPLICATE DOCUMENT f Entire document previously entered into system under:

ANO 79o7/ To/70 Enclosure :

No. of pages:

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