ML17037B956

Letter Concerning Recent Events and Conclusions Concerning a Generic Review of Anticipated Transients with Scram and Requesting Additional Analyses and Identification of Design Changes by December 30, 1976

ML17037B956
Person / Time
Site:	Nine Mile Point
Issue date:	06/29/1976
From:	Boyd R Office of Nuclear Reactor Regulation
To:	Rhode G Niagara Mohawk Power Corp
References
NEDO-20626
Download: ML17037B956 (4)

Text

DISTRIBUTION:

Docket'ile NRC PDR Local PDR LWR-4 Reading June 29, 1976 RCDeYoung FJWilliams DBVassallo Docket No.'0-410 WKane NService ACRS (16)

OELD Niagara f<ohawk Power Corporation IE (g3)

ATTN: Hr. Gerald K. Rhode JMiller Vice President - Engineering RSBoyd 300 Erie Boulevard, West EPN Syracuse, New York 13202 EP LA OThiadani Gentlemen: TNovak This letter is to inform you of recent events and conclusions concerning our generic review of Anticipated Transients Without Scram (ATWS) as they relate to Nine Nile Point, Unit 2.

As you know, upon'he publication of our report on ATWS in

.September 1973, MASH-1270, we sent you a letter on October 10, 1973, requesting analysis of ATWS in compliance with WASH 1270 as it applied that to your facility. Your response of September 25, 1974, indicated you were referencing the General Electric topical report, NED0-20626, "Studies of BWR Designs for llitigation of Anticipated Transients Without Scram."

You are pr.obably aware that the NRC staff and General Electric personnel have been engaged in an extensive effort,to resolve our differences concerning the referenced General Electric topical report.

He published our Status Report (Enclosure 1) on December 9, 1975, wherein we stated that additional analyses and justification of the General Electric analysis model. are needed and that changes in typical General Electric plant designs are indicated. At the 189th Meeting of the Advisory Committee on ReactorsSafeguards (ACRS), the ATWS issue and our Status Reports were reviewed by the ACRS with the staff and General Electric.

We now consider our review of the General Electric ATWS methods to be complete'and our position clearly and adequately presented in the Status Report. We have written to General Electric (Enclosure 2) informing them that we expect by June 30, 1976, they can provide us with acceptable additional analyses and justification of the General Electric analysis model as ideni:ified in our Status Report. Therefore, we request that you provide by December 30, 1976, the following information:

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Niagara I(ohawk Power Corporation a. The additional analyses and justification of the General Electric analysis model identified in the Status Report. (lie anticipate that you will reference the generic June 30, 1976 General Electric analysis model.)

b. Based on these analyses, identification of the design changes needed to assure that the limits specified in"WASH-1270 will not be violated following an ATWS event.

We expect, of course, that the detailed desc} Pption of the design changes will be included in your Final Safety Analysis Report.

We have established the above schedules for the submittal of the required information to emphasize our determination to move forward to resolve the ATWS concern and conclude the lengthy deliberations that have taken place among all parties. We expect your effor ts will be directed to this same end, and if you have any questions regarding this letter, please let-me know.

This request for generic information was approved by GAO under a blanket clearance number B-180225 (R0072). This clearance expires July 31, 1977.

Sincerely, Otr final sly'< >II:

.. nnyd C

Roger S. Boyd, Director Division of Project Management Office of Nuclear Reactor Regulation

Enclosures:

1. Status Report

2. Letter to General Electric Company OPPICC~ LWR-4 AD/

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