ML18079A557: Difference between revisions

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e Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 July 13, 1979 of Nuclear Reactor Regulatior; 1ran£ United States Nuclear Regulatory Commission rai COPY Washington, D.C. 20555 Attention:
PS~G e Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 July 13, 1979 Di~ector      of Nuclear Reactor Regulatior; United States Nuclear Regulatory Commission
Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management Gentlemen:
                                                                ~£GUlATORV D~Ckf!r'f          1ran£ u~[y rai COPY Washington, D.C.               20555 Attention:         Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management Gentlemen:
ROD DROP ANALYSIS NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 In a letter dated May 15, 1979, Public Service Electric and Gas Company addressed the Single Rod Drop issue. It was PSE&G's position that Salem Unit 2 incorporated an eering system which Westinghouse has stated prevents the power overshoot during a single rod drop event. Since this submittal, a meeting was held between Westinghouse, the NRC Core Performance Branch and the Reactor Safety Branch. This meeting resulted in a Staff recommendation that Westinghouse perform a safety analysis to assure that the auctioneered neutron flux signal in the rod control system would preclude exceeding any of the design criteria associated with the accident analysis.
ROD DROP ANALYSIS NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 In a letter dated May 15, 1979, Public Service Electric and Gas Company addressed the Single Rod Drop issue.                           It was PSE&G's position that Salem Unit 2 incorporated an auction-eering system which Westinghouse has stated prevents the power overshoot during a single rod drop event.                           Since this submittal, a meeting was held between Westinghouse, the NRC                                             1I Core Performance Branch and the Reactor Safety Branch.                             This meeting resulted in a Staff recommendation that Westinghouse perform a safety analysis to assure that the auctioneered neutron flux signal in the rod control system would preclude exceeding any of the design criteria associated with the accident analysis.               During that meeting, an interim position was established to assure a Reactor Trip via the Negative Rate Trip during a single rod drop event. To accomplish this, the Negative Rate Trip setpoint and the time constant on the Power Range NIS would be lowered.
During that meeting, an interim position was established to assure a Reactor Trip via the Negative Rate Trip during a single rod drop event. To accomplish this, the Negative Rate Trip setpoint and the time constant on the Power Range NIS would be lowered. To comply to this interim position, the Technical tions for Salem Unit 2 will be changed to reflect the lower setpoint requirements. If you have any questions related to the above subject, please do not hesitate to contact us.  
To comply to this interim position, the Technical Specifica-tions for Salem Unit 2 will be changed to reflect the lower setpoint requirements.
\. ' 0 fRB!:nergy People R. L. Mittl General Manager -Licensing and Environment Engineering and Construction 7907t9 0 5JLj 1 I 95-0942}}
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If you have any questions related to the above subject, please do not hesitate to contact us.
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                                                                                                \.
                                                                                      ~~
R. L. Mittl                                 ' 0 General Manager -
Licensing and Environment Engineering and Construction fRB!:nergy People                    7907t9 0 5JLj 95-0942}}

Latest revision as of 15:17, 21 October 2019

Summarizes Actions Taken Since Util 790515 Ltr Re Single Rod Drop Issue.Meeting Held Between Westinghouse & NRC Resulted in Recommendation That Former Perform Safety Analysis
ML18079A557
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/13/1979
From: Mittl R
Public Service Enterprise Group
To: Parr O
Office of Nuclear Reactor Regulation
References
NUDOCS 7907190514
Download: ML18079A557 (1)
v • d • e


Text

,.._

PS~G e Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 July 13, 1979 Di~ector of Nuclear Reactor Regulatior; United States Nuclear Regulatory Commission

~£GUlATORV D~Ckf!r'f 1ran£ u~[y rai COPY Washington, D.C. 20555 Attention: Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management Gentlemen:

ROD DROP ANALYSIS NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 In a letter dated May 15, 1979, Public Service Electric and Gas Company addressed the Single Rod Drop issue. It was PSE&G's position that Salem Unit 2 incorporated an auction-eering system which Westinghouse has stated prevents the power overshoot during a single rod drop event. Since this submittal, a meeting was held between Westinghouse, the NRC 1I Core Performance Branch and the Reactor Safety Branch. This meeting resulted in a Staff recommendation that Westinghouse perform a safety analysis to assure that the auctioneered neutron flux signal in the rod control system would preclude exceeding any of the design criteria associated with the accident analysis. During that meeting, an interim position was established to assure a Reactor Trip via the Negative Rate Trip during a single rod drop event. To accomplish this, the Negative Rate Trip setpoint and the time constant on the Power Range NIS would be lowered.

To comply to this interim position, the Technical Specifica-tions for Salem Unit 2 will be changed to reflect the lower setpoint requirements.

,*~

If you have any questions related to the above subject, please do not hesitate to contact us.

r;;Jil~

\.

~~

R. L. Mittl ' 0 General Manager -

Licensing and Environment Engineering and Construction fRB!:nergy People 7907t9 0 5JLj 95-0942

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