ML20205F981

Informs That Encl RAI Was Transmitted by Facsimile on 990331 to G Salamon of Public Svs Electric & Gas Co.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI

ML20205F981
Person / Time
Site:	Hope Creek
Issue date:	03/31/1999
From:	Richard Ennis NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
GL-95-07, GL-95-7, TAC-M93472, NUDOCS 9904070074
Download: ML20205F981 (3)

Text

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March 31,1999 MEMORANDUM TO: Docket File FROM: Richard B. Ennis, Project Manager, Section 2 /

Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION, GENERIC LETTER 95-07 i (TAC M93472)

The attached request for additional Information (RAI) was transmitted by facsimile on 1 March 31,1999 to Mr. Gabe Salamon of Public Service Electric & Gas Company (PSE&G).

Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

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Docket No. 50-354 i i

Attachment:

Draft RAI

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DISTRIBUTION - n Docket File .'

L PUBLIC JClifford REnnis OFFICE PDl/S2/PM NAME REnnis DATE- 3 /3 I/99 OFFICIAL RECORD COPY g g } g h h3 h DOCUMENT NAME: HCM93472.MEM '

9904070074 990331 (i()U

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s* j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2061 5 0001 4 ,o 9***** March 31,1999 MEMORANDUM TO: Docket File FROM: Richard B. Ennis, Project Manager, Section 2 q Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION, GENERIC LETTER 95-07 (TAC M93472)

The attached request for additionalinformation (RAI) was transmitted by facsimile on March 31,1999 to Mr. Gabe Salamon of Public Service Electric & Gas Company (PSE&G).

Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAl. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-354

Attachment:

Draft RAI

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, Clarifications regarding PSE&G's response to Generic Letter 95-07 Pressure-Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves Hope Creek Generating Station

1. Your submittal dated February 13,1996, states that the high pressure coolant turbine steam admission valve,1FDHV F001, is not susceptible to pressure locking. Explain if FDHV-F001 is susceptible to pressure locking during an event that results in a reduction in reactor pressure but reactor pressure remains high enough to operate the HPCI turbine. During this type of i

event, pressure in the bonnet of 1 FDHV-F001 could be higher than upstream and downstream pressure when the valve is required to open.

2. In Attachment 1 to GL 95-07, the NRC staff requested that licensees include consideration i i

of the potential for gate valves to undergo pressure locking or thermal binding during surveillance testing. During workshops on GL 95-07 in each Region, the NRC staff stated tnat, i if closing a safety-related power-operated gate valve for test or surveillance defeats the  ;

capability of the safety system or train, the licensee should perform one of the following within  ;

the scope of GL 95-07: l

a. Verify that the valve is not susceptible to pressure locking or thermal binding while closed, I

b. Follow plant technical specifications for the train / system while the valve is closed,

c. Demonstrate that the actuator has sufficien: capacity to overcome these phenomena, or

d. Make appropriate hardware and/or procedural modifications to prevent pressure locking and thermal binding.  ;

The staff stated that normally open, safety-related power-operated gate valves, which are closed for surveillance but must retum to the open position, would be evaluated within the scope of GL 95-07. YourJuly 10,1996, submittal states that when you stroke test a valve you do not declare it inoperable if the valve automatically repositions to its required position on a system initiation signal. Are there any instances where a valve would be stroked shut for  !

testing and while the valve is shut the upstream and/or downstream pressure could decrease to less than the pressure in the bonnet and the valve may not automatically reopen due to pressure locking defeating the capability of the safety system or train?

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