ML20205C877

Requests That Encl questions,e-mailed to W Sparkman of Southern Nuclear Operating Co,Inc,Which Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC & Util Be Made Available in NRC PDR

ML20205C877
Person / Time
Site:	Farley
Issue date:	03/31/1999
From:	Jacob Zimmerman NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
GL-95-07, GL-95-7, NUDOCS 9904020051
Download: ML20205C877 (3)

Text

n 5 ^ March 31, 1999 MEMORANDUM TO: Docket File .

FROM: Jacob 1.Zimmerman, Project Manager Origina1 signed by:

Project Directorate ll/Section 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

FARLEY UNITS 1 AND 2 - PLACEMENT OF A DOCUMENT IN THE PUBLIC DOCUMENT ROOM Please make the attached questions available in the NRC's Public Document Room, l

These questions wore e-mailed, today, to Wes Sparkman of the Southern Nuclear Operating l Company, Inc. These questions will be used to facilitate discussions during an upcoming conference call between NRC and SNC staffs. This document neither constitutes a formal request for information nor does it represent a formal NRC staff position.

Docket Nos. 50-348 and 50-364

Attachment:

As stated Distribution Docket File RUBLICU H. Berkow R. Emch S. Tingen Ol' D\

DOCUMENT NAME: G:\FARLEY\9507RAl.WPD Ta receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure

'E" = Copy with attachment / enclosure "N" = No copy OFFICE PMfS)(-f) LA:PDil 2 SC:ll-1 l D:P0l h l NAME JZimMefman:en CHawes(f/M REmch HBdr@ V DATE $ /D/99 8 (dv/99 3 /31/99 '6/ g[/99 / /99 / /97

. OFFICIAL RECORD COPY 9904020051 990331

• PDR ADOCK 05000348 P PDR

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2 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055W1

% ,,,,, # March 31, 1999 MEMORANDUM TO: Docket File '

FROM: Jacob 1. Zimmerman, Project Manager M- l Project Directorate ll/Section 1 Division of Licensing Project Management  !

Office of Nuclear Reactor Regulation

SUBJECT:

FARLEY UNITS 1 AND 2 - PLACEMENT OF A DOCUMENT IN THE PUBLIC DOCUMENT ROOM l

Please make the attached questions available in the NRC's Public Document Room.

These questions were e-mailed, today, to Wes Sparkman of the Southern Nuclear Operating Company, Inc. These questions will be used to facilitate discussbns during an upcoming l l

conference call between NRC and SNC staffs. This document neither constitutes a formal l request for information nor does it represent a formal NRC staff position.

I I

Docket Nos. 50-348 and 50-364 1 i

Attachment:

As stated i

l

l Conference Call Questions  !

Joseph M. Farley, Units 1 and 2 Generic Letter 95-07," Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves" l

1. Your submittal dated June 30,1996, states that the residual heat removal (RHR) to hot Leg injection valves,1(2)-MOV8889, are not susceptible to pressure locking because they are not opened until 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> after initiation of an accident and after 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> 4

prqssure in the bonnets will decay. Does the temperature of the valves increase at any  ;

time during the 11-hour period? If so, are the valves susceptible to thermalinduced I pressure locking?

2. In Attachment 1 to GL 95-07, the NRC staff requested that licensees include consideration 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 that, 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 peifonn one of the following within the scope of GL 95-07:

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

b. Follow plant technical specifications for the tra:n/ system while the valve is closed,

c. Demonstrate that the actuator has sufficient capacity to overcome these j 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 st veillance but must return to the open position, would be evaluated within the scope of GL 95-07. Your July 30,1996, submittal states that when you stroke test a valve you do not declare it inoperable because it is shut for only 1 to 2 minutes.

This does not comply with GL 95-07 scoping guidance. 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 reopen due to pressure locking defeating the capability of the safety system or train?

3. Your February 12,1996, submittal lists the RHR pump recirculation valves, 2-FCV0602A/B, and the low head safety injection cold leg injection valves, 1(2) MOV8888A/B, as screening code PL-7 and the submittal states that all PL-7 screening codes require an analytical evaluation using the Entergy Operations Inc.,

and/or the Commonwealth Edison models. What anc.lytical method was used to l demonstrate that these valves will operate during pressure locking conditions? Describe the margins between the required thrust to overcome pressure locking and actuator capability. Explain why these valves are not susceptible the thermal binding.

4. Are Units 1 and 2 licensed as hot shutdown?

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