ML17292A438

Requests for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Requests That Licensee Take Action to Ensure That Valves Susceptible to Pressure

ML17292A438
Person / Time
Site:	Columbia
Issue date:	09/04/1996
From:	Colburn T NRC (Affiliation Not Assigned)
To:	Parrish J WASHINGTON PUBLIC POWER SUPPLY SYSTEM
References
GL-95-07, GL-95-7, TAC-M95359, NUDOCS 9609100384
Download: ML17292A438 (5)

Text

September 4,

1996 Mr. J.

V. Parrish Chief Executive Officer Washington Public Power Supply System P.O.

Box 968 (Mail Drop 1023)

Richland, Washington 99352-0968

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION GENERIC LETTER 95-07, "PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES," FOR THE WASHINGTON PUBLIC POWER SUPPLY SYSTEM (WPPSS)

NUCLEAR PROJECT NO.

2 (WNP-2)

(TAC NO. H95359)

Dear Mr. Parrish:

On August 17, 1995, the NRC issued Generic Letter (GL) 95-07, "Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees take actions to ensure that safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.

The NRC staff is reviewing and evaluating your responses to GL 95-07 dated October 13,

1995, and'ebruary 13 and July 12, 1996.

Additional information, as discussed in the enclosure, is requested in order for the staff to complete its review.

We

request that you respond within 30 days.

The information requested by this letter is within the scope of the overall burden estimated in Generic Letter 95-07, "Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," which was a maximum of 75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> per response.

This request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires July 31, 1997.

Docket No. 50-397

Enclosure:

Request for Additional Information' cc w/encl:

See next page DOCUMENT NAME: WNP93539.RAI Sincerely, Original Signed By Timothy G. Colbur n, Senior Project Hanager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation DISTRIBUTION:

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V. Parrish September 4,

1996 cc w/encl:

Hr. Greg 0. Smith (Hail Drop 927M)

WNP-2 Plant General Manager Washington Public Power Supply System P. 0.

Box 968

Richland, Washington 99352-0968 Mr. Al E. Mouncer (Mail Drop 396)

Chief Counsel Washington Public Power Supply System P.O.

Box 968

Richland, Washington 99352-0968 Mr. Frederick S. Adair, Chairman Energy Facility Site Evaluation Council P. 0.

Box 43172 Olympia, Washington 98504-3172 Mr. David A. Swank (Hail Drop PE20)

Manager, Regulatory Affairs Washington Public Power Supply System P.O.

Box 968

Richland, Washington 99352-0968 Hr. Paul R.

Bemis (Mail Drop PE20)

Vice President, Nuclear Operations Washington Public Power Supply System P.O.

Box 968

Richland, Washington 99352 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower 8 Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Chairman Benton County Board of Commissioners P.O.

Box 69

Prosser, Washington 99350-0190 Hr.

R.

C. Barr, Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O.

Box 69

Richland, Washington 99352-0968 H.

H. Philips, Jr.,

Esq.

Winston

& Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 Hr. Rodney L. Webring (Hail Drop PE08)

Vice President, Operations Support/PIO Washington Public Power Supply System P. 0.

Box 968

Richland, Washington 99352 Hs.

Lourdes C. Fernandez (Hail Drop PE20)

Manager, Licensing Washington Public Power Supply System P.

O.

Box 968

Richland, Washington 99352

RE U ST FOR ADD TIONAL NFORMATION R

SPONSE TO GENERIC TTER 95-07 WASHINGTON PUBLIC POW R SUPPLY SYSTEM NUCL AR PROJECT NO.

2 DOCKET NO. 50-397 Regarding valve HPCS-V-4, High Pressure Core Spray Injection, the WPPSS submittal states that the HPCS pump will relieve pressure locking in 2.6

seconds, and that a capability evaluation demonstrates capability to open the valve during the'short transient.

The NRC staff believes that reliance on pump pressure to relieve a pressure locked condition is uncertain.

This is because the valve actuator may be damaged due to

'peration at locked rotor conditions between the time the valve is initially called upon to open, the pump is started and the pressure in the vicinity of the valve builds up sufficiently to relieve the pressure locked condition.

Please provide information on how this uncertainty is addressed for WNP-2.

In addition, please provide the capability evaluation, including thrust requirement and actuator capability calculations, for our review.

Regarding valve RCIC-V-31, Reactor Core Isolation Cooling Suppression Pool Suction, the licensee's submittal states that a capability evaluation demonstrates valve capability under pressure locked conditions.

Please provide this capability evaluation, including thrust requirement and actuator capability calculations, for our review.

In addition, the NRC staff believes that valve RCIC-V-31 may be potentially susceptible to thermally-induced pressure locking through heat transfer from the suppression pool during a design basis event.

Please address this issue.

If applicable, please provide for our review any heat transfer analyses completed to address this concern.

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