ML20205G254

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Forwards RAI Re GL 95-07, Pressure-Locking & Thermal- Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 30 Days from Date of Ltr
ML20205G254
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 04/01/1999
From: Mozafari B
NRC (Affiliation Not Assigned)
To: Protsch E
IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
References
GL-95-07, GL-95-7, TAC-M93460, NUDOCS 9904070182
Download: ML20205G254 (7)


Text

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April 1, 1999 Mr. Eliot Protsch President IES Utilities Inc.

200 First Street, SE P.O. Box 351 Cedar Rapids, IA 52406-0351

SUBJECT:

CORRECTED ENCLOSUR.E: REQUEST FOR ADDITIONAL INFORMATION ON GENERIC LETTER 95-07," PRESSURE-LOCKING AND THERMAL-BINDING OF SAFEYY-RELATED POWER-OPERATED GATE VALVES," DUANE ARNOLD ENERGY CENTER (TAC NO. M93460)

Dear Mr. Protsch:

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 those safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.

In a letter of February 13,1996, IES Utilities (the licensee) submitted its180-day respocse to GL 95-07 for Duane Arnold Energy Center (DAEC). The NRC staff reviewed the licensee's submittal and requested additional information in a letter dated May 31,1996. In a letter dated July 3,1996, the licensee provi%d the additional information.

The NRC staff has reviewed the licensee's submittals regarding GL 95-07 for DAEC, and has determined that additionalinformation is necessary to complete our review. We request that you provide the additionalinformation as identified in the enclosure within 30 days of the date of this letter.

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Mr. Eliot Protsch.

Your timely response to the request for additional information (RAI) will assist us in meeting our schedule. This RAI and the schedule have been discussed with Robert Murrell of your staff. If you have any questions regarding this issue, please contact me at 301-415-2020.

Sincerely 9

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Brenda L. Mozafari, Project Manager, Section 1 Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-331

Enclosure:

As stated cc w/ encl.: See next page

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Mr. Eliot Protsch April 1, 1999 J

Your timely response to the request for additional information (RAl) will assist us in meeting cJr schedule. This RAI and the schedule have been discussed with Robert Murrell of your staff. If you have any questions regarding this issue, please contact me at 301-415-2020.

Sincerely Original si

' by:

Brenda L. Mozafari, Project Manager, Section 1 Project Directorate til Division of Licensing Project Management Office of Nuclear Reactor Regulation i

Docket No. 50-331

Enclosure:

As stated cc w/ encl.: See next page DISTRIBUTION Docket File ACRS PUBLIC STingen PD3-1 Reading JZwolinski GGrant, Rlli OGC DOCUMENT NAME: J:\\BRENDA\\DA934602.WPD "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE PM:PD31 LA:PD31 6

o NAME BMozafa@XCEBamhill 6!P DATE 4 / / /99 4 / ) /99 0FFICIAL RECORD COPY

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Mr. Eliot Protsch,

April 1, 1999

'Your timely response to the request for additional information (RAl) will assist us in meeting our schedule. This RAI and the schedule have been disedtsed with Robert Murrell of your staff. If you have any questions regarding this issue, please contact me at 301-415-2020.

l Sincerely l

Original. signed by:

Brenda L. Mozafari, Project Manager, Section 1 -

Project Directorate lli l

. Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-331

Enclosure:

As stated cc w/ encl.: See next page l

DISTRIBUTION

' Docket File -

ACRS PUBLIC STingen PD3-1 Reading JZwolinski GGrant, Rlli OGC 1

1 DOCUMENT NAME: J:\\BRENDA\\DA934602.WPD l

"C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE PM:PD31 LA:PD31 6

NAME BMozafa@X8"EBamhill $fg DATE 4 / / /99 4 / l /99 0FFICIAL RECORD COPY l

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M. L. Marchi Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant cc:

Foley & Lardner ATTN: Bradley D. Jackson One South Pinckney Street P.O. Box 1497 Madison, WI 53701-1497 Chairman Town of Cartton Route 1 Kewaunee,WI 54216 Harold Reckelberg, Chairman Kewaunee County Boerd Kewaunee County Courthouse Kewaunee,WI 54216 Attorney General 114 East, State Capitol Madison,WI 53702 U.S. Nuclear Regulatory Commission Resident inspectors Office Route #1, Box 999 Kewaunee, WI 54216-9511 Regional Administrator-Region ill U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4531 James D. Loock, Chief Engineer Public Service Commission of Wisconsin P. O. Box 7854 Maoison, WI 53707-7854 I

REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 95-07 RESPONSE FOR THE DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331

1. Your submittal dated July 3,1996, states that temperature measurements of the residual heat removal (RHR) torus suction piping'were scheduled to be taken by the Fall of 1996 to evaluate if RHR torus suction valves M01913, MO1921, MO2012, and MO2015 are susceptible to thermalinduced pressure locking. Discuss the results of the temperature measurements and the corrective actions taken to eliminate the potential for pressure locking if the valves are susceptible to pressure locking.
2. During a phone call on March 23,1999, you stated that you were reevaluating if the high pressure coolant injection (HPCI) turbine steam admission valve, MO2202, 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 event, pressure in the bonnet of MO2202 could be higher than upstream and downstream pressure when the valve is required to open. During the phone call, you stated that you developed a pressure locking analytical method to demonstrate that the valve will operate during pressure locking conditions.

On April 9,1997, a public meeting was conducted to discuss the Commonwealth Edison and Entergy Operations, Inc. pressure locking thrust prediction methodologies presented in GL 95-07 submittals. The minutes of the public meeting were issued on April 25,1997, and placed in the Public Document Room. The Commonwealth Edison and Entergy Operations, Inc., methodologies that predict the thrust required to open pressure locked flexible-wedge gate yalves, validation testing of the analytical method, enhancements to the Commonwealth Edison pressure locking, methodology, and pressure locking tests sponsored by the NRC conducted by Idaho National Engineering and Environmental Laboratory were discussed during the meeting.

The minutes of this public meeting indicate the type of information requested by the NRC in order to review and approve pressure locking thrust prediction methodologies.

In order for the NRC to review your pressure locking thrust prediction methodology, please provide the following information:

a.

Describe the pressure locking thrust prediction methodology and provide the test procedure /results that validated the methodology. Include any information that will help j

evaluate if your valve is similar to test valves as applicable.

b.

Results from pressure locking testing sponsored by the NRC perfoimed by Idaho National Engineering and Environmental Laboratory on a double disk and a flexible wadge gate valve have been placed in the Public Document Room (NUREG/CR-6611).

Please discuss if your pressure locking thrust prediction methodology accurately ENCLOSURE l

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predicted the results of these pressure locking tests. Indicate whether your pressure locking thrust prediction methodology accurately predicted the results of pressure locking tests performed by Commonwealth Edison that were discussed during the April 9,1997, public meeting.

i c.

Discuss the recommended margin between actuator capability and the calculated thrust value when using your pressure locking prediction methodology, any limitations associated with the use of your methodology and any diagnostic test equipment accuracy requirements. Commonwealth Edison Company provided this type of information to the NRC in a letter dated May 29,1998. This letter is in the Public Document Room (Accession Number. 9806040184).

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