ML20207M959
| ML20207M959 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/15/1999 |
| From: | Lawrence Burkhart NRC (Affiliation Not Assigned) |
| To: | Horn G NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| GL-95-07, GL-95-7, TAC-M93453, NUDOCS 9903190305 | |
| Download: ML20207M959 (4) | |
Text
. _ _ _ _ _ _ _.. _ _ _ _ _ _ _ _
Mr. G. R. Horn March 15, 1999 Sr. Vice President of Energy Supply Nebraska Public Power District 141415th Street Columbus, NE 68601
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER (GL) 95-07,
" PRESSURE-LOCKING AND THERMAL-BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES," COOPER NUCLEAR STATION (TAC NO. M93453)
Dear Mr. Horn:
On August 17,1995, the Nuclear Regulatory Commission (NRC) issued Generic Letter
' (GL) 95-07, " Pressure Locking and Thermal Binding of Safety-Relatetl Power-Operated Gate Valves," to request that licensees take actions to ensure those safety-related power-operated j
gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.
In a letter dated February 13,1996, Nebraska Public Power District (NPPD, the licensee) submitted its 180-day response to GL 95-07 for the Cooper Nuclear Station (CNS). The NRC I
staff reviewed the licensee's submittal and requested additional information in a letter dated May 28,1996. In a letter dated June 27,1996, the licensee provided the additional information.
The staff has reviewed NPPD's submittals and has determined that additionalinformation is j
necessary to complete its evaluation. The information requested is enclosed and was discussed with your staff on February 4 and March 2,1999. It was agreed that NPPD's response would be provided no later than 90 days from the date of this letter.
i Sincerely,
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Lawrence J.,B0rkhart,- Project Manager Project Directorate IV-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-298 DISTRIBUTION Docket File -
Enclosure:
Request for Additional PUBLIC OGC
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k*****,o March 15,1999 Mr. G. R. Horn Sr. Vice President of Energy Supply Nebraska Public Power District 141415th Street Columbus, NE 68601
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 95-07,
' PRESSURE-LOCKING AND THERMAL-BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES," COOPER NUCLEAR STATION (TAC NO. M93453)
Dear Mr. Horn:
On August 17,1995, the Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to roquest 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 dated February 13,1996, Nebraska Public Power District (NPPD, the licensee) submitted its 180-day response to GL 95-07 for the Cooper Nuclear Station (CNS). The NRC staff reviewed the licensee's submittal and requested additional information in a letter dated May 28,1996. In a letter dated June 27,1996, tree licensee provided the additional information.
The staff has reviewed NPPD's submittals and has determined that additional information is necessary to complete its evaluation. The information requested is enclosed and was discussed with your staff on February 4 and March 2,1999. It was agreed that NPPD's response would be provided no later than 90 days from the date of this letter.
Sincerely,
'/
f f
j Lawrence J. Bur hart, Project Manager Project Directorate IV-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
Request for Additional i
Information I
cc w/enci: See next page i
o Mr. G. R. Hom s
Nebraska Public Power District Cooper Nuclear Station ec:
l Mr. John R McPhail, General Counsel Lincoln Electric System Nebraska Public Power District ATTN: Mr. Ron Stoddard P. O. Box 499 1040 O Street Columbus, NE 68602-0499 Box 80869 Lincoln, NE 68501 Nebraska Public Power District ATTN: Mr.J. H. Swalles MidAmerican Energy Vice President of Nuclear Energy ATTN: Dr. William D. Leech, Manager-Nuclear P. O. Box 98 907 Walnut Street 4
Brownville, NE 68321 P. O. Box 657 Des Moines, IA 50303-0657 Randolph Wood, Director Nebraska Department of Environmental Nebraska Public Power District Control ATTN: Mr. B. L. Houston, Nuclear P. O. Box 98922 Licensing & Safety Manager Lincoln, NE 68509-8922 P. O. Box 98 Brownville, NE 68321 Mr. Larry Bohiken, Chairman Nemaha County Board of Commissioners Nemaha County Courthouse 1824 N Street Aubum, NE 68305 Senior Resident inspector U.S. Nuclear Regulatory Commission P. O. Box 218 Brownville, NE 68321 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington,TX 76011 Ms. Cheryl Rogers, LLRW Program Manager Division of Radiological Health Nebraska Department of Health 301 Centennial Mall, South P. O. Box 95007 Lincoln, NE 68509 5007 Mr. Ronald A. Kucera, Department Director of Intergovernmental Cooperation Department of Natural Resources P.O. Box 176 l
Jefferson City, MO 65102
9:
REQUEST FOR ADDITIONAL INFORMATION COOPER NUCLEAR STATION RESPONSE TO GENERIC LETTER 95-07.
" PRESSURE-LOCKING AND THERMAL-BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES" 1
1.
Are there any conditions when high pressure coolant injection (HPCI) valve, HPC-MO14, would be required te men when pressure in the valve's bonnet is greater than upstream or downstream prassure? If so, is this valve susceptible te pressure locking and are other valves in the HPCI steam lines susceptible to pressure locking during surveillance testing?
2.
The 180-day Generic Letter 95-07 submittal states that testing demonstrated that HPCI suppression pool suction valve, HPCI-MOV-MO58, is not susceptible to pressure locking due to increased ambient room temperatures. Please describe the test, how the test demonstrates the valve is not susceptible to pressure locking, accident room temperatures, and room temperatures during the test.' Testing and operational experience are not generally acceptable corrective actions for pressure locking because valve leakage rates are not predictable. Explair, why leakage rates for this valve are predictable. Also discuss how this testing demonstrates that the valve will operate during pressure locking conditions with reduced voltage to the actuator.
3.
Explain if suppression pool cooling loop isolation valves, RHR-MOV-MO39A and RHR-MOV-MO398, are susceptible to pressure locking following operation of ths residual heat removal (RHR)/ low pressure safety injection (LPSI) system in the shutdown cooling, pump testing, or injection modes. Ate the bonnets of these valves pressurized from the RHR/LPSI pump then required to open later at a lower pump discharge pressure?
4.
Discuss if LPSI injection va'ves, RHR-MOV-MO25A and RHR-MOV-MO258, are susceptible to thermal binding following operation of the RHR system in the plant heatup mode of operation. Are these valves closed after securing RHR during heatup of the unit and then required to automatically open after the valves have cooled down?
Enclosure