ML20198Q528
| ML20198Q528 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/04/1997 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | Grigg R WISCONSIN ELECTRIC POWER CO. |
| References | |
| GL-96-06, GL-96-6, TAC-M96852, TAC-M96853, NUDOCS 9711120239 | |
| Download: ML20198Q528 (3) | |
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November 4, 1997 Mr. Richard R. Grigg Chief Nuclear Officer Wisconsin Electric Power Company 231 West Michigan Street, Room P379 Milwaukee, WI 53201
SUBJECT:
INFORMATION PERTAINING TO POINT BEACH NUCLEAR PLANT'S IMPLEMENTATION OF MODIFICATIONS ASSOCIATED WITH GENERIC LETTER 96-06, " ASSURANCE OF EQUlPMENT OPERABILITY /AD CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS"(TAC NOS, M96852 AND M96853)
Dear Mr. Grigg:
The staff issued Generic Letter (GL) 96-06 on September 30,1996. The gener:c letter requested licensees to determine (1) if containment air cooler cooling water systems are susceptible to either waterhammer or two-phase flow conditions during postulated accident conditions, and (2) if piping systems that penetrate the containment are susceptible to thermal expansion of fluid so that overpressurization of piping could occur. By letters dated January 28,1997, as supplemented on June 25,1997, you submitted your 120-day response to GL 96-06. The staff is currently performing a detailed review of your response.
r implementing corrective actions to resolve the GL 96-06 issues can have a significant impact on outage schedules and resources. Some licensees have indicated that it would be pruden'.
to take more time to better understand the specific concems that have been identified in order to optimize whatever actions are needed and to assure that they do not ultimately result in a detriment to safety. Current issues and ongoing efforts that could influence a licensee's decision in planning corrective actions include (1) risk implications of installing relief valves to deal with the thermal overpressurization issue, (2) feasibility of using the acceptance criteria contained in Appendix F to Section ll! of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the permanent resolution of the GL 96-06 issues, (3) ongoing tests by the Electric Power Research Institute to support a generic resolution of the overpressurization of piping issue, and (4) questions regarding the staff's closure of Generic Safety Issue 150,"Overpressurization of Containment Penetrations." Risk insights and industry initiatives that are being considered or that may be proposed could also influence the course of action that licensees take to resolve the GL 96-06 issues.
4 Licensees are responsible for assessing equipment operability, determining actions, and i
establishing schedules that are appropriate for resolving the specific conditions that have been identified. In determining the appropriate actions and schedules for resolving GL 96-06 issues, licensees should consider, for example, the continued validity of existing operability g Q j
determinations, compensatory actions required to maintain operability, the safety significance associ&ted with the specific nonconformances or degraded conditions that have been identified, risk insights, and the time required to complete any generic initiatives and/or plant-specific actions (e.g., engineering evaluations, design change packages, material procurement, and equipmerd modification and installation). Also, analytical solutions employing the permanent use of the acceptano criteria contained in the ASME Code, 9711120239 971104 i
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R. R. Grigg -
Novenber 4, 1997 Section lil, Appendix F (or other acceptance criteria) may present viable attematives to plant modifications and can be used where appropriate, justified, and evaluated in accordance with NRC requirements such as 10 CFR 50.59, as applicable. Licensees may find the revised guidance contained in GL 91-18, "Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability," Revision 1, dated October 8,1997, helpfulin determining appropriate actions and schedules. Although adjustments in schedules may be war anted on the basis of these (and other) considerations, specific actions that have been defined and are clearly needed should not be delayed without suitable justification.
It is the staf's current position that licens'.Ls can use the ASME Code, Section Ill, Appendix F, criteria for interim operability determinations for degraded and nonconforming piping and pipe supports until permanent actions have been identified and approved by the NRC (as applicable) for resolving the GL 96-06 issues. This guidance supplements the guidance provided by GL 91-18 for resolution of the GL 96-06 issues.
In order to further facilitate resolution of the GL 96-06 issues, the NRC will participate in a public workshop on this topic later this fall. The workshop proceedings will be summarized by the NRC staff and made publicly available. The need for additional NRC guidance and generic communication will be considered upon completion of the workshop.
If you choose to revise your commitments for resolving the GL 06-06 issues, you should submit a revised response to the generic letter. Your revised response should include appropriate discussion of the considerations discussed above, the current resolution status, and actions remaining to be completed, and plans being considered for final resolution of the GL 96-06 issues.
If you have any questions, please contact me at 301415-1380.
Sincerely, ORIGINAL SIGNED BY Linda L. Gundrum, Project Manager Project Directorate 111-1 Division of Reactor Projects - lil/IV i
Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301 cc: See next page DISTRIBUTION:
Docket File PUBLIC PDill-1 Reading E. Adensam C. Jamerson L. Gundrum OGC ACRS J. McCormick-Barger, Rill B. Wetzel, LPM L. Marsh, SPLB DOCUMENT NAME: G:\\WPDOCS\\PTBEACH\\PTB96852.LTR Ta receive e cray of this document, indcate in the bos: 'C' = Copy mthreut attachment / enclosure "E' = Copy wth attachment / enclosure 'N' = No copy l0FFICE PM:PD31 E
LA:PD31 kl,E 0:PD31 e w),I lNAME LGundrum: 44J CJamerson CNY J!:annon1W lDATE i 11/ 4 /97 11/ 4 /97 0
11/ 4 /97 0FFICIAL RECORD COPY
-d Mr. Richard R. Grigg Point Beach Nuclear Plant Wisconsin Electric Power Company-Unit Nos.1 and 2 cc:
Emest L. Blake, Jr.
Shaw, Pittman, Po:ts & Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mr. Scott A. Patuiski Vice President Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Mr. Ken Duveneck Town Chairman Town oiTwo Creeks 13017 State Highway 42 Mishicot, Wisconsin 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, W;sconsin 53707-7854 Regional Administrator, Region lil U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, Wisconsin 54241 Ms. Sarah Jenkins 1
Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 March 1H7 u