ML17059B771
| ML17059B771 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/12/1997 |
| From: | Hood D NRC (Affiliation Not Assigned) |
| To: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| References | |
| GL-96-06, GL-96-6, TAC-M96837, NUDOCS 9711190165 | |
| Download: ML17059B771 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 12, 1997 Mr. B. Ralph Sylvia Executive Vice President Generation Business Group and Chief Nuclear Officer Niagara Mohawk Power Corporation Nuclear Learning Center 450 Lake Road Oswego, NY 13126
SUBJECT:
INFORMATIONPERTAINING TO NINE MILEPOINT NUCLEAR STATION UNIT2 IMPLEMENTATIONOF MODIFICATIONSASSOCIATED WITH GENERIC LETTER 96-06, "ASSURANCE OF EQUIPMENT OPERABILITYAND CONTAINMENTINTEGRITYDURING DESIGN-BASIS ACCIDENTCONDITIONS" (TAC NO. M96837)
Dear Mr. Sylvia:
The staff issued Generic Letter (GL) 96-06 on September 30, 1996. The generic letter requested licensees to determine (1) ifcontainment air.cooler cooling water systems are susceptible to either waterhammer or two-phase flow conditions during postulated accident conditions, and (2) ifpiping systems that penetrate the containment are susceptible to thermal expansion of fluid so that overpressurization of piping could occur.
By letter dated Jebruary 7, 1997, you submitted your 120-day response to GL 96-06. The staff is currently performing a detailed review of your response.
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 prudent to take more time to better understand the specific concerns 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 III 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 staffs 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.
Licensees are responsible for assessing equipment operability, determining actions, and 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 determinations, compensatory actions required to maintain operability, the safety significance associated with the specific nonconformances or degraded conditions that have been identified, risk insrghts, and the time required to complete any generic initiatives and/or plant-specific actions (e.g., engineering evaluations, design change packages, material procurement, and equipment modification and installation). Also, analytical solutions employing the permanent use of the acceptance criteria contained in the ASME Code,Section III, Appendix F (or other pooh Xoock ooooo%<o Illltlllllllllllllllll IIIIIIIIIIIIIIIIIpimIg Flyer gpggp
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B. Ralph Sylvia acceptance criteria) may present viable alternatives 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, helpful in determining appropriate actions and schedules.
Although adjustments in schedules may be warranted on the basis of these (and other) considerations, specific actions that have been defined and are dearly needed should not be delayed without suitable justification.
It is the staffs current position that licensees can use the ASME Code,Section III,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 willparticipate in a public workshop on this topic later this fail. The workshop proceedings willbe summarized by the NRC staff and made publicly available. The need for additional NRC guidance and generic communication willbe considered upon completion of the workshop.
Ifyou choose to revise your commitments for resolving the GL 96-06 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.
Ifyou have any questions, please contact me at (301) 415-3049.
Sincerely, Darl S. Hood, Proj t Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-410 cc: See next page
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I November 12 97 B. Ralph Sylvia acceptance criteria) may present viable alternatives to plant modifications and can be used where appropriate, justiTied, 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, helpful in determining appropriate actions and schedules.
Although adjustments in schedules may be warranted 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 staffs current position that licensees can use the ASME Code,Section III, 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 willparticipate in a public workshop on this topic later this fall. The workshop proceedings willbe summarized by the NRC staff and made publicly available. The need for additional NRC guidance and generic communication willbe considered upon completion of the workshop.
Ifyou choose to revise your commitments for resolving the GL 96-06 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.
Ifyou have any questions, please contact me at (301) 415-3049.
Docket No. 50410 cc: See next page DISTRIBUTION:See next page DOCUMENT NAME:G:>NMP21/I96837.LTR Since<<iy Original Signed by I Karen Cotton for Oar 1 S.
Hood Darl S. Hood, Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" =
Cop with attachment/enclosure "N"= No co OFFICE PH:PDI-1 IIAME DHOOD/LCC E
LA:PDI 1
SLITTLE D:PDI-1 S.
Ba Ma DATE 11/
97 11/
/97 11/ 1497 Official Record Copy
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B. Ralph Sylvia Niagara Mohawk Power Corporation CC:
Nine Mile Point Nuclear Station Unit 2 Hr,. Richard B. Abbott Vice President and General Manager Nuclear Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093 Hr. Carl D. Terry Vice President Nuclear Safety Assessment and Support Niagara Mohawk Power Corporation P.O.
Box 63
- Lycoming, NY 13093 Hs. Denise J. Wolniak Hanager Licensing Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093 Hr. Kim A. Dahlberg Vice President-Nuclear Operations Acting Unit 2 Plant Manager Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093 Hr. John T.
Conway Vice President-Nuclear Engineering Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation P.O.
Box 63
- Lycoming, NY 13093 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector Nine Mile Point Nuclear Station P.O.
Box 126
- Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Richard M. Kessel Chair and Executive Director State Consumer Protection Board 99 Washington Avenue
- Albany, NY 12210 Mark J. Wetterhahn, Esquire Winston 8 Strawn 1400 L Street, NW.
Washington, DC 20005-3502 Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, NY 13202 Hr. F. William Valentino, President New York State
- Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension
- Albany, NY 12203-6399 Supervisor Town of Scriba Route 8, Box 382
- Oswego, NY 13126 Hr. Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus
- Syracuse, NY 12223 Hr. John V. Vinquist, MATS Inc.
P.O.
Box 63
- Lycoming, NY 13093 Hr. Hartin J. HcCormick, Jr.
Vice President-Special Projects Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093
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B. Ralph Sylvia Niagara Hohawk Power Corporation CC:
Nine Hile Point Nuclear Station Unit 2 Hr. Jim Rettberg New York State Electric
& Gas Corporation Corporate Drive Kirkwood Industrial Park P.O.
Box 5224 Binghamton, NY 13902-5224
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DISTRIBUTION:
+Docket File PUBLIC'DI-1 R/F B. Boger S. Bajwa S. Little D. Hood M. P. Siemien, OGC (email MPS)
C. Hehl, Region I
B. Wetzel SPLB
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