ML17292B112
| ML17292B112 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 11/12/1997 |
| From: | Colburn T NRC (Affiliation Not Assigned) |
| To: | Parrish J WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| GL-96-06, GL-96-6, TAC-M96886, NUDOCS 9711190202 | |
| Download: ML17292B112 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 November 12, 1997
~d-sp7 Mr. J.
V. Parrish Chief Executive Officer Washington Public Power Supply System P.O.
Box 968 (Mail Drop 1023)
Richland.
Washington 99352-0968
SUBJECT:
INFORMATION PERTAINING TO WASHINGTON PUBLIC POWER SUPPLY SYSTEM IMPLEMENTATION OF MODIFICATIONS ASSOCIATED WITH GENERIC LETTER 96-06.
"ASSURANCE OF EQUIPMENT OPERABILITY,AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS" (TAC NO. M96886)
Dear Hr. Parrish:
The staff issued Generic Letter (GL) 96-06 on September 30, 1996.
The generic 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 May 29, 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 (ASHE 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 ot 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.
97iii90202 97iii2 PDR ADOCK 05000397 P
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Hr. J.
V. Parrish November 12, 1997 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 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 equipment modification and installation).
Also,.analytical solutions employing the permanent use of the acceptance criteria contained in the ASNE Code,Section III. Appendix F (or other 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 tind 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 statf's current position that licensees can use the ASNE 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 will participate in a public workshop on this topic later this fall.
The workshop proceedings will be summarized by the NRC staff'nd 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 96-06 issues, you should submit a revised response to the generic letter.
Your revised response should include appropriate discussion of the considerations
Mr. J.
V. Parrish November 12, 1997 discussed
- above, the current resolution status, and actions remaining to be completed, and plans being considered for final resolution ot the GL 96-06
'issues.
If you have any questions, please contact me at (301) 415-1341.
Sincerely, Original Signed By Timothy G. Colburn, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects
- III/IV Office of Nuclear Reactor Regulation Docket No. 50-397 cc:
See next page DISTRIBUTION:
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Hr. J.
V. Parrish November 12, 1997 CC:'r. Greg 0. Smith (Mail Drop 927M)
WNP-2 Plant General Manager Washington Public Power Supply System P. 0.
Box 968 Richland.
Washington 99352-0968 Hr. Albert E. Mouncer (Hail Drop 1396)
Chief Counsel Washington Public Power Supply System P.O.
Box 968
- Richland, Washington 99352-0968 Hr. Frederick S. Adair. Chairman Energy Facility Site Evaluation Council P. 0.
Box 43172 Olympia, Washington 98504-3172 Hr. David A. Swank (Nail Drop'PE20)
- Manager, Regulatory Affairs Washington Public Power Supply System P.O.
Box 968
- Richland, Washington 99352-0968 Hr. Paul Inserra (Hail Drop PE20)
- Manager, Licensing 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 Nr. Rodney L. Webring (Hail Drop PE08)
Vice President, Operations Support/PIO Washington Public Power Supply System P. 0.
Box 968
- Richland, Washington 99352 Nr. Scott Boynton, Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O.
Box 69
- Richland, Washington 99352-0968 Mr. Perry D. Robinson, Esq.
Winston 8 Strawn 1400 L Street, N.W.
DC 20005-3502