ML20199C315
| ML20199C315 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/10/1997 |
| From: | Wharton L NRC (Affiliation Not Assigned) |
| To: | Gambhir S OMAHA PUBLIC POWER DISTRICT |
| References | |
| GL-96-06, GL-96-6, TAC-M96813, NUDOCS 9711190302 | |
| Download: ML20199C315 (4) | |
Text
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-g pa argk UNITED STATES -
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WASHINGTON, D.C. annas anni o\\ *****/
November 10, 1997-
-Mr. S. K. Gambhir Division Manager - Engineering & Operations Support Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 399 iky. 75 - North of Fort Calhoun Fort Calhoun Nebraska 68023 0399
SUBJECT:
Itlc0RMATION PERTAINING TO FORT CALHOUN STATION IMPLEMENTATION OF MODIFICATIONS ASSOCIATED WITH GENERIC LETTER 96-06. " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DF 'NG DESIGN BASIS ACCIDENT CONDITIONS" (TAC NO. M96813)
Dear Mr. Gamb.11r:
The staff issued Genere Letter (GL) 96-06 on September 30, 1996. 'The generic letter requested licewees 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 over>ressurization of piping could occur.
By letter dated January 24, 1997. you su)mitted your 120-day response to GL 96-06. The staff is currently performing a detailed review of your response.
Implementing corrective actions to resolva the GL 96-06 issues can have a significant impact on outage schedules and resources.
Some licensees have indicated that it would be pr dent to take more time to better understand the specific concerns that have,"een 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 r.ontained 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 of pi ing issue, and (4)pport a generic resolution of the overpressurization Research Institute to su questions regarding the staff's closure of Generic Safet Issue 150 "0verpressurization of Containment Penetrations." Risk M
insig ts and industry initiatives that are being considered or that may be IN{
proposed could also influence the course of action that licensees take to
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resolve the GL=96-06 issues.
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Mr.'S. K. Gambhir November 10, 1997 License?s are res>onsible for assessing equipment operability, determining actions, and esta)lishing senedules 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 s)ecific nonconformances or degraded conditions that have been identified. risc insights, and the time required to complete any generic initiatives and/or )lant-specific actions (e.g., engineering evaluations. design c1ange 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 Ill. 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 find the revised guidance contained in GL 91-18. "Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolutio') 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 staff's current position that licensees can use the ASME Code.
Section Ill. Appendix F. criteria for-interim operability determinations for degraded and nonconforming piping and )ipe supports until oermanent actions have been identified and approved by tie NRC (as applicabl') for resolving the e
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 )ublic worksho) on this topic later this fall.
The workshop proceedings will 3e summarized )y 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 96-06 issues, you should submit a revised response to the generic letter.
Your revised response should include appropriate discussion of the considerations
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- 3- -t 1 November =10, 1997c discussed above 'the current resolution status; a'nd: actions-remaining:to be completed.tand plans being considered-for_ final resolution ~ofithe GL-96 :
-issues, Ifyouha'veanyquestions,lplease-contactmea$(301)---415'1396.
Sincerely, Opidinal Signed By'-
L;=Raynard Wharton,_ Project Manager Project = Directorate IV - '
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Division of-Reactor Projects - III/IV-Office rf Nuclear Reactor Regulation Docket No. 50-285 0"STR'BUTION:
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. November 10,-1997--
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ATTN:
Perry D.-Robinson, Esq.-
1400~L Street, N.W.
Washington. DC =20005-3502 Mr. Jack Jensen. Chairman Washington County Board of Supervisors ~
Blair, Nebraska -68008 Mr. Wayne Walker, Resident Inspector-U.S. Nuclear Regulatory Comission Post Office Box 309-
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- Fort Calhoun. Nebraska-68023-Regional Administrator, Region-IV U.S. Nuclear Regulatory Comission 611 Ryan Plaza Drive. Suite 1000 Arlington, Texas-76011 Ms. Cheryl Rodgers, LLRW Program Manager Environmental Protection Section
- Nebraska Department of Health 301 Centennial Hall, South P.O. Box 95007
- Lincoln,' Nebraska 68509-5007 Mr.-James W.! Chase, Manager Fort-Calhoun Station
' Post Office Box 399 Fort Calhoun.-Nebraska 68023
- Mr.-James W. Tills
. Manager - Nuclear. Licensing Omaha Public Power' District Fort Calhoun Station FC-2-4 Adm.
- Post Office Box 3991 Hwy. 75 --North of Fort Calhoun Fort Calhoun. Nebraska 68023-0399 q
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