ML062350572
| ML062350572 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/23/2006 |
| From: | Kobetz T NRC/NRR/ADRO/DIRS/ITSB |
| To: | Terao D NRC/NRR/ADRO/DORL/LPLIV |
| Hearn, P, NRR/DIRS, 301-415-1189 | |
| References | |
| TAC MD2030, TSTF-491 | |
| Download: ML062350572 (5) | |
Text
August 23, 2006MEMORANDUM TO:David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
/RA/FROM:Timothy J. Kobetz, Chief Technical Specifications Branch Division of Inspection and Regional Support
SUBJECT:
SAFETY EVALUATION INPUT FOR CALLAWAY PLANTAMENDMENT TO ADOPT TSTF-491 The Technical Specifications Branch (ITSB) has completed its plant-specific safety evaluation(SE) in response to submittal of AmericanEU of 06/18/2006, which requested adoption of TSTF-491. ITSB found the licensee's submittal acceptable. This completes ITSB's work on TAC number MD2030. Based on previous approvals ofamendments adopting TSTF-491, ITSB does not recommend routing the final amendmentpackage through the Office of General Counsel.CONTACT:P. C. Hearn, DIRS/ITSB(301) 415-1189 August 23, 2006MEMORANDUM TO:David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
/RA/FROM:Timothy J. Kobetz, Chief Technical Specifications Branch Division of Inspection and Regional Support
SUBJECT:
SAFETY EVALUATION INPUT FOR CALLAWAY PLANTAMENDMENT TO ADOPT TSTF-491 The Technical Specifications Branch (ITSB) has completed its plant-specific safety evaluation(SE) in response to submittal of AmericanEU of 06/18/2006, which requested adoption of TSTF-491. ITSB found the licensee's submittal acceptable. This completes ITSB's work on TAC number MD2030. Based on previous approvals ofamendments adopting TSTF-491, ITSB does not recommend routing the final amendmentpackage through the Office of General Counsel.CONTACTS:P. C. Hearn, DIRS/ITSB(301) 415-1189Distribution
- ITSB RFTKobetzPCHearnAccession Number: OFCDIRS/ITSBDCI/CPTB/BCDIRS/ITSB/BCNAMEPHearnTYLIUTKobetz DATE08/23/200608/22 /2006 08/23/2006Official Record Copy EnclosurePROPOSED SAFETY EVALUATIONU.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationTechnical Specification Task Force (TSTF) Change Traveler TSTF-491, Removal of Main Steam and Feedwater Isolation Times1.0 IntroductionBy letter dated May 11, 2006, AmericanUE (the licensee) proposed changes to the technicalspecifications (TS) for the Callaway Plant. The requested changes are the adoption of TSTF-491, Revision 2, "Removal of Main Steam and Feedwater Valve Isolation Times" which was proposed by the Technical Specification Task Force (TSTF) by letter on May 18, 2006.
The proposed changes would revise Technical Specification 3.7.2 " Main Steam Isolation Valves (MSIVs)" and 3.7.3 "Main Feedwater Isolation Valves (MFIVs), Feedwater Regulating Valves (MFRVs) and Main Feedwater Regulating Valve Bypass Valves. (MFRVBVs)." The proposed TSTF would allow relocating the isolation valve closure times to the Bases.2.0 Regulatory Evaluation Section 182a of the Atomic Energy Act (the "Act") requires applicants for nuclear power plantoperating licenses to include TS as part of the license. The TS ensure the operational capability of structures, systems and components that are required to protect the health andsafety of the public. The Commission's regulatory requirements related to the content of theTS are contained in 10 CFR Section 50.36. That regulation requires that the TS include itemsin the following specific categories: (1) safety limits, limiting safety systems settings, andlimiting control settings (50.36(c))(1)); (2) Limiting Conditions for Operation (50.36(c))(2));(3) Surveillance Requirements (50.36(c))(3)); (4) design features (50.34(c))(4)); and(5) administrative controls (50.36(c))(5)).In general, there are two classes of changes to TS: (1) changes needed to reflect modificationsto the design basis (TS are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferredformat of TS over time. This amendment deals with the second class of changes. In determining the acceptability of revising STS 3.7.2 and 3.7.3, the staff used the accumulationof generically approved guidance in; NUREG-1431, Revision 3, "Standard TechnicalSpecifications, Westinghouse Plants," dated June, 2004.Licensees may revise the TS to adopt current improved STS format and content provided thatplant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (i.e., no requirements are materially altered),
(2) the change is more restrictive than the licensee's current requirement, or (3) the change is less restrictive than the licensee's current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed applicationof this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes.
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the justification for the proposed TSTF as described in the May 18,2006, submittal. The detailed evaluation below will support the conclusion that: (1) there isreasonable assurance that the health and safety of the public will not be endangered byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendment will not be inimical to thecommon defense and security or to the health and safety of the public.3.1 Main Steam Isolation Valves (MSIV)One MSIV is located in each main steam line outside of the containment. Closing the MSIVsisolates each steam generator from the others and isolates the turbine, steam bypass systemand other auxiliary steam supplies from the steam generator.By isolating the steam flow from the secondary side of the steam generator the MSIVs preventover cooling the reactor core following a high energy line break (HELB). By preventing core overcooling the MSIVs protect the reactor core from being damaged. TSTF-491 is proposing to relocate the required closure times for the MSIVs to the Bases. Changes to Bases are subject to the 10 CFR 50.59 process. The 10 CFR 50.59 criteria provide adequate assurance that prior staff review and approval will be requested by the licensee forchanges to the Bases requirements with the potential to affect the safe operation of the plant. Furthermore, the MSIVs are subject to periodic testing and acceptance criteria in accordance with the Inservice Testing (IST) Program. Compliance with the IST Program is required by Section 5.5.7 of the Standard Technical Specifications (STS) and 10 CFR 50.55. The ISTProgram includes specific reference value baseline operating times for valves that are not subject to arbitrary changes. 10 CFR 50.36 requires the inclusion of the periodic testing of the MSIVs in the SurveillanceRequirements not the actual closure time of the valves. TSTF-491 change maintains the periodic testing requirements for MSIVs in accordance with 10 CFR 50.36.Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and IST Program, the staffconcludes that relocating the MSIV closure time to the Bases is acceptable.3.2Main Feedwater Isolation Valve (MFIV), Main Feedwater Regulation Valve (MFRV) and Main Feedwater Regulation Valve Bypass Valves (MFRVBV)The MFIVs or the MFRVs and MFRVBVs isolate the nonsafety related portions from the safetyrelated portions of the system. In the event of a secondary side pipe rupture insidecontainment, these valves limit the quantity of high energy fluid that enters the containmentthrough the break and provide a pressure boundary for the controlled addition of auxiliaryfeedwater to the intact loops. By isolating the feedwater flow from the affected steam generator the MFIVs, MFRVs andMFRVBVs prevent overcooling the reactor core and over pressurizing of the containment from feedwater pump runout.As with the MSIVs, TSTF-491 is also proposing to relocate the required closure times for theMFIVs, MFRVs and MFRVBVS to the Bases. Changes to the Bases are subject to the 10 CFR 50.59 process. The 10 CFR 50.59 criteria provide adequate assurance that prior staff review and approval will be requested by the licensee for changes to the Bases requirementswith the potential to affect the safe operation of the plant. Furthermore, the MFIVs, MFRVs andMFRVBVs are subject to periodic testing and acceptance criteria in accordance with the Inservice Testing (IST) Program. Compliance with the IST Program is required by Section 5.5.7 of the Standard Technical Specifications (STS) and 10 CFR 50.55. The ISTProgram includes specific reference value baseline operating times for valves that are not subject to arbitrary changes. 10 CFR 50.36 requires the inclusion of the periodic testing of the MFIVs, MFRVs andMFRVBVs in the Surveillance Requirements not the actual closure time of the valves. TSTF-491 maintains the periodic testing requirements for MFIVs, MFRVs and MFRVBVs in accordance with 10 CFR 50.36.Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and the IST Program, the staffconcludes that relocating the MFIVs, MFRVs and MFRVBVs closure times to the Bases is acceptable.
4.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there isreasonable assurance that the health and safety of the public will not be endangered byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendment will not be inimical to thecommon defense and security or to the health and safety of the public. Proposed No Significant Hazards Consideration Determination Description of Amendment Request:
Callaway Plant requests adoption of an approved change to the standard technical specifications (STS) for Westinghouse PWR STS Revision 3.0 of NUREG-1431 plant specifictechnical specifications (TS), to allow relocating the main steam and main feedwater isolation valve closure times to the Bases. The changes are consistent with NRC approvedIndustry/Technical Specification Task Force (TSTF) Standard Technical Specifcation Change Traveler, TSTF-491, Revision 2.