ML20059H945
| ML20059H945 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 11/04/1993 |
| From: | Simpkin T COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20059H949 | List: |
| References | |
| NUDOCS 9311100275 | |
| Download: ML20059H945 (6) | |
Text
{{#Wiki_filter:F [- ) Commonwrith Edison 4 -{ 1400 Opus Place - Downer. Grove, !!!inois 60515 November 4,1993 Dr. Thomas E. Murley, Director - Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission L Washington, DC.20555 -t l-Attn: Document Control Desk a
Subject:
Zion Station Units 1 and 2 Application for Amendment to Facility Operating License DPR-39 and DPR-48 NRC Docket Nos. 50-295 and 50-304
- j i
Dear Dr. Murley:
Pursuant to 10 CFR 50.90, Commonwealth Edison (CECO) proposes to amend Appsndix A, Technical Specification of Facility Operating License DPR-39 and DPR-48. The proposed amendment changes Specification 4.7.1.A, Steam Generator Safety Valves, to revise the surveillance frequency and acceptance criteria. A detailed description and evaluation of the proposed change is presented in Attachment A. The revised Technical Specification pages are contained in Attachment B. The proposed change had been reviewed and approved by both on-site and off-site review..
- in accordance with CECO procedures. CECO has reviewed this proposed amendment in' accordence with 10 CFR 50.92(c) and has determined that no significant hazards consideration exists. This evaluation is documented in Attachment C. An Environmental Assessment has been completed and is contained in Attachment D.
CECO is notifying the State of Illinois of our application for this amendment by transmitting a copy of this letter and its attachments to the designated State Official. -. i 100040 f k:\\mnsvlar.wpf /1 [I -9311100275 931104' F3 / i PDR ADOCK 05000295 De I P PDR.Q .}j y
l i Dr. T.E Murley November 4,1993 i To the best of my knowledge and belief the statements contained herein are true and correct. In some respects, these statements are not based on my personal knowicdge but upon information received from other Commonwealth Edisca and contractor employees. Such information has been reviewed in accordance with Company practice and I believe it to be reliable. Please direct any questions regarding this oratter to this office. Sincerely, m M. M T.W. Simpkin ' NuclearUcensingMministrator Attachments cc: J.B. Martin - Region 111 i C.Y. Shiraki - Project Manager, NRR J.D. Smith - Senict Resident inspector, Zion l Office of Nuclear Facility Safety-IDNS j 4 / r state of County of e[ n#/ wwww " OFFICI AL SEAL-s gned t>ct we me on th s EI day S AfJDR A C.LARA Ofd.!!2f *'d sb by 7/v / fiDTMY R !ir. STATE Or tLLINO:s i q' ' .. ;p' MY CON"/iSEj0_'; DF;cE S c/pSfg4 s ~ futary PubMel' N" NM3 [~ e N k:\\rsavlar.wpf/2
l F ATTACHMENT A ZION NUCLEAR GENERATING STATION DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS OF FACILITY OPERATING LICENSES DPR-39 AND DPR-48 REVISION OF THE MAIN STEAM SAFETY VALVE SURVEILLAtlCE REQUIREMENTS i k:\\msevlar.wTf/3 m
DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGES TO APPENDIX A l TECHNICAL SPECIFICATIONS OF FACluTY OPERATING UCENSES DPR-39 AND DPR-48 ? F A. DESCRIPTION OF THE PROPOSED CHANGE: The proposed change is being submitted to implement testing of the Main Steam Safety Valves (MSSVs) in accordance with the Zion station Inservice Testing (IST) Plan. The test frequency and detailed instructions of Specification 4.7.1.A, Steam Generator Safety Valves per unit, have been replaced with the requirement that the MSSVs be tested pursuant to Specification 4.0.5. Specification 4.0.5 requires the testing of ASME Code Class 1.,2, and 3 pumps and valves be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required in 10CFR50.55a(g). The Zion station IST Plan. and implementing procedures satisfy the ASME Boiler and Pressure Vessel Code testing requirements except where specific relief has been granted by the NRC pursuant to 10CFR50.55a(g). The proposed change results in the MSSVs being tested in accordance with Part 1 of the ASME/ ANSI OM-1987 (Requirements for Inservice Performance Testing of Nuclear Power Plant Pressure Relief Devices). The proposed change is also consistent with the Westinghouse Standard Technical Specifications as presented in NUREG-1431. B. CURRENT REQUIREMENTS: The primary purpose of the MSSVs is to provide overpressure protection for the secondary system. The MSSVs also provide protection against overpressurizing the Reactor Coolant System by providing a heat sink for the removal of energy if the preferred heat sink, provided by the condenser and Circulating Water System, is not available. In order for the MSSVs to provide the required overpressure protection, the valves must open within the setpoint tolerances, relieve steam generator pressure and reseat when pressure is reduced. The operability of the MSSVs is determined by periodic surveillance testing in accordance with the Technical Specifications. The current testing requirements for MSSVs are stated in Technical Specification Surveillance 4.7.1.A and associated Table 4.7-1. Ten of the 20 MSSVs per unit are required to be tested at each refueling such that all valves are tested by the end of the second refueling (nominally 36 4 months). The acceptable test methods are also specified (e.g. calibrated auxiliary lifting device l or bench testing with compressed gas). In addition, to assure a representative sample, the Specification requires that at least two valves from each orifice size are tested. The orifice sizes, setpoints, and the required i 1% tolerance are specified in Table 4.7-1. i i i l i ki\\mssviar.wpf/4 1
i C. REQUESTED REVISION: T The Technical Specifications require testing of ASME Code Class 1,2, and 3 pumps and valves . in accordance with the IST Plan by applying Specification 4.0.5 in the Surveillance Requirements. The proposed change replaces the current requirements of specification.4.7.1.A with the ~' requirement to test the MSSVs pursuant to Specification 4.0.5. Compliance with Specification 4.0.5 results in the application of Part 1 of the ASME/ ANSI OM-1987 Standard to MSSV testing as required by the recently submitted Zion Third-Ten Year IST-Plan and implementing procedures. This Standard provides general requirements for performance testing and monitoring of nuclear power plant pressure relief devices. The Standard establishes methods, intervals, and record requirements for monitoring and testing, as well as guidelines for the evaluation of results. The Standard requires all MSSVs to be tested every 5 years and a minimum sample population (20%) to be tested every 24 months. If, during the testing of the required 20% sample population, the stamped set pressure criteria of a valve is exceeded by 3% or more, the Standard specifies that the sample population of valves be expanded. The additional testing can include up to 100% of the remaining MSSVs if the additional valves tested continue to exceed the stamped set - j pressure criteria by 3% or more. l The proposed change also replaces the i 1% tolerance specified for set pressure on Table 4.7-1 with 3%. The revised tolerance is consistent with the ASME/ ANSI OM-1987 Standard and 'I NUREG-1431, Standard Technical Specifications for Westinghouse Plants. The proposed change also contains a requirement that specifies the lift settings of the MSSVs tested shall be left within i 1% of the required value after testing is complete. This requirement ~ is not specified in the ASME/ ANSI OM-1987 Standard, but is consistent with NUREG-1431, Standard Technical Specifications for Westinghouse Plants. D. IMPACT OF THE PROPOSED CHANGE: The proposed change replaces the existing Specification 4.7.1.A with the requirement to test the MSSVs in accordance with, and at a frequency specified by, the IST Plan. This results in the application of Part 1'of the ASME/ ANSI OM-1987 Standard to MSSV testing. The application of the ASME/ ANSI Standard results in a relaxation of the surveillance test interval'. for the MSSVs. The current Technical Specification requires that 10 MSSVs be tested each -' i refueling such that 100% of the MSSVs are tested at the end of the second refueling outage (nominally 36 months). The ASME/ ANSI Standard requires all MSSVs to be tested every 5 years. i and a minimum sample population (20%) to be tested every.24 months. The Standard does. however, require additional valves be tested (up to 100% of the remaining MSSVs) if the stamped set pressure criteria of the valve (s) being tested is exceeded by 3% or more. The current ' Technical Specification requirement to assure that at least two MSSVs of each orifice size are tested is also relaxed. The ASME/ ANSI Standard has no requirements related to the orifice size - of the valves tested. h K: Wssvlar.wpt/5
I D. IMPACT OF THE PROPOSED CHANGE: (Continued) While the proposed changes regarding surveillance intervals and orifice size requirements described above represent a relaxation in the requirements applicable to Zion station, these l changes are consistent with the applicable industry standard. The ASME/ ANSI Standard has been applied extensively throughout the industry and demonstrated adequate by the resulting industry experience. The effect of allowing the Zion station MSSV lift setpoint tolerance to increase frc.m the currently required 11% to the 13% consistent with the ASME/ ANSI Standard has been evaluated for all non-LOCA and LOCA design basis requirements. The 13% tolerance for the MSSV setpoints was assumed in the VANTAGE 5 Reload Transition Safety Report for the Zion Units 1 and 2. The VANTAGE 5 Reload Transition Safety Report has been previously reviewed and approved by the NRC in conjunction with license amendments 139/128. In all cases, either a reanalysis incorporating the increased MSSV setpoint tolerance was performed and showed results to be. within the acceptance limits, or the increased MSSV setpoint tolerance was determined not to affect the licensing basis results. i The relocation of the specific testing requirements for the MSSVs to the Zion station IST plan and implementing procedures ensure that an equivalent level of operational readiness is provided for the MSSVs. Adequate control of MSSV testing specified in the IST Plan and implementing procedures is provided by the ASME Section XI requirements pursuant to 10CFR 50.55a(g) and. the required 10CFR50.59 review process. E. lMPLEMENTATION SCHEDULE: it is requested that this amendment be effectwe as of its issuance and be implemented within 30 dayr, from the date of issuance. In order to support the required MSSV testing for the next Unit 2 refueling outage, this amendment is requested by June of 1994. t f i k 2 \\mssvl a r ap f n o}}