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MONTHYEARULNRC-06331, Proposed Revision of Callaways FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (LDCN 16-0001)2017-04-0606 April 2017 Proposed Revision of Callaways FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (LDCN 16-0001) Project stage: Request ML17304B1912017-10-31031 October 2017 NRR E-mail Capture - Requests for Additional Information Concerning Callaway License Amendment - Thermal Overload Protection Project stage: RAI ML17300A2972017-11-0101 November 2017 Non-Acceptance of Relief Request RV-2 Related to Extension of Pressure Relief Valve Testing Intervals (Cac/Epid Nos. 000976/05000454/L-2017-LLR-0091 and 000976/05000455/L-2017-LLR-0091) Project stage: Acceptance Review ML17335A0442017-12-0404 December 2017 Tvel Lead Test Assembly 3rd Closed Meeting Project stage: Meeting L-17-372, Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088)2017-12-23023 December 2017 Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088) Project stage: Response to RAI ML18010A1742018-01-10010 January 2018 NRR E-mail Capture - Braidwood, Unit 2, Acceptance Review and Resource Estimate for Relief Request I4R-07 (Cac/Epid No. 000976/05000457/L-2017-LLR-0155) Project stage: Acceptance Review ML18018B4432018-01-25025 January 2018 Summary of December 17, 2017, Closed Meeting with Exelon Generation Company, LLC, Regarding Tvel Lead Test Assemblies to Be Placed in the Braidwood Reactor (EPID 000976/05000456/L-2017-LRM and 000976/05000457/L-2017-LRM-0047 Project stage: Meeting ML18036A6672018-02-0505 February 2018 Response to Request for Additional Information Concerning Proposed Revision of Callaway'S FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (LDCN 16-0001) Project stage: Request L-18-061, Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement2018-03-16016 March 2018 Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement Project stage: Response to RAI L-18-125, Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/02018-05-0202 May 2018 Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/0 Project stage: Request ML18129A3312018-05-0404 May 2018 Proposed Relief Request Associated with Reactor Pressure Vessel Nozzle Repairs Project stage: Request LG-18-068, Instrumentation Nozzle N-16D As-Left J-Groove Weld Analysis, Areva Document No. 32-9281804-000 (Non-Proprietary Version)2018-05-0404 May 2018 Instrumentation Nozzle N-16D As-Left J-Groove Weld Analysis, Areva Document No. 32-9281804-000 (Non-Proprietary Version) Project stage: Request ML18124A0262018-05-30030 May 2018 Issuance of Amendment No. 218 FSAR Revision Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection Project stage: Approval ML18156A4632018-06-0404 June 2018 Acceptance Review: Relief Request No. I4R-17, Revision 1, to Request Relief an Alternative to the Requirements in the ASME Code, Section XI (CAC No. 000976; EPID No. L-2018-LLR-0071) Project stage: Acceptance Review ML18221A6322018-08-15015 August 2018 Eicb Safety Evaluation - Comanche Peak Nuclear Power Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.2 Engineered Safety Feature Actuation System Instrumentation Docket/Epid 000976/05000446/L-2018-LLA-0 Project stage: Approval ML19256D4382019-09-10010 September 2019 Task Order No. 31310019F0035 Under Interagency Agreement No. 31310019N0001 Project stage: Other CNL-20-072, Tennessee Valley Authority - Bellefonte Nuclear Plant (Bln), Units 1 and 2 - Status Update and Request for Extension of Unit 1 Construction Permit CPPR-1222020-08-28028 August 2020 Tennessee Valley Authority - Bellefonte Nuclear Plant (Bln), Units 1 and 2 - Status Update and Request for Extension of Unit 1 Construction Permit CPPR-122 Project stage: Request ML20335A3932021-01-22022 January 2021 Bellefonte Nuclear Plant, Units 1 and 2 Extension of Construction Permit Expiration Dates (Cac/Epid Nos. 000976/05000438/L-2020-LLA-0214 and 000976/05000439/L 2020 Project stage: Other ML21014A3562021-01-22022 January 2021 Order - Extension of Construction Permits for Bellefonte Nuclear Plant, Units 1 and 2 Project stage: Request ML20335A3902021-01-22022 January 2021 Federal Register Notice - Order Approving the Extension of Bellefonte Units 1 and 2 Construction Permits Project stage: Request 2018-03-16
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Similar Documents at Byron |
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Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 1, 2017 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BYRON STATION, UNIT NOS. 1 AND 2, NONACCEPTANCE OF RELIEF REQUEST RV-2 RELATED TO EXTENSION OF PRESSURE RELIEF VALVE TESTING INTERVALS (CAC/EPID NOS. 000976/05000454/L-2017-LLR-0091 AND 000976/05000455/L-2017-LLR-0091)
Dear Mr. Hanson:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 25, 2017, Exelon Generation Company, LLC submitted a relief request to extend the test frequency for a limited number of pressure relief valves (PRVs) (i.e., 10 PRVs) from 48 months to 54 months to allow implementation of a "divisional outage strategy" during refueling outages, for the Byron Station, Unit Nos. 1 and 2.
The NRC staff has reviewed your application and concluded that your request is not necessary, because American Society of Mechanical Engineers (ASME) OM Code Case OMN-20 can be applied to extend the test intervals by up to 6 months. OMN-20 allows test intervals be extended 25 percent of the Code required frequencies up to but not to exceed 6 months.
OMN-20 was approved by the ASME OM Standard Subcommittee on February 15, 2012, and was later published in the 2012 Edition of the ASME OM Code. This Code Case was incorporated into 10 CFR 50.55a by reference and published in Federal Register (82 FR 32934) on July 18, 2017. The Code Case became effective on and after August 18, 2017, and can be implemented by licensees without NRC authorization.
ASME OM Code Case OMN-20 allows period extension to facilitate test scheduling in consideration of plant operating conditions that may not be suitable for performance of the required testing. In your September 25, 2017, letter you stated that the proposed relief would allow implementation of an outage strategy during refueling outages that maintains one division/train of equipment/components fully operational and protected while performing maintenance/testing on the opposite division/train. The NRC staff acknowledges that this approach reduces risk because one division/train of equipment/components would always be operational during the outage thereby avoiding a potential maintenance or equipment restoration error on the equipment/components for an entire division/train. To meet the current Mandatory Appendix I, paragraph 1-1350 requirement of testing 20 percent of the valves in each group every 48 months, a test on a "B" division valve during an "A" division outage would be
required. The alternative would be to perform a division valve test each refueling outage (alternate division/train each outage). Based on the above, the NRC staff does not consider this use of OMN-20 to be merely for operational convenience to extend the test intervals beyond those specified. The NRC staff determines that this use of OMN-20 is to facilitate test scheduling that considers plant operating conditions (maintaining one division/train of equipment/components fully operational and protected while performing maintenance/testing on the opposite division/train).
The NRC staff finds the request unnecessary and therefore terminated its acceptance review.
By teleconference on November 1, 2017, your staff agreed to withdraw the request.
Docket Nos. STN 50-454 and STN 50-455 cc w/encl: Distribution via Listserv Sincerely, Uoel S. Wiebe, Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML17300A297 LPL3 R/F OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA EMIB/BC NAME JWiebe SRohrer SBailey DATE 10/30/2017 10/30/2017 10/31/2017