ML18099A373: Difference between revisions
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{{#Wiki_filter: | {{#Wiki_filter:From:Guzman, RichardTo:"Walpole, Robert W"Cc:Danna, James; Alley, David; Haagensen, Brian; Schroeder, Daniel | ||
= | ==Subject:== | ||
Verbal Authorization for Indian Point, Unit 2 Relief Request IP2-ISI-RR-06Date:Monday, April 09, 2018 7:48:25 PMMr. Walpole, In accordance with NRR Office Instruction LIC-102, "Relief Request Reviews," the NRR staff hasprovided verbal authorization for Indian Point, Unit 2 relief request IP2-ISI-RR-06 as described inyour letter to the NRC dated April 4, 2018, as supplemented by letter dated April 6, 2018. Below is the script for the verbal authorization of relief request IP2-RR-ISI-06 that was provided atapproximately 2:10pm EDT on 4/9/2018 by David Alley and James Danna. The NRC staff intendsto follow-up this verbal authorization with a written safety evaluation within approximately 150 days. Please let me know if you have any questions. A copy of this email and verbal authorization will bemade publicly available in ADAMS. Thanks,~~~~~~~~~Rich GuzmanSr. PM, Division Operator Reactor LicensingOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionOffice: O-9C7 l Phone: (301) 415-1030Richard.Guzman@nrc.gov ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ VERBAL AUTHORIZATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONFOR RELIEF REQUEST IP2-ISI-RR-06ALTERNATE REPAIR OF A REACTOR VESSEL HEAD PENETRATION NOZZLEENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT UNIT 2DOCKET NO. 50-247April 9, 2018 Technical Evaluation Read by David Alley, Branch Chief, Piping and Head PenetrationBranch, Division of Material and License Renewal, Office of Nuclear Reactor Regulation By letter dated April 4, 2018 (Agencywide Documents Access and Management System (ADAMS)Accession No. ML18094B454) as supplemented by letter dated April 6, 2018 (ADAMS AccessionNo. ML18098A088), Entergy Nuclear Operations, Inc. (the licensee) submitted Relief Request IP2-ISI-RR-06 for the repair of degraded reactor vessel head penetration nozzle Number 3 at IndianPoint Unit 2 (IP2). In order to repair the degraded nozzle, the licensee proposed to use theembedded flaw repair process described in the NRC-approved WCAP-15987-P, Revision 2-P-Areport. The licensee made this request in accordance with 10 CFR 50.55a(z)(1) on the basis that theproposed alternative repair will provide an acceptable level of quality and safety. The licenseerequested the alternative for one cycle of operation. The NRC staff reviewed the following information: (1) proposed repair method and inspections: (2) flaw evaluation including a conservatively postulated flaw in the nozzle J-groove weld and potentialfatigue crack growth into the reactor vessel head; (3) corrosion resistance of repair weld material(Alloy 52/52M) exposed to reactor coolant; and (4) consistency of the repair, inspection and flawevaluation methods with those described in the NRC-approved WCAP-15987-P, Revision 2-P-Areport. The NRC staff finds that the licensee's repair, inspection and flaw evaluation methods are consistentwith the guidance in the NRC-approved WCAP-15987-P, Revision P-A report and the inspectionrequirements specified in ASME Code Case N-729-4 (as conditioned in 10 CFR Part 50, paragraph(g)(6)(ii)(D)). The NRC staff determines that the proposed repair will restore the primary systempressure boundary and provide reasonable assurance that the structural integrity of the reactorvessel head and repaired nozzle Number 3 will be maintained for the period of the relief request(i.e., Cycle 24 that will end in Spring 2020). NRC Staff Conclusion Read by James Danna, Chief of Plant Licensing Branch 1, Division ofOperating Reactor Licensing, Office of Nuclear Reactor Regulation As Chief of Plant Licensing Branch 1, I concur with the Piping and Head Penetration Branch'sdeterminations. The NRC staff concludes that Relief Request IP2-ISI-RR-06 will provide an acceptable level ofquality and safety for the reactor vessel head and repaired nozzle Number 3. Accordingly, the NRCstaff concludes that the licensee has adequately addressed all of the regulatory requirements setforth in 10 CFR 50.55a(z)(1) and is in compliance with the requirements of the ASME Code, SectionXI, ASME Code Case N-729-4 as mandated and conditioned in 10 CFR Part 50, paragraph (g)(6)(ii)(D). Therefore, as of April 9, 2018, the NRC authorizes Relief Request IP2-ISI-RR-06 for Cycle 24that will end in Spring 2020. All other requirements of ASME Code Section XI and 10 CFR 50.55a(g)(6)(ii)(D), for which reliefwas not specifically requested and authorized by the NRC staff, remain applicable including the thirdparty review by the Authorized Nuclear Inservice Inspector. This verbal authorization does not preclude the NRC staff from asking additional questions andclarifications regarding Relief Request IP2-ISI-RR-06 while preparing the subsequent written safetyevaluation. ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ | |||
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Revision as of 00:08, 18 April 2018
ML18099A373 | |
Person / Time | |
---|---|
Site: | Indian Point ![]() |
Issue date: | 04/09/2018 |
From: | Guzman R V Plant Licensing Branch 1 |
To: | Walpole R W Entergy Nuclear Operations |
Guzman R V | |
References | |
EPID: L-2018-LLR-0050, IP2-ISI-RR-06 | |
Download: ML18099A373 (2) | |
Text
From:Guzman, RichardTo:"Walpole, Robert W"Cc:Danna, James; Alley, David; Haagensen, Brian; Schroeder, Daniel
Subject:
Verbal Authorization for Indian Point, Unit 2 Relief Request IP2-ISI-RR-06Date:Monday, April 09, 2018 7:48:25 PMMr. Walpole, In accordance with NRR Office Instruction LIC-102, "Relief Request Reviews," the NRR staff hasprovided verbal authorization for Indian Point, Unit 2 relief request IP2-ISI-RR-06 as described inyour letter to the NRC dated April 4, 2018, as supplemented by letter dated April 6, 2018. Below is the script for the verbal authorization of relief request IP2-RR-ISI-06 that was provided atapproximately 2:10pm EDT on 4/9/2018 by David Alley and James Danna. The NRC staff intendsto follow-up this verbal authorization with a written safety evaluation within approximately 150 days. Please let me know if you have any questions. A copy of this email and verbal authorization will bemade publicly available in ADAMS. Thanks,~~~~~~~~~Rich GuzmanSr. PM, Division Operator Reactor LicensingOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionOffice: O-9C7 l Phone: (301) 415-1030Richard.Guzman@nrc.gov ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ VERBAL AUTHORIZATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONFOR RELIEF REQUEST IP2-ISI-RR-06ALTERNATE REPAIR OF A REACTOR VESSEL HEAD PENETRATION NOZZLEENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT UNIT 2DOCKET NO. 50-247April 9, 2018 Technical Evaluation Read by David Alley, Branch Chief, Piping and Head PenetrationBranch, Division of Material and License Renewal, Office of Nuclear Reactor Regulation By letter dated April 4, 2018 (Agencywide Documents Access and Management System (ADAMS)Accession No. ML18094B454) as supplemented by letter dated April 6, 2018 (ADAMS AccessionNo. ML18098A088), Entergy Nuclear Operations, Inc. (the licensee) submitted Relief Request IP2-ISI-RR-06 for the repair of degraded reactor vessel head penetration nozzle Number 3 at IndianPoint Unit 2 (IP2). In order to repair the degraded nozzle, the licensee proposed to use theembedded flaw repair process described in the NRC-approved WCAP-15987-P, Revision 2-P-Areport. The licensee made this request in accordance with 10 CFR 50.55a(z)(1) on the basis that theproposed alternative repair will provide an acceptable level of quality and safety. The licenseerequested the alternative for one cycle of operation. The NRC staff reviewed the following information: (1) proposed repair method and inspections: (2) flaw evaluation including a conservatively postulated flaw in the nozzle J-groove weld and potentialfatigue crack growth into the reactor vessel head; (3) corrosion resistance of repair weld material(Alloy 52/52M) exposed to reactor coolant; and (4) consistency of the repair, inspection and flawevaluation methods with those described in the NRC-approved WCAP-15987-P, Revision 2-P-Areport. The NRC staff finds that the licensee's repair, inspection and flaw evaluation methods are consistentwith the guidance in the NRC-approved WCAP-15987-P, Revision P-A report and the inspectionrequirements specified in ASME Code Case N-729-4 (as conditioned in 10 CFR Part 50, paragraph(g)(6)(ii)(D)). The NRC staff determines that the proposed repair will restore the primary systempressure boundary and provide reasonable assurance that the structural integrity of the reactorvessel head and repaired nozzle Number 3 will be maintained for the period of the relief request(i.e., Cycle 24 that will end in Spring 2020). NRC Staff Conclusion Read by James Danna, Chief of Plant Licensing Branch 1, Division ofOperating Reactor Licensing, Office of Nuclear Reactor Regulation As Chief of Plant Licensing Branch 1, I concur with the Piping and Head Penetration Branch'sdeterminations. The NRC staff concludes that Relief Request IP2-ISI-RR-06 will provide an acceptable level ofquality and safety for the reactor vessel head and repaired nozzle Number 3. Accordingly, the NRCstaff concludes that the licensee has adequately addressed all of the regulatory requirements setforth in 10 CFR 50.55a(z)(1) and is in compliance with the requirements of the ASME Code, SectionXI, ASME Code Case N-729-4 as mandated and conditioned in 10 CFR Part 50, paragraph (g)(6)(ii)(D). Therefore, as of April 9, 2018, the NRC authorizes Relief Request IP2-ISI-RR-06 for Cycle 24that will end in Spring 2020. All other requirements of ASME Code Section XI and 10 CFR 50.55a(g)(6)(ii)(D), for which reliefwas not specifically requested and authorized by the NRC staff, remain applicable including the thirdparty review by the Authorized Nuclear Inservice Inspector. This verbal authorization does not preclude the NRC staff from asking additional questions andclarifications regarding Relief Request IP2-ISI-RR-06 while preparing the subsequent written safetyevaluation. ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~