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| | number = ML18099A373 | | | number = ML18099A373 |
| | issue date = 04/09/2018 | | | issue date = 04/09/2018 |
| | title = Indian Point, Unit 2 - 04/09/2018 E-mail from R. Guzman to R. Walpole, Verbal Authorization for Relief Request IP2-ISI-RR-06 | | | title = 04/09/2018 E-mail from R. Guzman to R. Walpole, Verbal Authorization for Relief Request IP2-ISI-RR-06 |
| | author name = Guzman R V | | | author name = Guzman R |
| | author affiliation = NRC/NRR/DORL/LPLI | | | author affiliation = NRC/NRR/DORL/LPLI |
| | addressee name = Walpole R W | | | addressee name = Walpole R |
| | addressee affiliation = Entergy Nuclear Operations, Inc | | | addressee affiliation = Entergy Nuclear Operations, Inc |
| | docket = 05000247 | | | docket = 05000247 |
| | license number = DPR-026 | | | license number = DPR-026 |
| | contact person = Guzman R V | | | contact person = Guzman R |
| | case reference number = EPID: L-2018-LLR-0050, IP2-ISI-RR-06 | | | case reference number = EPID: L-2018-LLR-0050, IP2-ISI-RR-06 |
| | document type = Code Relief or Alternative, E-Mail | | | document type = Code Relief or Alternative, E-Mail |
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| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:From: Guzman, Richard To: "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-06 Date: Monday, April 09, 2018 7:48:25 PM Mr. Walpole, In accordance with NRR Office Instruction LIC-102, Relief Request Reviews, the NRR staff has provided verbal authorization for Indian Point, Unit 2 relief request IP2-ISI-RR-06 as described in your 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 at approximately 2:10pm EDT on 4/9/2018 by David Alley and James Danna. The NRC staff intends to 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 be made publicly available in ADAMS. |
| | : Thanks, |
| | ~~~~~~~~~ |
| | Rich Guzman Sr. PM, Division Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov |
| | ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ |
| | VERBAL AUTHORIZATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR RELIEF REQUEST IP2-ISI-RR-06 ALTERNATE REPAIR OF A REACTOR VESSEL HEAD PENETRATION NOZZLE ENTERGY NUCLEAR OPERATIONS, INC. |
| | INDIAN POINT UNIT 2 DOCKET NO. 50-247 April 9, 2018 Technical Evaluation Read by David Alley, Branch Chief, Piping and Head Penetration Branch, 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 Accession No. 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 Indian Point Unit 2 (IP2). In order to repair the degraded nozzle, the licensee proposed to use the embedded flaw repair process described in the NRC-approved WCAP-15987-P, Revision 2-P-A report. |
| | The licensee made this request in accordance with 10 CFR 50.55a(z)(1) on the basis that the proposed alternative repair will provide an acceptable level of quality and safety. The licensee requested 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 potential fatigue 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 flaw evaluation methods with those described in the NRC-approved WCAP-15987-P, Revision 2-P-A report. |
| | The NRC staff finds that the licensees repair, inspection and flaw evaluation methods are consistent with the guidance in the NRC-approved WCAP-15987-P, Revision-2-P-A report and the inspection requirements 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 system pressure boundary and provide reasonable assurance that the structural integrity of the reactor vessel 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 of Operating Reactor Licensing, Office of Nuclear Reactor Regulation As Chief of Plant Licensing Branch 1, I concur with the Piping and Head Penetration Branchs determinations. |
| | The NRC staff concludes that Relief Request IP2-ISI-RR-06 will provide an acceptable level of quality and safety for the reactor vessel head and repaired nozzle Number 3. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) and is in compliance with the requirements of the ASME Code, Section XI, 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 24 that will end in Spring 2020. |
| | All other requirements of ASME Code Section XI and 10 CFR 50.55a(g)(6)(ii)(D), for which relief was not specifically requested and authorized by the NRC staff, remain applicable including the third party review by the Authorized Nuclear Inservice Inspector. |
| | This verbal authorization does not preclude the NRC staff from asking additional questions and clarifications regarding Relief Request IP2-ISI-RR-06 while preparing the subsequent written safety evaluation. |
| | ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~}} |
Letter Sequence Other |
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EPID:L-2018-LLR-0050, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability (Approved, Closed) |
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Category:Code Relief or Alternative
MONTHYEARML21299A0032021-10-28028 October 2021 and Waterford Steam Electric Station, Unit 3 - Approval of Request for Alternative EN-20-RR-003 from Certain Requirements of the ASME Code ML21054A3302021-02-24024 February 2021 Approval of Alternative IP3-ISI-RR-16 to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020 Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 ML19039A1492019-02-25025 February 2019 Issuance of Relief Request IP3-ISI-RR-14 Alternative Examination Required by ASME Code Case N-724-4 CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019 Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML18251A0042018-09-18018 September 2018 Safety Evaluation for Relief Request IP3-ISI-RR-11, RR-12, RR-15 Approval of Alternative Associated with Extension of Fourth Interval Reactor Vessel and Piping Weld Inspections (EPID: L-2017-LLR-0124,0127) ML18193B0302018-07-18018 July 2018 Safety Evaluation for Relief Request IP3-ISI-RR-13 Fourth Ten-year Inservice Inspection Interval Extension ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 ML18099A3732018-04-0909 April 2018 04/09/2018 E-mail from R. Guzman to R. Walpole, Verbal Authorization for Relief Request IP2-ISI-RR-06 ML18059A1562018-03-0606 March 2018 Safety Evaluation for Relief Request IP2-ISI-RR-05 Alternative Examination Volume Required by ASME Code Case N-729-4 ML18005A0662018-01-23023 January 2018 Safety Evaluation of Relief Requests ISI-RR-20, ISI-RR-21, and ISI-RR-22 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017 Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 ML17174B1442017-07-12012 July 2017 Relief Request for EN-ISI-16-1 Regarding Use of Later Edition and Addenda of the ASME Code ML17069A2832017-03-16016 March 2017 Relief Request No. IP3-ISI-RR-09, for Alternative to the Depth Sizing Qualification Requirement ML16358A4442017-01-11011 January 2017 Relief from the Requirements of the ASME Code Regarding Alternate IP3-RR-10 to the Full Circumferential Inspection Requirement of Code Case N-513-3 ML16167A0812016-07-15015 July 2016 Request for Alternative IP2-ISI-RR-03 to Weld Reference System Examination Required by ASME Code Subarticle IWA-2600 ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16053A0252016-03-0303 March 2016 IP2-ISI-44-18, Relief from the Requirements of the ASME Code CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division ML14198A3312014-07-23023 July 2014 Safety Evaluation for Relief Request IP3-ISI-RR-06 for Reactor Vessel Weld Examinations (Tac No. MF3345) NL-13-041, Relief Request IP2-ISI-RR-17: Code Case N-770-1 Weld Inspection Frequency Extension2013-02-20020 February 2013 Relief Request IP2-ISI-RR-17: Code Case N-770-1 Weld Inspection Frequency Extension ML12334A3172012-12-0303 December 2012 Relief Request IP2-ISI-RR-15 - Proposed Alternative to the Use of a Weld Reference System NL-12-065, 2012 Summary Report for In-Service Inspection and Repairers and Replacements2012-06-13013 June 2012 2012 Summary Report for In-Service Inspection and Repairers and Replacements NL-12-069, Unit Number 2, Relief Request IP2-1SI-RR-15 - Proposed Alternative to the Use of a Weld Reference System2012-05-23023 May 2012 Unit Number 2, Relief Request IP2-1SI-RR-15 - Proposed Alternative to the Use of a Weld Reference System ML11105A1222011-04-25025 April 2011 Relief from the Requirements of the ASME Code to Perform Essentially 100 Percent Volumetric Examination of the Weld and Adjacent Base Material for the Third 10-Year Inservice Inspection ML11109A0162011-04-25025 April 2011 Relief Request No. IP2-ISI-RR-12, Reactor Vessel Shell-To-Flange Weld Inspection for the Fourth 10-Year Inservice Inspection Interval (Tac No. ME5180) NL-10-136, Submittal of 10 CFR 50.55a Relief Request IP2-ISI-RR-12 for 4th Ten-Year Inservice Inspection Interval2010-12-14014 December 2010 Submittal of 10 CFR 50.55a Relief Request IP2-ISI-RR-12 for 4th Ten-Year Inservice Inspection Interval ML1017400482010-07-15015 July 2010 Relief Request RR-11 for the Fourth 10-Year Inservice Inspection Interval NL-10-061, CFR 50.55a Relief Requests RR-3-49 and RR-3-50 from Examinations of Component Welds with Less than Essentially 100% Examination Coverage for Third Ten-Year Inservice Inspection Interval2010-07-0505 July 2010 CFR 50.55a Relief Requests RR-3-49 and RR-3-50 from Examinations of Component Welds with Less than Essentially 100% Examination Coverage for Third Ten-Year Inservice Inspection Interval ML1015303122010-06-0707 June 2010 Relief Request RR-02 for the Fourth 10-Year Inservice Inspection Interval NL-09-022, Supplement to Request for Relief 3-48 and 3-47 (I) to Support Refuel Outage 15 Inservice Inspection Program2009-02-0606 February 2009 Supplement to Request for Relief 3-48 and 3-47 (I) to Support Refuel Outage 15 Inservice Inspection Program NL-09-0111, Submittal of Relief Requests No. 3-45, 3-46, 3-47(I) and 3-48 to Support the Unit 3 Refuel Outage 15 Inservice Inspection Program2009-01-22022 January 2009 Submittal of Relief Requests No. 3-45, 3-46, 3-47(I) and 3-48 to Support the Unit 3 Refuel Outage 15 Inservice Inspection Program NL-09-003, Supplemental Response to Request for Additional Information on Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination2009-01-20020 January 2009 Supplemental Response to Request for Additional Information on Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination NL-08-096, Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses2008-07-0808 July 2008 Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses ML0721304872007-09-0505 September 2007 Relief Request No. RR-01 NOC-AE-06002031, Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for Use of Penetrameters in Radiographic Examinations2006-06-14014 June 2006 Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for Use of Penetrameters in Radiographic Examinations ML0602600762006-02-0808 February 2006 Relief Request (RR) No. 74 NL-05-0720, Request for Relief to Extend the Third 10-Year Inservice Inspection Interval for the Reactor Vessel Weld Examination2005-06-0808 June 2005 Request for Relief to Extend the Third 10-Year Inservice Inspection Interval for the Reactor Vessel Weld Examination ML0509401362005-04-0404 April 2005 Relief, Relaxation of First Revised Order on Reactor Vessel Nozzles ML0507700102005-03-18018 March 2005 Relaxation of First Revised Order on Reactor Vessel Nozzles ML0427406642004-10-14014 October 2004 Relief Request Nos. R-33, R-71, R 3-40(A) and R-41, James A. FitzPatrick Nuclear Power Plant, Indian Point Nuclear Generating Unit Nos. 2 and No. 3 and Pilgrim Nuclear Power Station ML0427406282004-10-14014 October 2004 Relief Request Nos. 65, 66, 3-34 and 3-35 Regarding Alternative Nondestructive Examination Qualification Requirements ML0425203922004-10-0505 October 2004 Relief, Requirements of American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section III, 1965 Edition, & Section XI, 1989 Edition, for Repair & Inspection of Reactor Pressure Vessel Head Penetrations ML0418901542004-07-0707 July 2004 Relief, Relief Request Nos. RR-67 and RR 3-36, TAC Nos. MC1698 and MC1699 ML0410700882004-07-0606 July 2004 Relief Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-600 ML0408205162004-03-22022 March 2004 Relief Request Nos. RR-68, RR3-37, and PRR-34 (TAC MC1559, MC1560, & MC1561) ML0408506682004-03-19019 March 2004 Relief Request Nos. 70 and 3-39 Regarding Alternative Depth Sizing Criteria.(Tac MC1696 & MC1697) ML0408600062004-03-19019 March 2004 Relief Request No. RR 63 Regarding risk-informed Inservice Inspection Program ML0335000092003-12-16016 December 2003 Inservice Testing Program Relief Request Nos. 47 and 48, MB9111 and MB9112 2021-02-24
[Table view] Category:E-Mail
MONTHYEARML23341A2002023-12-0707 December 2023 Email - Indian Point Energy Center Generating Units 1, 2, and 3 Implementation Notice of Amendment No. 67, 300 and 276 to Independent Spent Fuel Storage Installation Only Emergency Plan (Ioep) ML23332A0802023-11-0808 November 2023 Email from State of New York on the Revised License Amendment for Indian Point Energy Center ISFSI Only Emergency Plan ML23325A1632023-11-0808 November 2023 State of New York Comments on the Revised License Amendment for Indian Point Unit 2 and 3 Technical Specification Changes Reflecting Permanent Removal of Spent Fuel ML23331A9542023-11-0808 November 2023 Email - State of New York Comments on the Revised License Amendment for Indian Point Unit 2 and 3 Technical Specification Changes Reflecting Permanent Removal of Spent Fuel ML23144A3452023-05-25025 May 2023 Adam Kahn of Monsey, New York Email Against Treated Water Release from Indian Point Site ML23144A3442023-05-25025 May 2023 Peggy Kurtz of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23144A3392023-05-25025 May 2023 David Morris of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3502023-05-25025 May 2023 Dan Kwilecki of Montebello, New York Email Against Treated Water Release from Indian Point Site ML23144A3422023-05-25025 May 2023 Peter Duda of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3382023-05-25025 May 2023 Dawn Giambalvo of Jersey City, New Jersey Email Against Treated Water Release from Indian Point Site ML23136B1622023-05-15015 May 2023 Town of North Salem, County of Westchester, New York Board Resolution Letter Regarding Treated Water Release from Indian Point Site ML23109A0632023-04-17017 April 2023 Email Acceptance Review for IP2 and IP3 Amended Facility License and Technical Specification to Reflect Permanent Removal of Spent Fuel from Spent Fuel Pits ML23055A1112023-02-23023 February 2023 Alyse Peterson Email- NYSERDA No Comments on Indian Point Unit 2 - Regarding Holtec License Amendment Request to Revise Permanently Defueled Technical Specifications and Staffing Requirements with Spent Fuel Transfer to ISFSI (Dockets 50-24 ML23049A0032023-02-14014 February 2023 NRC Acceptance Email to Holtec for License Amendment Request for Approval of New ISFSI-Only Emergency Plan and Associated EAL Scheme ML22313A1682022-11-0909 November 2022 NRC Response to Updates to the Proposed Amended IP2 Master Trust ML22308A0912022-11-0303 November 2022 Email Acknowledgement for IP2 and IP3 Amended Facility License and Technical Specification to Reflect Permanent Removal of Spent Fuel from Spent Fuel Pits ML22276A1642022-09-29029 September 2022 New York State Revised Draft EA Response E-Mail ML22271A8492022-09-28028 September 2022 E-Mail Transmitting Revised Indian Point Exemption Draft EA ML22269A3452022-09-22022 September 2022 Email Objection to Holtec IP2 Master Decommissioning Trust Agreement for Indian Point Nuclear Generating Facility Unit 1 and 2, EPID L-2022-LLA-0072 ML22259A1992022-09-0202 September 2022 Acceptance for License Amendment Request to Modify Staffing Requirements Following SFP Transfer to Dry Storage ML22265A0142022-08-31031 August 2022 Email Acknowledgement for Amended and Restated Holtec IP3 Master Decommissioning Trust Agreement for Indian Point Nuclear Generating Facility Unit 3 ML22242A2592022-08-19019 August 2022 E-mail from K. Sturzebecher, NRC, to B. Noval, HDI, Acknowledgement for Amended and Restated Holtec IP2 Master Decommissioning Trust Agreement for Indian Point Nuclear Generating Facility Unit 1 and 2 ML22228A1332022-08-0909 August 2022 Acknowledgement for License Amendment Request to Modify Staffing Requirements Following SFP Transfer to Dry Storage ML22215A0432022-08-0101 August 2022 E-Mail Transmitting NYS NSA Exemption Comments & Draft EA Review Completion ML22208A0292022-07-19019 July 2022 E-Mail Transmitting Indian Point Exemption Draft EA ML22168A0072022-06-16016 June 2022 Acceptance Review for License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML22112A0102022-04-21021 April 2022 Acceptance Review: Request for Exemption from 10 CFR 50.54(w)(1) Concerning Indian Point Energy Center Onsite Property Damage Insurance ML22112A0122022-04-21021 April 2022 Acceptance Review: Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance for Indian Point Energy Center ML22103A2432022-04-13013 April 2022 E-mail - Request for Additional Information - License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme for Permanently Defueled Condition for Indian Point Energy Center ML22104A0342022-04-13013 April 2022 E-mail from Z. Cruz, NRC to J. Fleming, Holtec - Request for Additional Information Related to Request for Exemption from Portions of 10 CFR 50.47 and Part 50 Appendix E for Indian Point Energy Center ML22038A2572022-02-0707 February 2022 E-mail from Z. Cruz, NRC, to J. Fleming, HDI - Acceptance Review: License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme to Address Permanently Defueled Condition for Indian Point Energy Center ML22035A1862022-02-0404 February 2022 E-mail to J. Fleming, Holtec, from Z. Cruz Perez, NRC - Acceptance Review: Exemption Requests from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E, Section IV for Indian Point Energy Center ML22028A1032022-01-28028 January 2022 E-mail Dated 1/28/2022, Transmittal of Draft Safety Evaluation for Proposed License Amendment Revision to Licensing Basis to Incorporate the Installation and Use of of New Auxiliary Lifting Device ML22038A1592022-01-24024 January 2022 NRR E-mail Capture - (External_Sender) 2021 IPEC Annual Sturgeon Impingement Report ML22006A0442022-01-0505 January 2022 Email from Z Cruz to J Fleming Request for Additional Information - HDI Indian Point Post-Shutdown Decommissioning Activities Report ML21337A2952021-12-0303 December 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (E-mail Dated 12/3/2021) ML21335A3692021-12-0101 December 2021 Acceptance Review: Indian Point Energy Center - Exemption Request from 10 CFR Part 20 App G Section Iii.E ML21266A2972021-08-18018 August 2021 8/18/2021 E-mail from H. Specter to R. Guzman Public Comments to NRC, Indian Point Post-Shutdown Decommissioning Activities Report Public Meeting on July 29, 2021 ML21225A6142021-08-0909 August 2021 Email from NRC to the Tuscarora Nation Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A5682021-08-0909 August 2021 Email from NRC to the Stockbridge-Munsee Community Band of Mohican Indians Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A5012021-08-0909 August 2021 Email from NRC to the Shinnecock Indian Nation Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21224A3032021-08-0909 August 2021 Email from NRC to the Mashantucket Pequot Tribe of Connecticut Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A4252021-08-0909 August 2021 Email from NRC to the Oneida Nation of Wisconsin Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A3142021-08-0606 August 2021 Email from NRC to the Oneida Indian Nation Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A4402021-08-0606 August 2021 Email from NRC to the Onondaga Nation of Wisconsin Announcing the IPEC PSDAR Meeting on August 18, 2021 ML21225A5462021-08-0606 August 2021 Email from NRC to the St. Regis Mohawk Tribe Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A5352021-08-0606 August 2021 Email from NRC to the Tonawanda Band of Seneca Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21266A2942021-07-25025 July 2021 E-mail from Paul Blanch to NRC (N. Sheehan, D. Screnci) Public Comments to NRC, Indian Point Post-Shutdown Decommissioning Activities Report Public Meeting, July 29, 2021 ML21197A2002021-07-16016 July 2021 (E-mail 7/16/2021) NRC Staff Assessment and RAI Closeout HDI Fleet Decommissioning Quality Assurance Program and Indian Point Energy Center Quality Assurance Program Manual ML21194A4082021-07-13013 July 2021 (7-13-2021) E-mail NRR Review Hour Estimate Change Supporting the Hi-Lift Crane Proposed License Amendment Request Review 2023-05-25
[Table view] |
Text
From: Guzman, Richard To: "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-06 Date: Monday, April 09, 2018 7:48:25 PM Mr. Walpole, In accordance with NRR Office Instruction LIC-102, Relief Request Reviews, the NRR staff has provided verbal authorization for Indian Point, Unit 2 relief request IP2-ISI-RR-06 as described in your 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 at approximately 2:10pm EDT on 4/9/2018 by David Alley and James Danna. The NRC staff intends to 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 be made publicly available in ADAMS.
- Thanks,
~~~~~~~~~
Rich Guzman Sr. PM, Division Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
VERBAL AUTHORIZATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR RELIEF REQUEST IP2-ISI-RR-06 ALTERNATE REPAIR OF A REACTOR VESSEL HEAD PENETRATION NOZZLE ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT UNIT 2 DOCKET NO. 50-247 April 9, 2018 Technical Evaluation Read by David Alley, Branch Chief, Piping and Head Penetration Branch, 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 Accession No. 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 Indian Point Unit 2 (IP2). In order to repair the degraded nozzle, the licensee proposed to use the embedded flaw repair process described in the NRC-approved WCAP-15987-P, Revision 2-P-A report.
The licensee made this request in accordance with 10 CFR 50.55a(z)(1) on the basis that the proposed alternative repair will provide an acceptable level of quality and safety. The licensee requested 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 potential fatigue 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 flaw evaluation methods with those described in the NRC-approved WCAP-15987-P, Revision 2-P-A report.
The NRC staff finds that the licensees repair, inspection and flaw evaluation methods are consistent with the guidance in the NRC-approved WCAP-15987-P, Revision-2-P-A report and the inspection requirements 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 system pressure boundary and provide reasonable assurance that the structural integrity of the reactor vessel 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 of Operating Reactor Licensing, Office of Nuclear Reactor Regulation As Chief of Plant Licensing Branch 1, I concur with the Piping and Head Penetration Branchs determinations.
The NRC staff concludes that Relief Request IP2-ISI-RR-06 will provide an acceptable level of quality and safety for the reactor vessel head and repaired nozzle Number 3. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) and is in compliance with the requirements of the ASME Code,Section XI, 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 24 that will end in Spring 2020.
All other requirements of ASME Code Section XI and 10 CFR 50.55a(g)(6)(ii)(D), for which relief was not specifically requested and authorized by the NRC staff, remain applicable including the third party review by the Authorized Nuclear Inservice Inspector.
This verbal authorization does not preclude the NRC staff from asking additional questions and clarifications regarding Relief Request IP2-ISI-RR-06 while preparing the subsequent written safety evaluation.
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