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Revision as of 23:50, 16 April 2018
Letter Sequence Other | |
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EPID:L-2018-LLR-0050, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability (Approved, Closed) | |
Administration Questions
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MONTHYEARML18108A1832018-04-0303 April 2018
[Table View]E-mail from R.Walpole to R.Guzman - Draft Relief Request IP2 RR-ISI-05 for Public Meeting Presentation NL-18-019, Relief Request Number IP2-ISI-RR-06 - Proposed Alternative to Use Reactor Vessel Head Penetration Flaw Weld Repair Method2018-04-0404 April 2018 Relief Request Number IP2-ISI-RR-06 - Proposed Alternative to Use Reactor Vessel Head Penetration Flaw Weld Repair Method Project stage: Request ML18098A0882018-04-0606 April 2018 Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability Project stage: Request 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 Project stage: Other ML18117A3162018-04-30030 April 2018 Summary of 04/03/2018 Meeting with Entergy on Planned Submittal of Propose Alternative for Reactor Pressure Vessel Head Nozzle Weld Repair Project stage: Meeting ML18142A4312018-05-31031 May 2018 Safety Evaluation for Relief Request IP2-ISI-RR-06 Approval of Alternative to Use Embedded Weld Repair Project stage: Approval 2018-04-04 |
| 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) | |
Similar Documents at Indian Point | |
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Category:Code Relief or Alternative
MONTHYEARML21299A0032021-10-28028 October 2021
[Table view]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 Category:E-Mail MONTHYEARML23341A2002023-12-0707 December 2023
[Table view]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 |
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