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MONTHYEARML0307106912003-03-12012 March 2003 Inservice Testing Program Request Nos. 45 & VR-5 Regarding Relief Valve Testing Requirements, Indian Point Nuclear Generating Units 2 & 3, MB7222 & MB7223 Project stage: Other 2003-03-12
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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:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000003/20240022024-08-0606 August 2024 NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24171A0122024-06-18018 June 2024 Reply to a Notice of Violation EA-24-037 ML24156A1162024-06-0404 June 2024 Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000003/20240052024-05-21021 May 2024 and 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation ML24128A0632024-05-0707 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 ML24116A2412024-04-25025 April 2024 Annual Environmental Protection Plan Report ML24114A2282024-04-23023 April 2024 Annual Radioactive Effluent Release Report L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) ML24080A1722024-03-20020 March 2024 Reply to a Notice of Violation EA-2024-010 IR 05000003/20240012024-03-20020 March 2024 NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only) ML24045A0882024-02-22022 February 2024 Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments ML24053A0642024-02-22022 February 2024 2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report IR 05000003/20230042024-02-22022 February 2024 NRC Inspection Report Nos. 05000003/2023004, 05000247/2023004, 05000286/2023004, and 07200051/2023004 and Notice of Violation ML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 – Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks ML23235A0602023-07-17017 July 2023 LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River 2024-09-18
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March 12, 2003 Mr. Michael R. Kansler Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INSERVICE TESTING PROGRAM RELIEF REQUEST NOS. 45 AND VR-5 REGARDING RELIEF VALVE TESTING REQUIREMENTS, INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (TAC NOS. MB7222 AND MB7223)
Dear Mr. Kansler:
In a letter dated January 9, 2003, Entergy Nuclear Operations, Inc. (the licensee) submitted Relief Request Nos. 45 and VR-5 for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3), respectively. Relief was requested from the requirements of Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the third 10-year inservice inspection (ISI) interval. Specifically, the licensee requested approval to use a portion of a more recent edition and addenda of the ASME OM Code, Code for Operation and Maintenance of Nuclear Power Plants (OM Code), for testing pressure relief devices in the IP2 and IP3 inservice testing (IST) programs. The current Code of record for IST programs at IP2 and IP3 is the 1989 Edition of the ASME Code,Section XI. The 1989 ASME Code,Section XI references ASME OM Standards Part 1, Part 6, and Part 10 (OM-1, 6, and 10) for its IST requirements. The licensee requested approval to use the portions of the ASME OM Code, 1997 Addenda to the 1995 Edition, related to the hold time between valve openings of pressure relief devices as provided in Appendix I, Inservice Testing of Pressure Relief Devices in Light-Water Reactor Nuclear Power Plants, paragraphs 8.1.1(h), 8.1.2(h), and 8.1.3(g). The licensee requested to use these portions of the 1997 Addenda for the remainder of its third 10-year IST interval.
Section 50.55a of Title 10 of the Code of Federal Regulations (10 CFR 50.55a) requires that IST of ASME Code Class 1, 2, and 3 pumps and valves be performed in accordance with Section XI of the ASME Code and applicable addenda. The regulation in 10 CFR 50.55a(f)(4)(iv) states that IST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b),
subject to U.S. Nuclear Regulatory Commission (NRC) approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. The 1997 Addenda to the ASME OM Code was incorporated by reference into 10 CFR 50.55a(b) on September 26, 2002 (67 FR 60520), with no modifications or limitations placed on Mandatory Appendix I requirements. The NRC staff finds that all related requirements in Appendix I of the ASME OM Code, 1997 Addenda, have been met in the licensees submittal. Therefore, the licensees request to use as an alternative the portions of a later Code and addenda associated with the IST of pressure relief devices at IP2 and IP3 is
M. Kansler approved pursuant to 10 CFR 50.55a(f)(4)(iv) for the remainder of the third 10-year IST intervals for IP2 and IP3.
This completes the actions under TAC Nos. MB7222 and MB7223. If you should have any questions, please contact Patrick Milano, Sr. Project Manager, at 301-415-1457.
Sincerely,
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286 cc: See next page
M. Kansler approved pursuant to 10 CFR 50.55a(f)(4)(iv) for the remainder of the third 10-year IST intervals for IP2 and IP3.
This completes the actions under TAC Nos. MB7222 and MB7223. If you should have any questions, please contact Patrick Milano, Sr. Project Manager, at 301-415-1457.
Sincerely,
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286 cc: See next page DISTRIBUTION:
PUBLIC PDI-1 Reading S. Richards R. Laufer D. Terao W. Poertner P. Milano B. Platchek, R-I S. Little G. Hill (2/Docket)
OGC T. McGinty, EDO ACRS ACCESSION Number: ML030710691 OFFICE PDI-1:PM PDI-1:LA EMEB:SC OGC PDI-1:SC NAME PMilano SLittle DTerao RHoefling RLaufer DATE 03/03/03 03/03/03 03/04/ 03 03/11/03 03/12/03 OFFICIAL RECORD COPY
Indian Point Nuclear Generating Unit Nos. 2 & 3 cc:
Mr. Jerry Yelverton Mr. Joseph DeRoy Chief Executive Officer General Manager Operations Entergy Operations Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Indian Point Nuclear Generating Unit 3 Jackson, MS 39213 295 Broadway, Suite 3 P.O. Box 308 Mr. Fred Dacimo Buchanan, NY 10511-0308 Vice President Operations Entergy Nuclear Operations, Inc. Mr. John Kelly Indian Point Nuclear Generating Units 1 & 2 Director of Licensing 295 Broadway, Suite 1 Entergy Nuclear Operations, Inc.
P.O. Box 249 440 Hamilton Avenue Buchanan, NY 10511-0249 White Plains, NY 10601 Mr. Robert J. Barrett Ms. Charlene Faison Vice President - Operations Manager, Licensing Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 3 440 Hamilton Avenue 295 Broadway, Suite 3 White Plains, NY 10601 P.O. Box 308 Buchanan, NY 10511-0308 Mr. John McCann Manager, Nuclear Safety and Licensing Mr. Dan Pace Indian Point Nuclear Generating Unit 2 Vice President Engineering Entergy Nuclear Operations, Inc.
Entergy Nuclear Operations, Inc. 295 Broadway, Suite 1 440 Hamilton Avenue P.O. Box 249 White Plains, NY 10601 Buchanan, NY 10511-0249 Mr. James Knubel Mr. Harry P. Salmon, Jr.
Vice President Operations Support Director of Oversight Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Mr. Christopher J. Schwarz Mr. Thomas Walsh General Manager Operations Secretary - NFSC Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 2 Indian Point Nuclear Generating Unit 2 295 Broadway, Suite 1 295 Broadway, Suite 1 P.O. Box 249 P.O. Box 249 Buchanan, NY 10511-0249 Buchanan, NY 10511-0249
Indian Point Nuclear Generating Unit Nos. 2 & 3 cc:
Regional Administrator, Region I Mr. Charles Donaldson, Esquire U.S. Nuclear Regulatory Commission Assistant Attorney General 475 Allendale Road New York Department of Law King of Prussia, PA 19406 120 Broadway New York, NY 10271 Senior Resident Inspector, Indian Point 2 U. S. Nuclear Regulatory Commission Mr. Ronald Schwartz 295 Broadway, Suite 1 SRC Consultant P.O. Box 38 64 Walnut Drive Buchanan, NY 10511-0038 Spring Lake Heights, NJ 07762 Resident Inspectors Office, Indian Point 3 Mr. Ronald J. Toole U.S. Nuclear Regulatory Commission SRC Consultant 295 Broadway, Suite 3 Toole Insight P.O. Box 337 605 West Horner Street Buchanan, NY 10511-0337 Ebensburg, PA 15931 Mr. John M. Fulton Mr. Charles W. Hehl Assistant General Counsel SRC Consultant Entergy Nuclear Operations, Inc. Charles Hehl, Inc.
440 Hamilton Avenue 1486 Matthew Lane White Plains, NY 10601 Pottstown, PA 19465 Ms. Stacey Lousteau Mayor, Village of Buchanan Treasury Department 236 Tate Avenue Entergy Services, Inc. Buchanan, NY 10511 639 Loyola Avenue Mail Stop: L-ENT-15E Mr. Ray Albanese New Orleans, LA 70113 Executive Chair Four County Nuclear Safety Committee Mr. William M. Flynn, President Westchester County Fire Training Center New York State Energy, Research, and 4 Dana Road Development Authority Valhalla, NY 10592 17 Columbia Circle Albany, NY 12203-6399 Alex Matthiessen Executive Director Mr. J. Spath, Program Director Riverkeeper, Inc.
New York State Energy, Research, and 25 Wing & Wing Development Authority Garrison, NY 10524 17 Columbia Circle Albany, NY 12203-6399 Paul Leventhal The Nuclear Control Institute Mr. Paul Eddy 1000 Connecticut Avenue NW Electric Division Suite 410 New York State Department Washington, DC, 20036 of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223
Indian Point Nuclear Generating Unit Nos. 2 & 3 cc:
Karl Copeland Pace Environmental Litigation Clinic 78 No. Broadway White Plains, NY 10603 Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001 Mr. Michael Kansler Sr. Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601