|
---|
Category:Inspection Report
MONTHYEARIR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 IR 05000003/20230012023-05-22022 May 2023 Unions 1, 2 and 3 - NRC Inspection Report Nos. 05000003/2023001, 05000247/2023001, 05000286/2023001, and 07200051/2023001 IR 05000003/20234012023-05-10010 May 2023 NRC Security Decommissioning Inspection Report Nos. 05000003/2023401, 05000247/2023401, and 05000286/2023401 IR 05000003/20220042023-03-13013 March 2023 NRC Inspection Report Nos. 05000003/2022004, 05000247/2022004, 05000286/2022004, and 07200051/2022002 IR 05000003/20220022022-11-17017 November 2022 NRC Inspection Report Nos. 05000003/2022002, 05000003/2022003, 05000247/2022002, 05000247/2022003, 05000286/2022002, 05000286/2022003, and 07200051/2022001 IR 05000003/20224022022-10-28028 October 2022 Reissued NRC Security Decommissioning Inspection Report Nos. 05000003/2022402, 05000247/2022402, and 05000286/2022402 (Letter Only) IR 05000003/20224012022-05-25025 May 2022 NRC Security Decommissioning Inspection Report Nos. 05000003/2022401, 05000247/2022401, and 05000286/2022401 IR 05000003/20220012022-05-25025 May 2022 NRC Inspection Report Nos. 05000003/2022001, 05000247/2022001, and 05000286/2022001 IR 05000003/20210042022-03-0404 March 2022 NRC Inspection Report Nos. 05000003/2021004, 05000247/2021004, 05000286/2021004, and 07200051/2021001 IR 05000003/20210032021-11-0909 November 2021 NRC Inspection Report Nos. 05000003/2021003, 05000247/2021003, and 05000286/2021003 IR 05000003/20210022021-08-0404 August 2021 NRC Inspection Report Nos. 05000003/2021002, 05000247/2021002, and 05000286/2021002 IR 05000286/20210022021-06-0707 June 2021 Integrated Inspection Report 05000286/2021002 IR 05000286/20214022021-05-0505 May 2021 Security Baseline Inspection Report 05000286/2021402 IR 05000003/20210012021-04-21021 April 2021 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Units 1 and 2 - NRC Inspection Report No. 05000003/2021001 and 05000247/2020001 IR 05000286/20210012021-04-15015 April 2021 Integrated Inspection Report 05000286/2021001 IR 05000286/20200062021-03-0303 March 2021 Annual Assessment Letter for Indian Point Energy Center, Unit 3 (Report 05000286/2020006) IR 05000247/20200142021-02-0101 February 2021 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 2 NRC Inspection Report No. 05000247/2020014 IR 05000286/20200042021-01-28028 January 2021 Integrated Inspection Report 05000286/2020004 IR 05000003/20200012020-12-0808 December 2020 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Units 1 and 2, NRC Inspection Report No. 05000003/2020001 and 05000247/2020013 IR 05000286/20200032020-10-28028 October 2020 Integrated Inspection Report 05000286/2020003 IR 05000286/20200102020-09-16016 September 2020 Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000286/2020010 IR 05000286/20200052020-08-31031 August 2020 Updated Inspection Plan for Indian Point Energy Center, Unit 3 (Inspection Report 05000286/2020005) IR 05000247/20200022020-08-10010 August 2020 Integrated Inspection Report 05000247/2020002 and 05000286/2020002 IR 05000286/20200122020-07-27027 July 2020 Design Basis Assurance Inspection (Programs) Inspection Report 05000286/2020012 IR 05000247/20020102020-05-12012 May 2020 Final ASP Analysis - Indian Point 2 (IR 050002472002010) IR 05000247/20200012020-04-29029 April 2020 Integrated Inspection Report 05000247/2020001 and 05000286/2020001 IR 05000247/20190062020-03-0303 March 2020 Annual Assessment Letter for Indian Point Energy Center, Units 2 and 3 (Report 05000247/2019006 and 05000286/2019006) IR 05000247/20190042020-02-10010 February 2020 Integrated Inspection Report 05000247/2019004 and 05000286/2019004 IR 05000003/20190012020-01-16016 January 2020 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 1 - NRC Inspection Report No. 05000003/2019001 IR 05000247/20190122020-01-0909 January 2020 Temporary Instruction 2515/194 Inspection Report 05000247/2019012 and 05000286/2019012 IR 05000247/20194112020-01-0909 January 2020 Material Control and Accounting Program Inspection Report 05000247/2019411 and 05000286/2019411 (Cover Letter Only) IR 05000247/20194032019-11-0505 November 2019 Cyber Security Inspection Report 05000247/2019403 and 05000286/2019403 (Cover Letter Only) IR 05000247/20190032019-11-0404 November 2019 Integrated Inspection Report 05000247/2019003 and 05000286/2019003 IR 05000247/20194102019-10-0202 October 2019 Security Inspection Report 05000247/2019410 and 05000286/2019410 (Cover Letter Only) IR 05000247/20190102019-09-26026 September 2019 Biennial Problem Identification and Resolution Inspection Report 05000247/2019010 and 05000286/2019010 IR 05000247/20190052019-08-28028 August 2019 Updated Inspection Plan (Inspection Report 05000247/2019005 and 05000286/2019005) IR 05000247/20190022019-08-13013 August 2019 Integrated Inspection Report 05000247/2019002 and 05000286/2019002 IR 05000247/20190112019-07-0909 July 2019 Design Basis Assurance Inspection (Programs) Inspection Report 05000247/2019011 and 05000286/2019011 IR 05000247/20190012019-05-13013 May 2019 Integrated Inspection Report 05000247/2019001 and 05000286/2019001 ML19130A0422019-05-0808 May 2019 Information Request for the Cyber-Security Inspection, Notification to Perform Inspection 05000247/2019403 and 05000286/2019403 IR 05000247/20193012019-04-18018 April 2019 Initial Operator Licensing Examination Report 05000247/2019301 IR 05000247/20180062019-03-0404 March 2019 Annual Assessment Letter for Indian Point Energy Center, Units 2 and 3 (Reports 05000247/2018006 and 05000286/2018006) IR 05000247/20180042019-02-0707 February 2019 Integrated Inspection Report 05000247/2018004 and 05000286/2018004 IR 05000247/20180102019-01-15015 January 2019 Design Bases Assurance Inspection (Teams) Report 05000247/2018010 and 05000286/2018010 IR 05000247/20180022019-01-0909 January 2019 Errata for Indian Point Nuclear Generating - Integrated Inspection Report 05000247/2018002 and 05000286/2018002 IR 05000247/20184102018-12-0606 December 2018 Security Inspection Report 05000247/2018410 and 05000286/2018410 (Cover Letter Only) IR 05000247/20182012018-11-27027 November 2018 NRC Inspection Report 05000247/2018201 and 05000286/2018201 IR 05000247/20180032018-11-0808 November 2018 Integrated Inspection Report 05000247/2018003 and 05000286/2018003 IR 05000003/20180012018-10-25025 October 2018 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 1 - NRC Inspection Report No. 05000003/2018001 Dated October 25, 2018 2023-08-22
[Table view] Category:Letter
MONTHYEARML24011A1982024-01-12012 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 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 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency 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 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 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 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) 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 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 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 ML23194A0442023-07-11011 July 2023 Clarification for Indian Point Energy Center License Amendment Request, Independent Spent Fuel Storage Installation Physical Security Plan ML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23171B0432023-06-23023 June 2023 Letter - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML23118A0972023-06-0606 June 2023 06-06-23 Letter to the Honorable Michael V. Lawler, Et Al., from Chair Hanson Regarding Holtec'S Announcement to Expedite Plans to Release Over 500,000 Gallons of Radioactive Wastewater from Indian Point Energy Center Into the Hudson River ML23144A3512023-05-25025 May 2023 Clementina Bartolotta of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3522023-05-25025 May 2023 Loredana Bidmead of New York E-Mail Against Treated Water Release from Indian Point Site ML23144A3412023-05-25025 May 2023 Dianne Schirripa of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23144A3472023-05-25025 May 2023 David Mart of Blauvelt, New York Email Against Treated Water Release from Indian Point Site ML23144A3402023-05-25025 May 2023 Melvin Israel of New York Email Against Treated Water Release from Indian Point Site ML23144A3542023-05-25025 May 2023 Terri Thal of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3532023-05-25025 May 2023 John Shaw of New York Email Against Treated Water Release from Indian Point Site 2024-01-09
[Table view] |
Text
UNITED STATES NUCLEAR REGU LATORY COMMISSION W
REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PA 19406.1415 January 25, 20LI Mr. Joseph E. Pollock Site Vice President Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 1051 1-0249
SUBJECT:
INDIAN POINT NUCLEAR GENEMTING UNIT 3 - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
Dear Mr. Pollock:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region I staff will conduct a triennial fire protection baseline inspection at the lndian Point Nuclear Generating Unit 3 in May 2011. The inspection team will be led by Dan Orr from the NRC Region I office. The team will be composed of personnel from the NRC Region l. The inspection will be conducted in accordance with NRC inspection procedure 71 1 1 1.05T, the NRC's baseline fire protection inspection procedure.
The schedule for the inspection is as follows:
. lnformation gathering visit - Week of April 25,2011 o Weeks of onsite inspection - May 9,2011 and May 23,2011 The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, to become familiar with the station fire protection programs, fire protection features, post-fire safe shutdown capabilities, plant layout and, as necessary, obtain plant specific site access training and badging for unescorted access. A list of the types of documents the team may be interested in reviewing and possibly obtaining, are listed in . The team leader will contact you with specific document requests prior to the information gathering visit.
During the information gathering visit, the team will also discuss the following inspection support administrative details: office space size and location; specific documents requested to be made available to the team in their office spaces; arrangements for reactor site access, including radiation protection training, security, safety, and fitness for duty requirements; and the availability of knowledgeable plant engineering and licensing organization personnel to serve as points of contact during the inspection.
J. Pollock We request that during the onsite inspection week you ensure that copies of analyses, evaluations, or documentation regarding the implementation and maintenance of the Indian Point Nuclear Generating Unit 3 fire protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest for the fire protection portion of the inspection are those documents which establish that your fire protection program satisfies NRC regulatory requirements and conforms to applicable NRC and industry fire protection guidance. Also, personnel should be available at the site during the inspection who are knowledgeable regarding those plant systems required to achieve and maintain safe shutdown conditions from inside and outside the control room, including the electrical aspects of the relevant post-fire safe shutdown analyses, reactor plant fire protection systems and features, and the Indian Point Nuclear Generating Unit 3 fire protection program and its implementation.
This letter does not contain new or amended information collection requirements subject to the Papenrvork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control number 3150-001 1. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
Your cooperation and support during this inspection will be appreciated. lf you have questions concerning this inspection, or the inspection team's information or logistical needs, please contact Dan Orr, the team leader in the Region I Office at (610) 337-5048.
Sincerely, Y.
Engineering Branch 3 Division of Reactor Safety Docket No: 50-286 License No: DPR-64
Enclosure:
List of Reactor Fire Protection Program Supporting Documentation cc wiEncl: Distribution via ListServ
J. Pollock 2 We request that during the onsite inspection week you ensure that copies of analyses, evaluations, or documentation regarding the implementation and maintenance of the lndian Point Nuclear Generating Unit 3 fire protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest for the fire protection portion of the inspection are those documents which establish that your fire protection program satisfies NRC regulatory requirements and conforms to applicable NRC and industry fire protection guidance. Also, personnel should be available at the site during the inspection who are knowledgeable regarding those plant systems required to achieve and maintain safe shutdown conditions from inside and outside the control room, including the electrical aspects of the relevant post-fire safe shutdown analyses, reactor plant fire protection systems and features, and the Indian Point Nuclear Generating Unit 3 fire protection program and its implementation.
This letter does not contain new or amended information collection requirements subject to the Papenvork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
Your cooperation and support during this inspection will be appreciated. lf you have questions concerning this inspection, or the inspection team's information or logistical needs, please contact Dan Or, the team leader in the Region l Office at (610) 337-5048.
Sincerely,
/RN John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket No: 50-286 License No: DPR-64
Enclosure:
List of Reactor Fire Protection Program Supporting Documentation cc w/Encl: Distribution via ListServ SUNSI Review Complete: JFR (Reviewer's lnitials) ADAMS ACC#M1110250538 DOCUMENT NAME: G;\DRS\Engineering Branch 3\90 Day Lefters\lP3 Triennial Fire Protection 90 Day Letter.doc After declaring this document "An Official Agency Record" it will be released to the Public.
To receive a copy of this Indicate in the box: "C" = Copy without attachmenVenclosure with attachmenVenclosure "N" = No DATE 01124111 OFFICIAL RECORD COPY
J. Pollock 3 Distribution MEncl: (Via E-Mail)
W. Dean, RA (RIoRAMATL RESOURCE)
D. Lew, DRA (RIoRAMATL RESOURCE)
J. Clifford, DRP (RI DRPMATL RESOURCE)
D. Roberts, DRS (RIDRSMAIL Resource)
P. Wilson, DRS (RIDRSMAIL Resource)
G. Miller, Rl OEDO M. Gray, DRP B. Bickett, DRP S. McCarver, DRP M. Jennerich, DRP P. Cataldo, SRI M. Halter, Rl D. Hochmuth, DRP D. Bearde, DRS RidsNrrPMl ndianPoint Resource RidsNrrDorlLpl 1 -1 Resource J. Rogge, DRS D. Orr, DRS DRS File
ENCLOSURE Reactor Fire Protection Program Supporting Documentation
[Note: This is a broad list of the documents the NRC inspection team may be interested in reviewing, and possibly obtaining, during the information gathering site visit.l
't. The current version of the Fire Protection Program and Fire Hazards Analysis.
- 2. Allfire protection program licensing basis documents such as FPP Operating License Condition, applicable UFSAR sections, and FPP SERs with associated correspondence.
- 3. Current versions of the fire protection program implementing procedures (e.9.,
administrative controls, surveillance testing, and fire brigade.)
- 4. Fire brigade training program and pre-fire plans.
- 5. Post-fire safe shutdown analysis.
- 6. Piping and instrumentation (flow) diagrams showing the systems and components used to achieve and maintain hot standby and cold shutdown for fires outside the control room and those components used for those areas requiring alternative shutdown capability.
- 7. Plant layout drawings which identify the physical plant locations of hot standby and cold shutdown equipment.
- 8. Plant layout drawings which identify plant fire area delineation, areas protected by automatic fire suppression and detection, and the locations of fire protection equipment.
- 9. Plant layout drawings which identify the location of post-fire emergency lighting units.
- 10. Plant operating procedures which would be used for shutdown from the control room with a postulated fire occurring in any plant area outside the control room, and procedures which would be used to implement alternative shutdown capability in the event of a fire in either the control or cable spreading room.
- 11. Copy of most recently completed maintenance and surveillance testing procedures for alternative shutdown capability components, fire barriers, fire detectors, fire pumps and suppression systems.
- 12. Maintenance procedures which routinely verify fuse and circuit breaker coordination in accordance with the post-fire safe shutdown coordination analysis'
- 13. A listing of significant fire protection and post-fire safe shutdown related design change packages (including their associated 10 CFR 50.59 evaluations) and Generic Letter 86-10 evaluations.
- 14. The reactor plant's IPEEE, results of any post-IEEE reviews, and listings of actions taken/plant modifications conducted in response to IEEE information.
Enclosure
2
- 15. Organization charts of site personnel down to the level of fire protection staff personnel.
- 16. Procedures/instructions that control the configuration of the reactor plant's fire protection program, features and post-fire safe shutdown methodology and system design.
- 17. A list of applicable codes and standards related to the design of plant fire protection features and evaluations of all code deviations.
- 18. The three most recent fire protection QA audits and/or fire protection self-assessments.
- 19. Recent (last 12 months) QA surveillances of fire protection activities.
- 20. A listing of open fire protection and fire safe shutdown related condition reports and a listing of fire protection and fire safe shutdown condition reports closed in the past three years.
- 21. Fire protection system health reports (last 2).
- 22. Lesson plans and related training information for licensed and non-licensed operators for post-fire safe shutdown including alternative shutdown.
- 23. Copies of AC and DC electrical system one line diagrams. (From offsite power grid connections down to the 120 volt level.)
Enclosure