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Category:Inspection Report Correspondence
MONTHYEARIR 05000220/20184102018-10-16016 October 2018 Material Control and Accounting Program Inspection Report 05000220/2018410 and 05000410/2018410 (Letter Only) IR 05000220/20070012007-03-0202 March 2007 Annual Assessment Letter - Nine Mile Point Nuclear Station (Report 05000220-07-001 and 05000410-07-001) ML0527205072005-09-29029 September 2005 Requalification Program Inspection - Nine Mile Point Nuclear Station, Unit 2 ML0534600942005-09-12012 September 2005 Inspection Request, NMP PI&R - IR 2005-007 IR 05000220/20040052005-01-26026 January 2005 IR 05000220-04-005, 05000410-04-005; on 10/01/2004 - 12/31/2004; Nine Mile Point, Units 1 and 2; Licensed Operator Requalification Program and Operability Evaluations IR 05000220/20030082003-06-16016 June 2003 IR 05000220-03-008, IR 05000410-03-008, on 05/05/2003 - 05/08/2003, Nine Mile Point Nuclear Station Unit 1 and Unit 2, Temporary Instruction 2515/148, Inspection of Nuclear Reactor Safeguards Interim Compensatory Measures. ML0308500772003-03-26026 March 2003 Notification of Conduct of a Triennial Fire Protection Baseline Inspection IR 05000220/20020042002-07-19019 July 2002 IR 05000220-02-004, IR 05000410-02-004, on 05/19-06/29/2002, Nine Mile Point Nuclear Station, LLC, Nine Mile Point, Units 1 & 2. Resident Inspector Report IR 05000220/20020032002-06-0707 June 2002 IR 05000220-02-03, IR 05000410-02-03, on 3/31-5/18/2002; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Resident Inspector Report. No Violations Identified IR 05000220/20020022002-04-26026 April 2002 IR 05000220/2002-002, IR 05000410/2002-002, on 2/17-4/6/2002; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Resident Inspector Report. No Violations Identified IR 05000220/20010112002-03-21021 March 2002 IR 05000220/2001-011, IR 05000410/2001-011, on 12/30/01-02/15/2002; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Emergency Work Control. Non-cited Violations Identified IR 05000220/20010102002-01-24024 January 2002 IR 05000220/2001-010, IR 05000410/2001-010, on 11/11-12/29/2001; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Resident Inspector Report. No Violations ML18018B0742000-03-27027 March 2000 ADAMS Distribution Notification ML17037C1621974-09-0404 September 1974 Letter Referring to Two Significant Matters Identified During the August 26 to 30, 1974 Inspection at Nine Mile Point-1 Reactor Facility ML17037C2091974-06-13013 June 1974 Letter Responding to the May 30, 1974 Letter Informing the Commission of the Corrective and Preventive Actions in Response to a May 15, 1974 Letter ML17037C2141973-11-14014 November 1973 Letter Responding to the September 13, 1973 Informing the Commission of the Action Taken to Correct the Items of Noncompliance Following the Recent Inspection and Advising That the Action Will Be Verified During the Next .. ML17037C2151973-10-25025 October 1973 Letter Responding to the September 10, 1973 Letter Informing the Commission of the Action Taken to Correct the Item of Noncompliance Brought to Attention Following the Recent Inspection and Advising That Corrective Action .. ML17037C1111972-08-10010 August 1972 Letter Regarding Action Taken in Response to a June 22, 1972 Letter Relating to Wall Thickness of Nuclear Service Valves ML17037C0991972-05-10010 May 1972 Letter Responding to an April 14, 1972 Letter Requesting Results of the Inspection on the Pressure Suppression Torus 2018-10-16
[Table view] Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
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March 26, 2003 Mr. John T. Conway Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC.
P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT UNIT 2 - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
Dear Mr. Conway:
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 Nine Mile Point Unit 2 Nuclear Station in June, 2003. The inspection team will be led by Mr. Larry Scholl, a senior reactor inspector from the NRC Region I Office. The team will be composed of NRC personnel. The inspection will be conducted in accordance with IP 71111.05, the NRCs baseline fire protection inspection procedure.
The schedule for the inspection is as follows:
- Information gathering visit - Week of May 12, 2003
- Onsite inspection - Weeks of June 2 and 16, 2003 The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, to become familiar with the Nine Mile Point Unit 2 fire protection programs, fire protection features, and post-fire safe shutdown capabilities and plant layout, and, as necessary, obtain plant specific site access training and badging for unescorted site access. The types of documents the team may be interested in reviewing, and possibly obtaining, are listed in Enclosure 1. The inspection team leader will contact you with specific document requests and inform you of plant areas for inspection focus.
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 and safety); and the availability of knowledgeable plant engineering and licensing organization personnel to serve as points of contact during the inspection.
Mr. J. Conway 2 We request that during the onsite inspection you ensure that copies of analyses, evaluations or documentation regarding the implementation and maintenance of the Nine Mile Point Unit 2 fire protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest 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 Nine Mile Point Unit 2 fire protection program and its implementation.
Your cooperation and support during this inspection will be appreciated. If you have questions concerning this inspection, or the inspection teams information or logistical needs, please contact Mr. Larry Scholl, the team leader, in the Region I Office at (610) 337-5144 or by e-mail at LLS@nrc.gov.
Sincerely,
/RA/
James C. Linville, Chief Electrical Branch Division of Reactor Safety Docket No. 50-410 License No. NPF-69
Enclosure:
List of Reactor Fire Protection Program Supporting Documents
Mr. J. Conway 3 cc w/encl: M. J. Wallace, President, Nine Mile Point Nuclear Station, LLC M. Wetterhahn, Esquire, Winston and Strawn J. M. Petro, Jr., Esquire, Counsel, Constellation Power Source, Inc.
P. D. Eddy, Electric Division, NYS Department of Public Service C. Donaldson, Esquire, Assistant Attorney General, New York Department of Law J. V. Vinquist, MATS, Inc.
W. M. Flynn, President, New York State Energy Research and Development Authority Supervisor, Town of Scriba C. Adrienne Rhodes, Chairman and Executive Director, State Consumer Protection Board T. Judson, Central NY Citizens Awareness Network
Mr. J. Conway 4 Distribution w/encl:
Region I Docket Room (with concurrences)
H. Miller, RA J. Wiggins, DRA J. Trapp, DRP T. McGinty, RI EDO Coordinator R. Laufer, NRR P. Tam, PM, NRR D. Skay/T. Colburn, PM, NRR (Backup)
G. Hunegs, SRI - Nine Mile Point B. Fuller, RI - Nine Mile Point N. Perry, DRP DOCUMENT NAME: G:\Electrical\Scholl\NMP-2fpltr.wpd After declaring this document An Official Agency Record it will be released to the Public.
To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RI/DRS E RI/DRS NAME LScholl JLinville DATE 03/25/03 03/25/03 OFFICIAL RECORD COPY
ENCLOSURE 1 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.]
- 1. The current version of the Fire Protection Program and Fire Hazards Analysis.
- 2. Current versions of the fire protection program implementing procedures (e.g.,
administrative controls, surveillance testing, fire brigade, technical requirements manual).
- 3. Fire brigade training program and pre-fire plans.
- 4. Post-fire safe shutdown analysis, including systems and separation analysis, as well as alternative shutdown analysis.
- 5. Piping and instrumentation (flow) diagrams for fire protection suppression systems.
- 6. Piping and instrumentation (flow) diagrams showing the 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 and equipment 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 general location of the post-fire emergency lighting units.
- 10. Plant operating procedures which would be used and describe shutdown from inside 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 (or any other alternative shutdown area).
- 11. Maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, 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. Significant fire protection and post-fire safe shutdown related design change packages (including the associated 10 CFR 50.59 evaluations) and Generic Letter 86-10 evaluations.
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- 14. The reactor plants IPEEE, results of any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in response to IPEEE information associated with fires.
- 15. Procedures/instructions that govern the implementation of plant modifications, temporary modifications, maintenance, and special operations, and their impact on fire protection.
- 16. Organization charts of site personnel down to the level of fire protection staff personnel.
- 17. Listing of plant fire protection licensing basis documents (i.e., a listing of the SERs and change evaluations which form the licensing basis for the reactor plants post-fire safe shutdown configuration).
- 18. Procedures/instructions that control the configuration of the reactor plants fire protection program, features, and post-fire safe shutdown methodology and system design.
- 19. A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations (i.e, a listing of the NFPA code versions committed to (NFPA codes of record)).
- 20. A listing of all open condition reports associated with fire protection or Appendix R safe shutdown issues (problem reports/NCRs/EARs/problem identification and resolution reports).
- 21. A listing of condition reports associated with fire protection or Appendix R safe shutdown issues (problem reports/NCRs/EARs/problem identification and resolution reports) that have been closed within the last three years.
- 22. The three most recent fire protection QA audits and/or fire protection self-assessments.
- 23. Copies of QA surveillances of fire protection activities performed in the last three years.
- 24. Electrical one-line drawings showing the power supplies (normal and emergency) for hot standby and cold shutdown equipment (including instrumentation and control circuits necessary for safe shutdown).