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| | number = ML082050452 | | | number = ML082050452 |
| | issue date = 07/23/2008 | | | issue date = 07/23/2008 |
| | title = Millstone Power Station Unit 2 - Notification of Conduct of a Triennial Fire Protection Baseline Inspection | | | title = Notification of Conduct of a Triennial Fire Protection Baseline Inspection |
| | author name = Rogge J F | | | author name = Rogge J |
| | author affiliation = NRC/RGN-I/DRS/EB3 | | | author affiliation = NRC/RGN-I/DRS/EB3 |
| | addressee name = Christian D | | | addressee name = Christian D |
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| =Text= | | =Text= |
| {{#Wiki_filter:July 23, 2008 | | {{#Wiki_filter:July 23, 2008 Mr. David Christian Sr. Vice President and Chief Nuclear Officer Dominion Resources 5000 Dominion Boulevard Glenn Allen, VA 23060-6711 |
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| Mr. David Christian Sr. Vice President and Chief Nuclear Officer Dominion Resources 5000 Dominion Boulevard Glenn Allen, VA 23060-6711 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| MILLSTONE POWER STATION UNIT 2 - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION | | MILLSTONE POWER STATION UNIT 2 - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION |
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| ==Dear Mr. Christian:== | | ==Dear Mr. Christian:== |
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| The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC) | | 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 Millstone Power Station Unit 2 beginning in November 2008. The inspection team will be led by Keith Young from the NRC Region I office. The team will be composed of personnel from the NRC Region I. | | Region I staff will conduct a triennial fire protection baseline inspection at Millstone Power Station Unit 2 beginning in November 2008. The inspection team will be led by Keith Young from the NRC Region I office. The team will be composed of personnel from the NRC Region I. |
| The inspection will be conducted in accordance with NRC inspection procedure 71111.05T, the NRC's baseline fire protection inspection procedure. | | The inspection will be conducted in accordance with NRC inspection procedure 71111.05T, the NRCs baseline fire protection inspection procedure. |
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| The schedule for the inspection is as follows: | | The schedule for the inspection is as follows: |
| * Information gathering visit - Week of November 3, 2008 | | * Information gathering visit - Week of November 3, 2008 |
| * Weeks of onsite inspection - November 17 - 21 and December 1 - 5, 2008 | | * Weeks of onsite inspection - November 17 - 21 and December 1 - 5, 2008 The purpose 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, and post-fire safe shutdown capabilities and 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 Enclosure 1. 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. |
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| The purpose 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, and post-fire safe shutdown capabilities and 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 Enclosure 1. The team leader will contact you with specific document requests prior to the information gathering visit.
| | Mr. David Christian 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 Millstone Power Station 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 as 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 Millstone Power Station 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 Keith Young, the team leader in the Region I Office at (610) 337-5293. |
| | Sincerely, |
| | /RA/ |
| | John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-336 License No. DPR-65 |
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| 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.
| | ==Enclosure:== |
| | List of Reactor Fire Protection Program Supporting Documents |
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| Mr. David Christian 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 Millstone Power Station 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 as 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 Millstone Power Station Unit 2 fire protection program and its implementation. | | Mr. David Christian 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 Millstone Power Station 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 as 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 Millstone Power Station 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 Keith Young, the team leader in the Region I Office at (610) 337-5293. |
| Your cooperation and support during this inspection will be appreciated. If you have questions concerning this inspection, or the inspection team's information or logistical needs, please contact Keith Young, the team leader in the Region I Office at (610) 337-5293. | | Sincerely, John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-336 License No. DPR-65 |
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| Sincerely, | |
| /RA/ John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety
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| Docket No. 50-336 License No. DPR-65 | |
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| ==Enclosure:== | | ==Enclosure:== |
| List of Reactor Fire Protection Program Supporting Documents Mr. David Christian 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 Millstone Power Station 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 as 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 Millstone Power Station Unit 2 fire protection program and its implementation. | | List of Reactor Fire Protection Program Supporting Documents SUNSI Review Complete: JFR (Reviewers Initials) |
| | DOCUMENT NAME: G:\DRS\Engineering Branch 3\Young\MILL-U2 FP 90 Day Letter-2008.doc 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 RI/DRS NAME KAYoung/klg KAY JFRogge/ JFR DATE 07/ 23/2008 07/23/2008 OFFICIAL RECORD COPY ML#082050452 |
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| Your cooperation and support during this inspection will be appreciated. If you have questions concerning this inspection, or the inspection team's information or logistical needs, please contact Keith Young, the team leader in the Region I Office at (610) 337-5293.
| | Mr. David Christian 3 cc w/encl: |
| | | J. A. Price, Site Vice President, Millstone Station C. L. Funderburk, Director, Nuclear Licensing and Operations Support W. Barton, Supervisor, Station Licensing J. Spence, Manager Nuclear Training L. M. Cuoco, Senior Counsel C. Brinkman, Manager, Washington Nuclear Operations J. Roy, Director of Operations, Massachusetts Municipal Wholesale Electric Company First Selectmen, Town of Waterford B. Sheehan, Co-Chair, NEAC E. Woollacott, Co-Chair, NEAC E. Wilds, Jr., Ph.D, Director, State of Connecticut SLO Designee J. Buckingham, Department of Public Utility Control C. Meek-Gallagher, Commissioner, Suffolk County, Department of Environment and Energy V. Minei, P.E., Director, Suffolk County Health Department, Division of Environmental Quality R. Shadis, New England Coalition Staff S. Comley, We The People D. Katz, Citizens Awareness Network (CAN) |
| Sincerely,
| | R. Bassilakis, CAN J. M. Block, Attorney, CAN P. Eddy, Electric Division, Department of Public Service, State of New York P. Tonko, President and CEO, New York State Energy Research and Development Authority J. Spath, SLO Designee, New York State Energy Research and Development Authority N. Burton, Esq. |
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| John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety
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| Docket No. 50-336 License No. DPR-65
| | Mr. David Christian 3 Distribution w/encl: VIA E-MAIL S. Collins, RA M. Dapas, DRA M. Gamberoni, DRS D. Roberts, DRS S. Williams, RI OEDO M. Kowal, NRR R. Nelson, NRR J. Hughey NRR, PM J. Lamb, NRR, PM S. Shaffer, SRI J. Benjamin, RI J. Krafty, RI D. Jackson, DRP B. Norris, DRP, Acting Branch Chief N. Sieller, DRP J. Rogge, DRS K. Young, DRS |
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| ==Enclosure:==
| | ENCLOSURE Reactor Fire Protection Program Supporting Documentation |
| List of Reactor Fire Protection Program Supporting Documents
| | [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, and fire brigade.) |
| | : 3. Fire brigade training program and pre-fire plans. |
| | : 4. Post-fire safe shutdown systems and separation analysis. |
| | : 5. Post-fire alternative 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 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 fie protection equipment. |
| | : 9. Plant layout drawings which identify the location of the 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. Maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, pumps and suppression systems. (Last completed copy.) |
| | : 12. Maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis. |
| | : 13. A list of 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 plants IPEEE, results of any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in response to IPEEE information. |
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| SUNSI Review Complete: JFR (Reviewer's Initials) DOCUMENT NAME: G:\DRS\Engineering Branch 3\Young\MILL-U2 FP 90 Day Letter-2008.doc 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:
| | 2 |
| " C" = Copy without attachment/enclosure " E" = Copy with attachment/enclosure " N" = No copy OFFICE RI/DRS RI/DRS NAME KAYoung/klg KAY JFRogge/ JFR DATE 07/ 23/2008 07/23/2008 OFFICIAL RECORD COPY ML#082050452 Mr. David Christian 3 cc w/encl:
| | : 15. Copies of AC and DC electrical system one line diagrams. (From offsite power grid connections down to the 120 volt level.) |
| J. A. Price, Site Vice President, Millstone Station C. L. Funderburk, Director, Nuclear Licensing and Operations Support W. Barton, Supervisor, Station Licensing J. Spence, Manager Nuclear Training L. M. Cuoco, Senior Counsel C. Brinkman, Manager, Washington Nuclear Operations J. Roy, Director of Operations, Massachusetts Municipal Wholesale Electric Company First Selectmen, Town of Waterford B. Sheehan, Co-Chair, NEAC E. Woollacott, Co-Chair, NEAC E. Wilds, Jr., Ph.D, Director, State of Connecticut SLO Designee J. Buckingham, Department of Public Utility Control C. Meek-Gallagher, Commissioner, Suffolk County, Department of Environment and Energy V. Minei, P.E., Director, Suffolk County Health Department, Division of Environmental Quality R. Shadis, New England Coalition Staff S. Comley, We The People D. Katz, Citizens Awareness Network (CAN)
| | : 16. Organization charts of site personnel down to the level of fire protection staff personnel. |
| R. Bassilakis, CAN J. M. Block, Attorney, CAN P. Eddy, Electric Division, Department of Public Service, State of New York P. Tonko, President and CEO, New York State Energy Research and Development Authority J. Spath, SLO Designee, New York State Energy Research and Development Authority N. Burton, Esq.
| | : 17. A listing of the SERs which form the licensing basis for the reactor plants post-fire safe shutdown configuration. |
| Mr. David Christian 3 Distribution w/encl
| | : 18. A list of applicable codes and standards related to the design of plant fie protection features and evaluations of code deviations. |
| : VIA E-MAIL S. Collins, RA M. Dapas, DRA M. Gamberoni, DRS D. Roberts, DRS S. Williams, RI OEDO M. Kowal, NRR R. Nelson, NRR J. Hughey NRR, PM J. Lamb, NRR, PM S. Shaffer, SRI J. Benjamin, RI J. Krafty, RI D. Jackson, DRP B. Norris, DRP, Acting Branch Chief N. Sieller, DRP J. Rogge, DRS K. Young, DRS ENCLOSURE Reactor Fire Protection Program Supporting Documentation
| | : 19. Procedures/instructions that govern the implementation of plant modifications, temporary modifications, maintenance, and special operations, and their impact on fire protection. |
| [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.]
| | : 20. The three most recent fire protection QA audits and/or fire protection self-assessments. |
| : 1. The current version of the Fire Protection Program and Fire Hazards Analysis.
| | : 21. Recent QA surveillances of fire protection activities. |
| : 2. Current versions of the fire protection program implementing procedures (e.g., administrative controls, surveillance testing, and fire brigade.)
| | : 22. A listing of open fire protection and fire safe shutdown related condition reports. |
| : 3. Fire brigade training program and pre-fire plans.
| | : 23. A listing of fire protection and fie safe shutdown condition reports closed in the past three years. |
| : 4. Post-fire safe shutdown systems and separation analysis.
| | : 24. Fire protection system health reports (last 2). |
| : 5. Post-fire alternative shutdown analysis.
| | : 25. Lesson plans and related training information for licensed and non-licensed operators for post-fire safe shutdown (including alternative shutdown). |
| : 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.
| | Enclosure}} |
| : 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 fie protection equipment.
| |
| : 9. Plant layout drawings which identify the location of the 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. Maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, pumps and suppression systems. (Last completed copy.)
| |
| : 12. Maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis.
| |
| : 13. A list of 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-IPEEE reviews, and listings of actions taken/plant modifications conducted in response to IPEEE information.
| |
| 2 Enclosure | |
| : 15. Copies of AC and DC electrical system one line diagrams. (From offsite power grid connections down to the 120 volt level.) | |
| : 16. Organization charts of site personnel down to the level of fire protection staff personnel. | |
| : 17. A listing of the SERs which form the licensing basis for the reactor plant's post-fire safe shutdown configuration. | |
| : 18. A list of applicable codes and standards related to the design of plant fie protection features and evaluations of code deviations. | |
| : 19. Procedures/instructions that govern the implementation of plant modifications, temporary modifications, maintenance, and special operations, and their impact on fire protection. | |
| : 20. The three most recent fire protection QA audits and/or fire protection self-assessments. | |
| : 21. Recent QA surveillances of fire protection activities. | |
| : 22. A listing of open fire protection and fire safe shutdown related condition reports. | |
| : 23. A listing of fire protection and fie safe shutdown condition reports closed in the past three years. | |
| : 24. Fire protection system health reports (last 2). | |
| : 25. Lesson plans and related training information for licensed and non-licensed operators for post-fire safe shutdown (including alternative shutdown).}} | |
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Category:Inspection Report
MONTHYEARIR 05000336/20240052024-08-29029 August 2024
Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005
IR 05000336/20240022024-08-13013 August 2024
Integrated Inspection Report 05000336/2024002 and 05000423/2024002
IR 05000336/20244412024-08-0606 August 2024
Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only)
IR 05000336/20244032024-07-22022 July 2024
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403
IR 05000336/20245012024-07-0101 July 2024
Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501
IR 05000336/20240102024-06-26026 June 2024
Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010
ML24142A0952024-05-20020 May 2024
End of Cycle 22 Steam Generator Tube Inspection Report
IR 05000336/20240012024-05-14014 May 2024
Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation
IR 05000336/20244012024-04-30030 April 2024
Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only)
IR 05000336/20244402024-04-25025 April 2024
Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only)
IR 05000336/20240112024-04-0101 April 2024
Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011
IR 05000336/20230062024-02-28028 February 2024
Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006)
IR 05000336/20230042024-02-14014 February 2024
Integrated Inspection Report 05000336/2023004 and 05000423/2023004
IR 05000336/20234022024-01-30030 January 2024
Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only)
IR 05000336/20234402024-01-11011 January 2024
Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only)
IR 05000336/20230032023-11-0606 November 2023
Integrated Inspection Report 05000336/2023003 and 05000423/2023003
IR 05000336/20234202023-10-0404 October 2023
Security Inspection Report 05000336/2023420 and 05000423/2023420
IR 05000245/20230012023-09-19019 September 2023
Safstor Inspection Report 05000245/2023001
IR 05000336/20230102023-09-0808 September 2023
Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010
IR 05000336/20230052023-08-31031 August 2023
Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005)
IR 05000336/20230022023-08-0909 August 2023
Integrated Inspection Report 05000336/2023002 and 05000423/2023002
IR 05000336/20234012023-07-17017 July 2023
Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only)
IR 07200047/20234012023-06-0808 June 2023
NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401
IR 05000336/20230012023-05-0808 May 2023
Integrated Inspection Report 05000336/2023001 and 05000423/2023001
IR 05000336/20234032023-05-0202 May 2023
Public - Millstone Power Station, Units 2 and 3 Final Significance Determination of Green Finding; Inspection Report 05000336/2023403 and 05000423/2023403
IR 05000336/20233022023-03-0707 March 2023
Operator Licensing Retake Examination Report 05000336/2023302
IR 05000336/20220062023-03-0101 March 2023
Annual Assessment Letter for Millstone Power Station, Units 2 and 3 (Reports 05000336/2022006 and 05000423/2022006)
IR 05000336/20220042023-02-13013 February 2023
Integrated Inspection Report 05000336/2022004 and 05000423/2022004
IR 05000336/20224012023-01-26026 January 2023
Security Baseline Inspection Report 05000336/2022401 and 05000423/2022401 and Preliminary Finding(S) of Greater than Very Low Significance and Apparent Violation(S) (Cover Letter Only)
IR 05000245/20220012023-01-0909 January 2023
Safstor Inspection Report 05000245/2022001
IR 05000336/20224032023-01-0505 January 2023
Cyber Security Inspection Report 05000336/2022403 and 05000423/2022403
IR 05000336/20225012022-12-14014 December 2022
Reissued Emergency Preparedness Biennial Exercise Inspection Report 05000336/2022501 and 05000423/2022501
IR 05000336/20223012022-11-22022 November 2022
Initial Operator Licensing Examination Report 05000336/2022301
ML22325A1042022-11-21021 November 2022
Emergency Preparedness Biennial Exercise Inspection Report 05000336/2022501 and 05000423/2022501
IR 05000336/20220032022-11-14014 November 2022
Integrated Inspection Report 05000336/2022003 and 05000423/2022003
IR 05000336/20220102022-11-0101 November 2022
Biennial Problem Identification and Resolution Inspection Report 05000336/2022010 and 05000423/2022010
IR 05000336/20220112022-09-0808 September 2022
Triennial Fire Protection Inspection Report 05000336/2022011 and 05000423/2022011
IR 05000336/20220052022-08-31031 August 2022
Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2022005 and 05000423/2022005)
IR 05000336/20220022022-08-11011 August 2022
Integrated Inspection Report 05000336/2022002 and 05000423/2022002
IR 05000336/20224022022-05-23023 May 2022
Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000336/2022402 and 05000423/2022402
IR 05000336/20220012022-05-10010 May 2022
Integrated Inspection Report 05000336/2022001 and 05000423/2022001
IR 05000423/20223022022-03-0707 March 2022
Operator Licensing Retake Examination Report 05000423/2022302
IR 05000336/20210062022-03-0202 March 2022
Annual Assessment Letter for Millstone Power Station, Units 2 and 3 (Reports 05000336/2021006 and 05000423/2021006)
IR 05000336/20210042022-02-10010 February 2022
Integrated Inspection Report 05000336/2021004 and 05000423/2021004
IR 05000336/20210112022-01-20020 January 2022
Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000336/2021011
IR 05000336/20210032021-11-12012 November 2021
Integrated Inspection Report 05000336/2021003 and 05000423/2021003
IR 05000423/20213012021-11-10010 November 2021
Initial Operator Licensing Examination Report 05000423/2021301
IR 05000336/20210052021-09-0101 September 2021
Updated Inspection Plan for the Millstone Power Station, Units 2 and 3 (Report 05000336/2021005 and 05000423/2021005)
IR 05000336/20210022021-08-0909 August 2021
Integrated Inspection Report 05000336/2021002 and 05000423/2021002 and Independent Spent Fuel Storage Installation Inspection Report 07200047/2021002
IR 05000245/20210012021-07-26026 July 2021
Safe Storage Inspection Report 05000245/2021001
2024-08-06
[Table view]
Category:Inspection Report Correspondence
MONTHYEARIR 05000245/20164032016-09-29029 September 2016
Millstone Power Station, Units 2 and 3 - Security Inspection Report 05000336/2016403 and 05000423/2016403. Letter Only
IR 05000336/20164032016-09-29029 September 2016
Security Inspection Report 05000336/2016403 and 05000423/2016403. Letter Only
ML0902800902009-01-27027 January 2009
Notification of Inspection and Request for Information
ML0820504522008-07-23023 July 2008
Notification of Conduct of a Triennial Fire Protection Baseline Inspection
IR 05000336/20052022007-10-0303 October 2007
Letter to Mr. D. Christian - Millstone Power Station, Units 2 and 3 - NRC Material Control and Accounting Program Inspection Report No. 05000336/2005202 and 05000423/2005202
ML0631102852006-11-0606 November 2006
Response to Evaluation of a Non-cited Violation (NRC Integrated Inspection Report Numbers 05000336/2006006 and 05000423/2006006
IR 05000336/20060122006-10-0404 October 2006
IR 05000336-06-012, IR 05000423-06-012, 08/21/2006 - 08/25/2006, Millstone Power Station, Units 2 and 3, Physical Protection
IR 05000336/20060152006-08-25025 August 2006
IR 05000336/2006015 and 05000423/2006015; Millstone Power Station, Units 2 and 3; Ti 2515/168
IR 05000336/20050022005-08-10010 August 2005
EA-05-156; Response Letter to Mr. Grecheck (Dominion) from NRC Disputed Violation in Inspection Report 05000336-05-002 and 05000423-05-002
ML0515803152004-10-0404 October 2004
Review of Millstone Unit 2 Steam Generator Tube Inspection Reports for Their 2003 Outage
IR 05000336/20040132004-06-0303 June 2004
IR 05000336-04-013, IR 05000423-04-013, on 05/03/2004-05/06/2004; for Millstone Power Station, Physical Security Baseline Inspection Report. Cover Letter
ML0412604612004-05-0505 May 2004
Assessment Follow-up Letter-Millstone Power Station, Unit 2
IR 05000336/20020032002-06-13013 June 2002
IR 05000336-02-03; on 03/31-05/11/02; Dominion Nuclear Connecticut, Inc., Millstone Power Station; Unit 2; Resident Inspection. No Violations Identified
IR 05000336/20020112002-06-0707 June 2002
IR 05000423-02-011, IR 05000336-02-011, on 04/30-05/03/2002, Dominion Nuclear Connecticut, Inc, Millstone Power Station Units 2 & 3. Emergency Preparedness Exercise & Performance Indicator Review
IR 05000336/20020022002-04-24024 April 2002
IR 05000336/2002-002; on 02/10-03/30/02; Dominion Nuclear Connecticut, Inc., Millstone Power Station; Unit 2; Resident Inspection. No Violations Identified
IR 05000336/20010152002-03-18018 March 2002
IR 05000336/2001-015 and 05000423/01-015, Millstone Power Station, Inspection on 02/01/02 Related to Biennial Baseline Inspection of Id and Resolution of Problems, Corrective Action Program. Two Violations Were Identified
IR 05000336/20010142002-03-0808 March 2002
IR 05000336/2001-014, IR 05000423/2001-014, Dominion Nuclear Connecticut, Inc., Millstone Power Station, Unit 2, Resident Inspection on 12/30/2001-02/09/2002 Re Unit 3, Maintenance Rule Implementation
ML0206602472002-03-0707 March 2002
Notification of Conduct of a Triennial Fire Protection Baseline Inspection
2016-09-29
[Table view]
Category:Letter
MONTHYEARML24248A2272024-09-0404 September 2024
Operator Licensing Examination Approval
ML24240A1532024-09-0303 September 2024
Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel
IR 05000336/20240052024-08-29029 August 2024
Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005
IR 05000336/20240022024-08-13013 August 2024
Integrated Inspection Report 05000336/2024002 and 05000423/2024002
IR 05000336/20244412024-08-0606 August 2024
Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only)
ML24212A0742024-08-0505 August 2024
Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification
ML24211A1712024-07-25025 July 2024
Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change
IR 05000336/20244032024-07-22022 July 2024
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403
IR 05000336/20245012024-07-0101 July 2024
Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501
ML24180A0932024-06-28028 June 2024
Readiness for Additional Inspection: EA-23-144
IR 05000336/20240102024-06-26026 June 2024
Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010
ML24178A2422024-06-25025 June 2024
2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46
ML24177A2792024-06-20020 June 2024
Preparation and Scheduling of Operator Licensing Examinations
ML24170B0532024-06-10010 June 2024
DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code
ML24165A1292024-06-0505 June 2024
ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023
ML24128A2772024-06-0404 June 2024
Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary)
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
ML24109A0032024-05-21021 May 2024
Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary)
ML24110A0562024-05-21021 May 2024
Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter)
ML24141A2432024-05-20020 May 2024
Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15
ML24142A0952024-05-20020 May 2024
End of Cycle 22 Steam Generator Tube Inspection Report
IR 05000336/20240012024-05-14014 May 2024
Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation
ML24123A2042024-05-0202 May 2024
Pre-Decisional Replay to EA-23-144
IR 05000336/20244012024-04-30030 April 2024
Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only)
ML24123A1222024-04-30030 April 2024
Inservice Inspection Program - Owners Activity Report, Refueling Outage 22
IR 05000336/20244402024-04-25025 April 2024
Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only)
ML24114A2662024-04-24024 April 2024
Submittal of 2023 Annual Radioactive Effluent Release Report
ML24116A1742024-04-24024 April 2024
Annual Radiological Environmental Operating Report
ML24103A0202024-04-22022 April 2024
Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits
ML24106A2032024-04-15015 April 2024
2023 Annual Environmental Operating Report
ML24088A3302024-04-0404 April 2024
Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel
IR 05000336/20240112024-04-0101 April 2024
Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011
ML24093A2162024-04-0101 April 2024
Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits
ML24093A1022024-04-0101 April 2024
Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification
ML24092A0752024-03-28028 March 2024
3R22 Refueling Outage Inservice Inspection (ISI) Owners Activity Report Extension
ML24088A2352024-03-26026 March 2024
Decommissioning Funding Status Report
ML24086A4802024-03-22022 March 2024
Alternative Request IR-4-14, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examination for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles
ML24086A4762024-03-22022 March 2024
Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process
ML24051A1922024-03-0808 March 2024
– Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)
IR 05000336/20230062024-02-28028 February 2024
Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006)
ML24053A2632024-02-21021 February 2024
Unit 3, and Independent Spent Fuel Storage Installation, Notification Pursuant to 10 CFR 72.212(b)(1) Prior to First Storage of Spent Fuel Under a General License
ML24057A0612024-02-19019 February 2024
and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage
ML24043A0062024-02-15015 February 2024
Request for Withholding Information from Public Disclosure for License Amendment Request to Support Implementation of Framatome Gaia Fuel
IR 05000336/20230042024-02-14014 February 2024
Integrated Inspection Report 05000336/2023004 and 05000423/2023004
IR 05000336/20234022024-01-30030 January 2024
Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only)
ML24030A7522024-01-30030 January 2024
Technical Specification Bases Pages
ML23341A0172024-01-12012 January 2024
Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures
IR 05000336/20234402024-01-11011 January 2024
Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only)
ML24004A1052024-01-0404 January 2024
Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010
ML23361A0942023-12-21021 December 2023
Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report .
2024-09-04
[Table view] |
Text
July 23, 2008 Mr. David Christian Sr. Vice President and Chief Nuclear Officer Dominion Resources 5000 Dominion Boulevard Glenn Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION UNIT 2 - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
Dear Mr. Christian:
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 Millstone Power Station Unit 2 beginning in November 2008. The inspection team will be led by Keith Young from the NRC Region I office. The team will be composed of personnel from the NRC Region I.
The inspection will be conducted in accordance with NRC inspection procedure 71111.05T, the NRCs baseline fire protection inspection procedure.
The schedule for the inspection is as follows:
- Information gathering visit - Week of November 3, 2008
- Weeks of onsite inspection - November 17 - 21 and December 1 - 5, 2008 The purpose 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, and post-fire safe shutdown capabilities and 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 Enclosure 1. 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.
Mr. David Christian 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 Millstone Power Station 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 as 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 Millstone Power Station 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 Keith Young, the team leader in the Region I Office at (610) 337-5293.
Sincerely,
/RA/
John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-336 License No. DPR-65
Enclosure:
List of Reactor Fire Protection Program Supporting Documents
Mr. David Christian 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 Millstone Power Station 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 as 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 Millstone Power Station 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 Keith Young, the team leader in the Region I Office at (610) 337-5293.
Sincerely, John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-336 License No. DPR-65
Enclosure:
List of Reactor Fire Protection Program Supporting Documents SUNSI Review Complete: JFR (Reviewers Initials)
DOCUMENT NAME: G:\DRS\Engineering Branch 3\Young\MILL-U2 FP 90 Day Letter-2008.doc 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 RI/DRS NAME KAYoung/klg KAY JFRogge/ JFR DATE 07/ 23/2008 07/23/2008 OFFICIAL RECORD COPY ML#082050452
Mr. David Christian 3 cc w/encl:
J. A. Price, Site Vice President, Millstone Station C. L. Funderburk, Director, Nuclear Licensing and Operations Support W. Barton, Supervisor, Station Licensing J. Spence, Manager Nuclear Training L. M. Cuoco, Senior Counsel C. Brinkman, Manager, Washington Nuclear Operations J. Roy, Director of Operations, Massachusetts Municipal Wholesale Electric Company First Selectmen, Town of Waterford B. Sheehan, Co-Chair, NEAC E. Woollacott, Co-Chair, NEAC E. Wilds, Jr., Ph.D, Director, State of Connecticut SLO Designee J. Buckingham, Department of Public Utility Control C. Meek-Gallagher, Commissioner, Suffolk County, Department of Environment and Energy V. Minei, P.E., Director, Suffolk County Health Department, Division of Environmental Quality R. Shadis, New England Coalition Staff S. Comley, We The People D. Katz, Citizens Awareness Network (CAN)
R. Bassilakis, CAN J. M. Block, Attorney, CAN P. Eddy, Electric Division, Department of Public Service, State of New York P. Tonko, President and CEO, New York State Energy Research and Development Authority J. Spath, SLO Designee, New York State Energy Research and Development Authority N. Burton, Esq.
Mr. David Christian 3 Distribution w/encl: VIA E-MAIL S. Collins, RA M. Dapas, DRA M. Gamberoni, DRS D. Roberts, DRS S. Williams, RI OEDO M. Kowal, NRR R. Nelson, NRR J. Hughey NRR, PM J. Lamb, NRR, PM S. Shaffer, SRI J. Benjamin, RI J. Krafty, RI D. Jackson, DRP B. Norris, DRP, Acting Branch Chief N. Sieller, DRP J. Rogge, DRS K. Young, DRS
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.]
- 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, and fire brigade.)
- 3. Fire brigade training program and pre-fire plans.
- 4. Post-fire safe shutdown systems and separation analysis.
- 5. Post-fire alternative 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 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 fie protection equipment.
- 9. Plant layout drawings which identify the location of the 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. Maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, pumps and suppression systems. (Last completed copy.)
- 12. Maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis.
- 13. A list of 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 plants IPEEE, results of any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in response to IPEEE information.
2
- 15. Copies of AC and DC electrical system one line diagrams. (From offsite power grid connections down to the 120 volt level.)
- 16. Organization charts of site personnel down to the level of fire protection staff personnel.
- 17. A listing of the SERs which form the licensing basis for the reactor plants post-fire safe shutdown configuration.
- 18. A list of applicable codes and standards related to the design of plant fie protection features and evaluations of code deviations.
- 19. Procedures/instructions that govern the implementation of plant modifications, temporary modifications, maintenance, and special operations, and their impact on fire protection.
- 20. The three most recent fire protection QA audits and/or fire protection self-assessments.
- 21. Recent QA surveillances of fire protection activities.
- 22. A listing of open fire protection and fire safe shutdown related condition reports.
- 23. A listing of fire protection and fie safe shutdown condition reports closed in the past three years.
- 24. Fire protection system health reports (last 2).
- 25. Lesson plans and related training information for licensed and non-licensed operators for post-fire safe shutdown (including alternative shutdown).
Enclosure
