ML092730016: Difference between revisions
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| issue date = 09/29/2009 | | issue date = 09/29/2009 | ||
| title = 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 | | author name = Rogge J | ||
| author affiliation = NRC/RGN-I/DRS/EB3 | | author affiliation = NRC/RGN-I/DRS/EB3 | ||
| addressee name = Pollock J | | addressee name = Pollock J | ||
| Line 72: | Line 72: | ||
D. Roberts, DRS P. Wilson, DRS J. Rogge, DRS | D. Roberts, DRS P. Wilson, DRS J. Rogge, DRS | ||
Enclosure ENCLOSURE Reactor Fire Protection Program Supporting Documentation | Enclosure 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 versions of the Fire Protection Program and Fire Hazards Analysis. | : 1. The current versions of the Fire Protection Program and Fire Hazards Analysis. | ||
: 2. Current versions of the Updated Final Safety Analysis Report (UFSAR) and Operating License. 3. Current versions of the fire protection program implementing procedures (e.g., administrative controls, surveillance testing, and fire brigade). | : 2. Current versions of the Updated Final Safety Analysis Report (UFSAR) and Operating License. 3. Current versions of the fire protection program implementing procedures (e.g., administrative controls, surveillance testing, and fire brigade). | ||
: 4. Fire brigade training program and pre-fire plans. | : 4. Fire brigade training program and pre-fire plans. | ||
: 5. Post-fire safe shutdown systems and separation analysis including alternative or dedicated shutdown analysis. | : 5. Post-fire safe shutdown systems and separation analysis including alternative or dedicated 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. | : 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. | : 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. | : 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 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. | : 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. Last completed copies of maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, selected detectors, pumps and selected suppression systems. | : 11. Last completed copies of maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, selected detectors, pumps and selected suppression systems. | ||
: 12. Last completed copies of selected maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis. | : 12. Last completed copies of selected maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis. | ||
2 Enclosure | 2 Enclosure | ||
: 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. | : 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. Copies of AC and DC electrical system one line diagrams. (From offsite power grid connections down to the 120 volt level.) | : 14. Copies of AC and DC electrical system one line diagrams. (From offsite power grid connections down to the 120 volt level.) | ||
: 15. Organization charts of site personnel down to the level of fire protection staff personnel. | : 15. Organization charts of site personnel down to the level of fire protection staff personnel. | ||
: 16. SERs which form the licensing basis for the reactor plant's post-fire safe shutdown configuration. | : 16. SERs which form the licensing basis for the reactor plant's post-fire safe shutdown configuration. | ||
: 17. A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations. | : 17. A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations. | ||
: 18. The three most recent fire protection QA audits and/or fire protection self-assessments. | : 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. | : 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. | : 20. A listing of open fire protection and fire safe shutdown related condition reports. | ||
: 21. A listing of fire protection and fire safe shutdown condition reports closed in the past three years. | : 21. A listing of fire protection and fire safe shutdown condition reports closed in the past three years. | ||
: 22. Fire protection system health reports (last 2). | : 22. Fire protection system health reports (last 2). | ||
: 23. Lesson plans and related training information for licensed and non-licensed operators for post-fire safe shutdown including alternative shutdown.}} | : 23. Lesson plans and related training information for licensed and non-licensed operators for post-fire safe shutdown including alternative shutdown.}} | ||
Revision as of 17:43, 11 July 2019
| ML092730016 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/29/2009 |
| From: | Rogge J Engineering Region 1 Branch 3 |
| To: | Joseph E Pollock Entergy Nuclear Operations |
| References | |
| Download: ML092730016 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PA 19406-1415 September 29, 2009
Mr. Joseph Pollock Site Vice President Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT 2 - 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 Indian Point 2 beginning in January 2010. 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 I. The inspection will be conducted in accordance with NRC inspection procedure 71111.05T, the NRC's baseline fire protection inspection procedure.
The schedule for the inspection is as follows:
- Information gathering visit - Week of January 11, 2010
- Weeks of onsite inspection - January 25 and February 8, 2010
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, 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.
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 Indian Point 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 Indian Point 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 team's information or logistical needs, please contact Dan Orr, the team leader in the Region I Office at (610) 337-5048.
Sincerely,
/RA/
John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety
Docket No. 50-247 License No. DPR-26
Enclosure:
Reactor Fire Protection Program Supporting Documentation
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 Indian Point 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 Indian Point 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 team's information or logistical needs, please contact Dan Orr, the team leader in the Region I Office at (610) 337-5048.
Sincerely,
/RA/
John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety
Docket No. 50-247 License No. DPR-26
Enclosure:
Reactor Fire Protection Program Supporting Documentation
SUNSI Review Complete: JFR (Reviewer's Initials) ADAMS ACC #ML092730016 DOCUMENT NAME: G:\DRS\Engineering Branch 3\Orr\IP2 Triennial FP\IP2 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 document, indicate in the box:
" C" = Copy without attachment/enclosure " E" = Copy with attachment/enclosure " N" = No copy OFFICE RI/DRS RI/DRS NAME DOrr/JDO* JRogge/JFR DATE 09/23/09 09/29/09 OFFICE NAME DATE OFFICIAL RECORD COPY
- See Previous Concurrence Page Mr. J. Pollock 3 cc w/encl: Senior Vice President, Entergy Nuclear Operations Vice President, Operations, Entergy Nuclear Operations Vice President, Oversight, Entergy Nuclear Operations Senior Manager, Nuclear Safety and Licensing, Entergy Nuclear Operations Senior Vice President and COO, Entergy Nuclear Operations Assistant General Counsel, Entergy Nuclear Operations Manager, Licensing, Entergy Nuclear Operations C. Donaldson, Esquire, Assistant Attorney General, New York Department of Law A. Donahue, Mayor, Village of Buchanan J. G. Testa, Mayor, City of Peekskill R. Albanese, Four County Coordinator S. Lousteau, Treasury Department, Entergy Services, Inc.
Chairman, Standing Committee on Energy, NYS Assembly Chairman, Standing Committee on Environmental Conservation, NYS Assembly Chairman, Committee on Corporations, Authorities, and Commissions M. Slobodien, Director, Emergency Planning P. Eddy, NYS Department of Public Service Assemblywoman Sandra Galef, NYS Assembly T. Seckerson, County Clerk, Westchester County Board of Legislators A. Spano, Westchester County Executive R. Bondi, Putnam County Executive C. Vanderhoef, Rockland County Executive E. A. Diana, Orange County Executive T. Judson, Central NY Citizens Awareness Network M. Elie, Citizens Awareness Network M. Mariotte, Nuclear Information & Resources Service F. Zalcman, Pace Law School, Energy Project L. Puglisi, Supervisor, Town of Cortlandt Congressman John Hall Congresswoman Nita Lowey Senator Kirsten E. Gillibrand Senator Charles Schumer G. Shapiro, Senator Gillibrand 's Staff J. Riccio, Greenpeace P. Musegaas, Riverkeeper, Inc.
M. Kaplowitz, Chairman of County Environment & Health Committee A. Reynolds, Environmental Advocates D. Katz, Executive Director, Citizens Awareness Network K. Coplan, Pace Environmental Litigation Clinic M. Jacobs, IPSEC W. Little, Associate Attorney, NYSDEC M. J. Greene, Clearwater, Inc.
R. Christman, Manager Training and Development J. Spath, New York State Energy Research, SLO Designee F. Murray, President & CEO, New York State Energy Research A. J. Kremer, New York Affordable Reliable Electricity Alliance (NY AREA)
Mr. J. Pollock 4 Distribution w/encl
- (via E-mail)
S. Collins, RA M. Dapas, DRA D. Lew, DRP J. Clifford, DRP L. Trocine, RI OEDO RidsNrrPMIndianPointResource B. Welling, DRP B. Bickett, DRP S. McCarver, DRP G. Malone, DRP, Senior Resident Inspector - Indian Point 2 D. Hochmuth, DRP D. Bearde, DRP Region I Docket Room (w/concurrences)
D. Roberts, DRS P. Wilson, DRS J. Rogge, DRS
Enclosure 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 versions of the Fire Protection Program and Fire Hazards Analysis.
- 2. Current versions of the Updated Final Safety Analysis Report (UFSAR) and Operating License. 3. Current versions of the fire protection program implementing procedures (e.g., administrative controls, surveillance testing, and fire brigade).
- 4. Fire brigade training program and pre-fire plans.
- 5. Post-fire safe shutdown systems and separation analysis including alternative or dedicated 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 fire 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. Last completed copies of maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, selected detectors, pumps and selected suppression systems.
- 12. Last completed copies of selected maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis.
2 Enclosure
- 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. Copies of AC and DC electrical system one line diagrams. (From offsite power grid connections down to the 120 volt level.)
- 15. Organization charts of site personnel down to the level of fire protection staff personnel.
- 16. SERs which form the licensing basis for the reactor plant's post-fire safe shutdown configuration.
- 17. A list of applicable codes and standards related to the design of plant fire protection features and evaluations of 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.
- 21. A listing of fire protection and fire safe shutdown condition reports closed in the past three years.
- 22. Fire protection system health reports (last 2).
- 23. Lesson plans and related training information for licensed and non-licensed operators for post-fire safe shutdown including alternative shutdown.