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Category:Fire Protection Plan
MONTHYEARML21137A1912021-05-17017 May 2021 Byron/Braidwood Stations - Amendment 29 to Fire Protection Report, Chapter 2.0-2.3, Area Design Hazards Analysis-Redacted ML21008A4142020-12-17017 December 2020 Byron/Braidwood Stations - Amendment 29 to Fire Protection Report, Chapter 4, Fire Protection Program ML21008A4202020-12-17017 December 2020 Byron/Braidwood Stations - Amendment 29 to Fire Protection Report, Cover and Page Index ML21008A4212020-12-17017 December 2020 Byron/Braidwood Stations - Amendment 29 to Fire Protection Report, Chapter 1, Introduction ML21008A4262020-12-17017 December 2020 Byron/Braidwood Stations - Amendment 29 to Fire Protection Report, Appendices RS-20-153, Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-12020-12-17017 December 2020 Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-1 ML19170A3112019-06-19019 June 2019 Redacted Braidwood Station, Units 1 & 2, and Byron Station, Units 1 & 2, Amendment 28 to Fire Protection Report, Appendix 5.1 (Public Version Pages 1-76 and 129-287) ML19169A0232019-06-18018 June 2019 Amendment to Fire Protection Report, Chapter 2.0 - 2.3, Area (Public Version Pages 1-26, 43-103, and 134) ML19168A2162019-06-17017 June 2019 Redacted Byron Station, Units 1&2, Amendment 28 to Fire Protection Report, Chapter 2.4, Safe Shutdown Analysis (Public Version Pages 1-20 and 1626-1643) RS-18-144, Amendment 28 to Fire Protection Report, Chapter 4, Fire Protection Program2018-12-17017 December 2018 Amendment 28 to Fire Protection Report, Chapter 4, Fire Protection Program RS-16-248, Braidwood Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-12016-12-15015 December 2016 Braidwood Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report Cover and Page Index2016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report Cover and Page Index RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report, Chapter 1, Introduction2016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report, Chapter 1, Introduction ML16357A5932016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 4.0, Fire Protection Program ML16357A5832016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report Cover and Page Index ML16357A5912016-12-15015 December 2016 Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 ML16357A5922016-12-15015 December 2016 Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 ML17095A8522016-12-15015 December 2016 Redacted Byron Nuclear Station, Amendment 27 to Fire Protection Plan, Chapter 2.4, Safe Shutdown Analysis. Section 2.4 Public Version Pages 1-19 and 1626-1643 ML17095A8662016-12-15015 December 2016 Redacted Braidwood Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 2.4, Safe Shutdown Analysis. Section 2.4 Public Version Pages 1-18 and 1726-1742 ML16357A5842016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report, Chapter 1, Introduction ML17087A2212016-12-15015 December 2016 Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 2.0, Fire Hazards Analysis RS-16-248, Byron Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-12016-12-15015 December 2016 Byron Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 ML17094A8652016-12-15015 December 2016 Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 5.1, Appendices RS-16-248, Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 5.1, Appendices2016-12-15015 December 2016 Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 5.1, Appendices RS-16-248, Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 2.0, Fire Hazards Analysis2016-12-15015 December 2016 Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 2.0, Fire Hazards Analysis RS-16-248, Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 4.0, Fire Protection Program2016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 4.0, Fire Protection Program ML15054A4562014-12-15015 December 2014 Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26. (Redacted Version) RS-14-338, Braidwood, Units 1 and 2, Byron, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26. (Redacted Version)2014-12-15015 December 2014 Braidwood, Units 1 and 2, Byron, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26. (Redacted Version) RS-12-043, Units 1 & 2 - Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2012-03-30030 March 2012 Units 1 & 2 - Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate ML0406201762004-03-0101 March 2004 Re Notification of NRC Triennial Fire Protection Baseline Inspection RS-02-207, Amendment 20 to Byron/Braidwood Stations Fire Protection Report, Tables 2.4-5 - 3-12002-12-31031 December 2002 Amendment 20 to Byron/Braidwood Stations Fire Protection Report, Tables 2.4-5 - 3-1 2021-05-17
[Table view] Category:Letter
MONTHYEARIR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 BYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline2023-11-17017 November 2023 Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23313A0852023-11-0909 November 2023 Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23278A0272023-10-0505 October 2023 Operator Licensing Examination Approval - Byron Station, October 2023 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23251A1622023-09-29029 September 2023 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) ML23242A3282023-09-0101 September 2023 Amendment No. 233 Correction IR 05000454/20235012023-08-31031 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501 IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) IR 05000454/20230022023-08-0303 August 2023 Integrated Inspection Report 05000454/2023002 and 05000455/2023002 ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23192A0362023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 IR 05000454/20234022023-07-18018 July 2023 Baseline Security Inspection Document; 05000454/2023402; 05000455/2023402 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information 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 ML23159A1302023-06-0808 June 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B1R25) ML23159A1542023-06-0808 June 2023 2022 Regulatory Commitment Change Summary Report RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process ML23157A2832023-06-0606 June 2023 Notification of NRC Baseline Inspection and Request for Information BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23003A7882023-05-11011 May 2023 Report for December 12-16, 2022, Regulatory Audit Regarding Reinsertion of a High Burnup Accident Tolerant Fuel Lead Test Assembly 2024-02-02
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March 1, 2004 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BYRON STATION NOTIFICATION OF AN NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
Dear Mr. Crane:
On June 21, 2004, the NRC will begin a triennial fire protection baseline inspection at the Byron Station. This inspection will be performed in accordance with the NRC baseline Inspection Procedure 71111.05.
The schedule for the inspection is as follows:
- Information gathering visit - June 9, 2004
- On-site inspection activity - June 21-25, 2004 and July 6-9, 2004 The purpose of the information gathering visit is: (1) to obtain information and documentation needed to support the inspection; (2) to become familiar with the Byron Station fire protection programs, fire protection features, post-fire safe shutdown capabilities and plant layout; and (3) to arrange administrative details such as office space, availability of knowledgeable office personnel and to ensure unescorted site access privileges.
Experience has shown that the baseline fire protection inspections are extremely resource intensive both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both organizations, we have enclosed a request for documents needed for the inspection. These documents have been divided into four groups. The first group lists information necessary to aid the inspection team in choosing specific focus areas for the inspection. It is requested that this information be provided to the lead inspector via mail or electronically no later than May 28, 2004. The second group lists information necessary to ensure that the inspection team is adequately prepared for the inspection. This information should be available on-site no later than June 9, 2004. The third group of requested documents are those items that the team will review, or need access to, during the inspection. Please have this information available by the first day of the on-site portion of the inspection (June 21, 2004). The fourth group lists information necessary to aid the inspection team in tracking issues identified as a result of the inspection. It is requested
C. Crane that this information be provided to the lead inspector as the information is generated during the inspection. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection.
The lead inspector for this inspection is Ms. Laura Kozak. If there are any questions about the inspection or the material requested, please contact the lead inspector at (630) 829-9604 or via e-mail at llc2@nrc.gov.
In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Julio F. Lara, Chief Electrical Engineering Branch Division of Reactor Safety Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
Enclosure:
Fire Protection Inspection Document Request cc w/encl: Site Vice President - Byron Byron Station Plant Manager Regulatory Assurance Manager - Byron Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear Document Control Desk - Licensing Assistant Attorney General Illinois Department of Nuclear Safety State Liaison Officer, State of Illinois State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission
C. Crane that this information be provided to the lead inspector as the information is generated during the inspection. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection.
The lead inspector for this inspection is Ms. Laura Kozak. If there are any questions about the inspection or the material requested, please contact the lead inspector at (630) 829-9604 or via e-mail at llc2@nrc.gov.
In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Julio F. Lara, Chief Electrical Engineering Branch Division of Reactor Safety Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
Enclosure:
Fire Protection Inspection Document Request cc w/encl: Site Vice President - Byron Byron Station Plant Manager Regulatory Assurance Manager - Byron Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear Document Control Desk - Licensing Assistant Attorney General Illinois Department of Nuclear Safety State Liaison Officer, State of Illinois State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission DOCUMENT NAME: ML040620176.wpd 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 RIII RIII RIII NAME LKozak:tr AStone JLara DATE 02/26/04 02/27/04 03/01/04 OFFICIAL RECORD COPY
C. Crane ADAMS Distribution:
AJM DFT GFD RidsNrrDipmIipb GEG HBC RAS DRPIII DRSIII PLB1 JRK1
INITIAL DOCUMENT REQUEST FIRE PROTECTION INSPECTION DOCUMENT REQUEST Information Requested Prior to the Information Gathering Visit The following information is requested by May 28, 2004. If you have any questions regarding this information, please call the lead inspector as soon as possible. All information may be sent electronically (to Ms. Laura Kozak, e-mail address llc2@nrc.gov) or provided on compact disc.
(1) The reactor plants Individual Plant Examination for External Events (IPEEE) for fire, results of any post-IPEEE reviews for fire, and listings of actions taken/plant modifications conducted in response to IPEEE information for fire. Alternatively, probabilistic risk analyses for fire and associated information, if it exists and is more recent than the IPEEE.
(2) A list of fire areas requiring alternative shutdown capability, i.e., those areas for which 10 CFR Part 50, Appendix R, Section III.G requirements are satisfied under Section III.G.3.
Information Requested During the Information Gathering Visit (June 9, 2004)
This information is requested to be available on-site during the information gathering visit.
(1) The current version of the Fire Protection Program and Fire Hazards Analysis; (2) Listing of plant fire protection licensing basis documents; (3) The NRC Safety Evaluation Reports (SERs) and actual copies of the 50.59 reviews which form the licensing basis for the reactor plants post-fire safe shutdown configuration; (4) A list of Generic Letter 86-10 evaluations; (5) A list of applicable codes and standards related to the design of plant fire protection features. The list should include National Fire Protection Association (NFPA) code versions committed to (i.e., the NFPA codes of record);
(6) A list of plant deviations from code commitments; (7) Post-fire safe shutdown analyses, including post-fire safe shutdown systems and separation analysis; (8) 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; (9) Plant layout and equipment drawings which identify the physical plant locations of hot standby and cold shutdown equipment for selected fire zones/areas (to be determined during information gathering visit);
1 Enclosure
INITIAL DOCUMENT REQUEST (10) Plant layout drawings which identify plant fire area delineation, areas protected by automatic fire suppression and detection, and the locations of fire protection equipment for selected fire zones/areas (to be determined during information gathering visit);
(11) Listing of open and closed fire protection condition reports (problem identification forms and their resolution reports) for the past three years; (12) Listing of fire impairments for the previous year; (13) Pre-fire plans for selected fire zones/areas (to be determined during information gathering visit);
(14) Plant operating procedures which would be used and describe shutdown for a postulated fire in selected fire zones/areas (to be determined during information gathering visit);
(15) A listing of the protection methodologies identified under 10 CFR Part 50, Appendix R, Section III.G used to achieve compliance for selected fire zones/areas (to be determined during information gathering visit). That is, please specify whether three hour rated fire barriers (Section III.G.2.a), 20-foot separation along with detection and suppression (Section III.G.2.b), one hour rated fire barriers with detection and suppression (Section III.G.2.c), or alternative shutdown capability (Section III.G.3) is used for each selected fire zone/area; (16) One-line schematic drawings of the electrical distribution system for 4160 Volts - alternating current (Vac) down to 480 Vac; (17) One-line schematic drawings of the electrical distribution system for 250 Volts - direct current (Vdc) and 125 Vdc systems as applicable; (18) A listing of abbreviations/designators for plant systems; (19) Organization charts of site personnel down to the level of fire protection staff personnel; and (20) A phone list for on-site licensee personnel.
In addition, during the information gathering visit, it is requested that licensee staff be available for the following:
(1) Informal discussion on plant procedures operators would use in the event of fire and under what conditions would the plant be shutdown using alternative shutdown methodology; (2) Informal discussion on the plants safe shutdown cable routing database and the plant-wide cable routing database, as applicable; and (3) A tour of alternative shutdown and risk significant fire areas.
Information Requested to be Available on First Day of Inspection (June 21, 2004) 2 Enclosure
INITIAL DOCUMENT REQUEST (1) List of the fire protection program implementing procedures (e.g., administrative controls, surveillance testing, fire brigade);
(2) List of maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, pumps, and suppression systems; (3) List of maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis; (4) List of procedures/instructions that control the configuration of the reactor plants fire protection program, features, and post-fire safe shutdown methodology and system design; (5) List of procedures/instructions that govern the implementation of plant modifications, maintenance, and special operations, and their impact on fire protection; (6) Coordination calculations and/or justifications that verify fuse/breaker coordination for selected fire zones/areas (to be determined during information gathering visit) that are fed off of the same electrical buses as components in the protected safe shutdown train; (7) Significant fire protection and post-fire safe shutdown related design change package descriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter (GL) 86-10 evaluations; (8) Gaseous suppression system pre-operational testing, if applicable, for selected fire zones/areas (to be determined during information gathering visit);
(9) Hydraulic calculations and supporting test data which demonstrate operability for water suppression systems, if applicable, for selected fire zones/areas (to be determined during information gathering visit);
(10) Alternating current (ac) coordination calculations for 4160 Vac down to 480 Vac electrical systems; (11) The three most recent fire protection Quality Assurance (QA) audits and/or fire protection self-assessments; and (12) Corrective action documents (e.g., condition reports, including status of corrective actions) generated as a result of the three most recent fire protection Quality Assurance (QA) audits and/or fire protection self-assessments.
Information Requested to Be Provided Throughout the Inspection (1) Copies of any corrective action documents generated as a result of the teams questions or queries during this inspection; and (2) Copies of the list of questions submitted by the team members and the status/resolution of the information requested (provide daily during the inspection to each team member).
3 Enclosure