IR 05000277/2003009
| ML031430425 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/22/2003 |
| From: | Linville J NRC/RGN-I/DRS/EB |
| To: | Skolds J Exelon Generation Co |
| References | |
| FOIA/PA-2003-0358, FOIA/PA-2004-0277 IR-03-009 | |
| Download: ML031430425 (26) | |
Text
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION - NRC TRIENNIAL FIRE PROTECTION INSPECTION REPORT 50-277/03-009, 50-278/03-009
Dear Mr. Skolds:
On April 25, 2003, the NRC completed a triennial fire team inspection at your Peach Bottom Atomic Power Station, Units 2 and 3. The enclosed report documents the inspection findings which were discussed on April 25, 2003, with Messrs. Rusty West, John Stone, and other members of the Exelon Generation Company, LLC staff.
This inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The purpose of the inspection was to evaluate your post-fire safe shutdown capability and fire protection program. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, the NRC identified one finding of very low safety significance (Green) that was a violation of NRC requirements. However, because of the very low safety significance and because the issue was entered into your corrective action program, the NRC is treating the finding as a non-cited violation (NCV) consistent with Section VI.A of the NRC Enforcement Policy. If you contest the NCV in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator Region I; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Peach Bottom Atomic Power Station.
In accordance with 10 CFR 2.790 of the NRC's "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 Publically 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).
Mr. John If you have any questions please contact me at 610-337-5129.
Sincerely,
/RA/
James C. Linville, Chief Electrical Branch Division of Reactor Safety Docket Nos. 50-277, 50-278 License Nos.: DPR-44, DPR-56
Enclosure:
Inspection Report No. 50-277/03-009 and 50-278/03-009
REGION I==
Enclosure
Mr. John Docket Nos.: 50-277, 50-278 License Nos: DPR-44, DPR-56 Report Nos: 50-277/03-009, 50-278/03-009 Licensee: Exelon Generation Company, LLC Correspondence Control Desk 200 Exelon Way, KSA 1-N-1 Kennett Square, PA 19348 Facility: Peach Bottom Atomic Power Station Units 2 and 3 Location: 1848 Lay Road Delta, Pennsylvania Inspection Period: April 7, 2003 through April 25, 2003 Inspectors: A. Della Greca, Sr. Reactor Inspector, Division of Reactor Safety C. Cahill, Sr. Reactor Inspector, Division of Reactor Safety K. Young, Reactor Inspector, Division of Reactor Safety Approved By: James C. Linville, Chief Electrical Branch Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS IR 05000277/02-009, IR 05000278/02-009; 04/07/2003-04/25/2003; Peach Bottom Atomic Power Station Units, 2 and 3; Fire Protection.
The inspection was conducted by a team composed of regional specialists. The inspection identified one Green non-cited violation (NCV). The significance of most findings is indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter 0609 Significance Determination Process (SDP). Findings for which the SDP does not apply are indicated by No Color or by a severity level of the applicable violation. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
A. NRC-Identified Findings Cornerstone: Mitigating Systems
! Green. The team identified a non-cited violation of 10 CFR Part 50, Appendix R, Section III.G.2. Exelon included manual actions in Table A-1 of Specification NE-00296, Post-Fire Safe Shutdown Program Requirements, November 23, 1999, to operate equipment necessary for achieving and maintaining hot shutdown. Several of these manual actions did not meet the requirements of Appendix R, section III.G.2 and the NRC had not granted exemptions to allow these actions.
In accordance with the guidance provided in inspection procedure 71111.05, Fire Protection, (revision dated 3/6/03) this finding is greater than minor. The finding is of very low safety significance because the manual actions are reasonable and are expected to meet the criteria outlined in Enclosure 2 of inspection procedure 71111.05. (Section 1R05.8).
ii Enclosure
Report Details Background This report presents the results of a triennial fire protection team inspection conducted in accordance with NRC Inspection Procedure (IP) 71111.05, Fire Protection. The objective of the inspection was to assess whether Exelon had implemented an adequate fire protection program for the Peach Bottom Atomic Power Station (PBAPS) and whether the PBAPS post-fire safe shutdown capabilities had been established and were being properly maintained. The following fire areas were selected for detailed review based on risk insights from the PBAPS, Units 2 and 3, Individual Plant Examination of External Events (IPEEE):
! Fire Area 4, Unit 2 Recirculation Pump M-G Set Room (Elevation 135'-0")
! Fire Area 25, Cable Spreading Room (Elevation 150'-0")
! Fire Area 32, Emergency Switchgear Room 261 (Elevation 135'-0")
! Fire Area 34, Emergency Switchgear Room 265 (Elevation 135'-0")
This Inspection was conducted in accordance with the March 6, 2003, revision to inspection procedure (IP) 7111.05, Fire Protection. This revision of the IP included guidance for inspecting manual actions in conjunction with licensee commitments to 10 CFR 50, Appendix R, Section III.G.2. In accordance with the procedure, issues regarding equipment malfunction due to fire-induced failures of associated circuits were not inspected. Criteria for review of fire-induced circuit failures are currently the subject of a voluntary industry initiative. The definition of associated circuit of concern used was that contained in the March 22, 1982, memorandum from Mattson to Eisenhut, which clarified the requests for information made in NRC Generic Letter 81-12.
1. REACTOR SAFETY Cornerstones: Initiating Events, Mitigating Systems 1R05 Fire Protection (71111.05)
.1 Programmatic Controls a. Inspection Scope During tours of the PBAPS facility, the team observed the material condition of fire protection systems and equipment, the storage of permanent and transient combustible materials, and control of ignition sources. The team also reviewed the procedures that controlled hot-work activities and combustibles at the site. This was accomplished to verify that Exelon was maintaining the fire protection systems, controlling hot-work activities, and controlling combustible materials in accordance with their fire protection program.
b. Findings No findings of significance were identified.
Enclosure
.2 Passive Fire Barriers a. Inspection Scope During tours of the selected fire areas, the team evaluated the design adequacy and material condition of fire area boundaries, including fire walls, fire doors, fire dampers and fire barrier penetration seals, to ensure that Exelon was maintaining the passive features of the fire areas in a state of readiness.
The team randomly selected three fire barrier penetration seals and a fire damper for detailed inspection to verify proper installation and qualification. The team reviewed associated design drawings, test reports, and engineering analyses. The team compared the observed in-situ seal configurations to the design drawings and tested configurations. Additionally, the team compared the penetration seal and fire damper ratings with the ratings of the barriers in which they were installed. This was accomplished to verify that Exelon had installed the selected penetration seals and fire damper in accordance with their design and licensing bases.
b. Findings No findings of significance were identified.
.3 Fire Detection System a. Inspection Scope The team reviewed the adequacy of the fire detection systems in the selected plant fire areas. This included a walkdown of the detection systems and a review of the type and locations of installed detectors to verify their conformance to the plant design and installation drawings. In addition, the team reviewed completed surveillance procedures to verify the adequacy and frequency of fire detection component testing. This review was performed to ensure that the fire detection systems for the selected fire areas met their design and licensing bases.
b. Findings No findings of significance were identified.
.4 Fixed Fire Suppression Systems and Equipment a. Inspection Scope The team evaluated the adequacy of the automatic total flooding carbon dioxide (CO2)
system in the cable spreading room (CSR), and the pre-action sprinkler systems in the recirculation pump motor-generator (MG) room and in emergency switchgear rooms 261 and 265. The evaluation included walkdown of the systems and reviews of installation Enclosure
drawings and functional testing. These reviews were accomplished to verify that the selected fixed suppression systems met their design and licensing bases.
The automatic function of the CO2 system at PBAPS was disabled in June 2002, due to an inadvertent CO2 discharge in the E-3 diesel generator room. With the automatic function disabled, the CO2 system is available for manual initiation by the fire brigade.
Regarding the CO2 system in the CSR, the team reviewed the initial CO2 discharge testing, the revised pre-fire strategy plan (which contained guidance for initiating the CO2 system manually), the fire brigade training documents and the CO2 system flow calculations. These reviews were performed to confirm that the CO2 concentration achieved in the CSR during pre-operational testing was acceptable and to ensure that the compensatory measures taken by PBAPS following the disabling of the CO2 system automatic function were appropriate.
b. Findings No findings of significance were identified.
.5 Manual Fire Suppression Capability a. Inspection Scope The team conducted physical inspection of selected stand pipe systems, hose reels and portable fire extinguishers to determine the material condition of manual fire fighting systems and to verify that equipment locations were in conformance with those specified in the firefighting strategies (pre-fire plans) and fire protection program documents. The team reviewed diesel fire pump flow and pressure tests to ensure that the pumps met their design requirements. The team also reviewed the fire main loop flow testing to ensure that no degradation of the piping had occurred and that the flow distribution circuits were able to meet the design requirements. A review of the pre-fire strategy plans for the target fire areas was conducted to verify the accuracy of the plans versus the installed fire protection features and to ensure that appropriate information had been provided to the fire brigade members and plant operators to identify safe shutdown equipment and instruments.
The team inspected the fire brigadess protective ensembles, self-contained breathing apparatus (SCBA), portable communications equipment and various other fire brigade equipment to determine material condition and operational readiness of equipment for fire fighting. The team also reviewed the qualifications of several fire brigade members to ensure that they had met and maintained the requirements for fire brigade membership.
Enclosure
b. Findings No findings of significance were identified.
.6 Safe Shutdown Capability a. Inspection Scope The team reviewed the PBAPS Specification for Post-Fire Safe Shutdown Requirements, NE-00296, and associated Safe Shutdown Analysis, MDE-86-0786, to confirm that the licensee had identified the methods and the structures, systems, and components (SSCs) necessary to achieve hot shutdown and cold shutdown, following postulated fires in the selected risk significant fire areas. The team further reviewed applicable flow diagrams, instrument drawings and the safe shutdown components list.
This review was conducted to identify the components required for establishing the specified flow paths and for isolating the flow diversion paths.
The team verified that the applicable requirements of 10 CFR 50, Appendix R, Sections III.G and III.L for achieving and maintaining safe shutdown were properly addressed.
The team verified that systems necessary to assure the safe shutdown functions of reactivity control, reactor coolant makeup, reactor heat removal, and process monitoring were protected within or independent of the selected fire zones. Where deviations from Appendix R requirements were identified, the team verified that the deviations had been approved and that conditions required by the deviations were implemented and being maintained.
b. Findings No findings of significance were identified.
.7 Operational Implementation of Post-Fire Safe Shutdown Capability a. Inspection Scope The team reviewed the fire response procedures and emergency operating procedures (EOPs) for the selected fire areas to evaluate the methods and equipment used to achieve hot shutdown following a fire in those areas. The team reviewed piping and instrumentation drawings and confirmed that the required components had been evaluated and included in the safe shutdown equipment list. The review included an evaluation of selected alternate shutdown components and their control circuits to ensure that, in the event of a fire in the CSR and control room complex, alternate shutdown capability had been provided and proper isolation had been included. Field walkdowns were conducted to evaluate the protection of the equipment from the effects of fires.
Post-fire shutdown procedures for the selected areas were also reviewed to determine if appropriate information was provided to plant operators to identify protected equipment Enclosure
and instrumentation and if the recovery actions specified in the post-fire shutdown procedures considered area accessibility and manpower needs for performing restorations. The team reviewed training lesson plans, including those for the alternative shutdown procedures. In addition, the team discussed training with operators, reviewed selected alternate shutdown equipment tests, inventoried manual action tool packages, reviewed the adequacy of shift manning, and evaluated the accessibility of the alternative shutdown operating stations and required manual action locations. Specific procedures reviewed included PBAPS Special Event Procedure, SE-10, Alternate Shut Down, Revision 13, SE-10 Plant Shutdown from the Alternate Shutdown Panels - Bases, Revision 14, and SE-10.1 Alternate Shutdown Restoration, Revision 11.
A procedure walkdown was performed for procedure SE-10, Alternate Shut Down, Revision 13, The walkdown was performed by an operator and focused primarily on the portion of the procedure associated with achieving stable hot shutdown conditions. The plant operator was accompanied by NRC team members during the walkdown and the approximate time for critical steps, such as isolating and transferring safety relief valve (SRV) controls, was noted and evaluated to assess the ability of the operators to maintain plant parameters within procedural limits.
b. Findings No findings of significance were identified.
.8 Safe Shutdown Circuit Analyses a. Inspection Scope The team reviewed applicable system flow diagrams, electrical one line diagrams, control panel layouts, control circuit schematic diagrams, instrument loop diagrams, cable tray designations, fire zone/area arrangements drawings, panel and rack wiring diagrams, operating procedures, circuit breaker coordination curves, calculations, modifications, vendor information and the electrical cable and raceway information system to verify that the conclusions of selected sections of the safe shutdown analysis were correct and that the procedures, equipment, fire barriers, and systems provided were sufficient to assure post-fire safe shut down of the plant.
For the selected areas, the team also reviewed the PBAPSs safe shutdown analysis (SSA) report to ensure that at least one post-fire safe shutdown success path, free of fire damage, was available in the event of a fire. This included a review of manual actions required to achieve and maintain hot shutdown conditions and to make the necessary repairs to reach cold shut down within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The team sampled sections of operating procedures and walked down required manual actions taking into consideration such factors as timing, accessability of the equipment, and availability of procedures. The team used the guidance of IP 71111.05, Enclosure 2, to confirm the availability of selected components and feasibility of the manual actions.
Enclosure
Due to the issuance of Change Notice 00-020 against Inspection Procedure 71111.05, Fire Protection, the team did not review associated circuit issues during this inspection.
This change notice has suspended this review pending completion of an industry initiative in this area.
b. Findings Introduction. The team identified a Green non-cited violation (NCV) because Exelon used manual actions to operate equipment necessary for achieving and maintaining hot shutdown in lieu of providing protection for the cables associated with that equipment, as required by 10 CFR Part 50, Appendix R, Section III.G.2.
Description. In a Safety Evaluation dated September 16, 1993, the NRC evaluated and accepted manual actions performed outside the control room to achieve post-fire safe shutdown following fires in certain fire areas of PBAPS. Table A-4 of the PBAPS Fire Protection Program, revision 4, January 1991, described the manual actions and the fire areas that required manual actions. The actions included fuse pulling and manual operation of motor-operated valves from motor control centers.
During this inspection, the team reviewed Table A-1 of Specification NE-00296, Post-Fire Safe Shutdown Program Requirements, revision 0, November 23, 1999, and identified that the Table included multiple manual actions that had been credited for and incorporated in the post-fire safe shutdown procedures. These additional manual actions did not meet the requirements of Appendix R, section III.G.2 and the NRC had not granted exemptions to allow these actions. Exelon had incorporated the additional manual actions to address Thermo-lag related changes and analysis refinements. The manual actions that were identified in Specification NE-00296 but not approved by the NRC included fuse pulling, tripping circuit breakers and operating switches to restore power.
Analysis. Inspection procedure 71111.05 (revision date March 6, 2003) states that, If the inspectors determine that manual actions are reasonable and are expected to meet the criteria outlined in Enclosure 2, then the inspection report will identify this issue as a green finding pending the Commissions acceptance of the proposed staff initiative to incorporate the use of manual actions into section III.G.2 of the code. (The green finding is an indicator that while compensatory measures in the form of manual actions have been implemented and are acceptable, the licensee continues to be in violation of the code requirements). If the inspectors determine that the manual actions are not reasonably accomplishable and, therefore, implementation may not lead to a safe plant condition, the preliminary finding will be identified as potentially greater than green and entered into the [significance determination process] SDP.
The team determined that, (1) adequate diagnostic instrumentation was provided to detect spurious actuation of equipment and accomplishment of manual actions; (2) the environmental conditions potentially encountered by the operator(s) while accessing and performing the manual actions were reasonable; (3) staffing was sufficient and training adequate; (4) procedures were available for performing the planned manual action; (5)
Enclosure
communication means had been provided; (6) when necessary, special tools had been dedicated and made available for use; (7) the equipment requiring manipulation was accessible; and (8) the Exelon fire protection team had confirmed their ability to perform the required manual actions within the specified time. Therefore, the team concluded that the manual actions were reasonable and were expected to meet the criteria of Enclosure 2.
Enforcement. Title 10 of the Code of Federal Regulations (CFR), Part 50.48, Fire Protection, and 10 CFR Part 50, Appendix R, Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979," establish specific fire protection features required to satisfy 10 CFR Part 50, Appendix A, General Design Criterion 3, Fire Protection. Appendix R applies to licensed nuclear power stations that were operating prior to January 1, 1979, which includes PBAPS.Section III.G.2 of Appendix R to 10 CFR Part 50 requires that, where cables or equipment, including associated non-safety circuits that could prevent operation or cause maloperation due to hot shorts, open circuits, or shorts to ground, of redundant trains of systems necessary to achieve and maintain hot shutdown conditions are located within the same fire area outside of primary containment, one of the following means of ensuring that one of the redundant trains is free of fire damage shall be provided:
a. Separation of cables and equipment and associated non-safety circuits of redundant trains by a fire barrier having a 3-hour rating. Structural steel forming a part of or supporting such fire barriers shall be protected to provide fire resistance equivalent to that required of the barrier; b. Separation of cables and equipment and associated non-safety circuits of redundant trains by a horizontal distance of more than 20 feet with no intervening combustible or fire hazards. In addition, fire detectors and an automatic fire suppression system shall be installed in the fire area; or c. Enclosure of cable and equipment and associated non-safety circuits of one redundant train in a fire barrier having a 1-hour rating. In addition, fire detectors and an automatic fire suppression system shall be installed in the fire area.
Contrary to the above, the team found that, at PBAPS, Exelon included manual actions in Table A-1 of Specification NE-00296, November 23, 1999, to operate equipment necessary for achieving and maintaining hot shutdown. Several of these manual actions did not meet the requirements of Appendix R, section III.G.2 and the NRC had not granted exemptions to allow these actions. This issue was determined to be of very low safety significance because PBAPS application of manual actions met the criteria established in IP 71111.05, Enclosure 2, and was entered into the PBAPS corrective action program (CR 00-155529). This violation is being treated as a NCV, consistent with Section VI.A of the NRC Enforcement Policy: NCV 50-277&278/03-009-01, Failure to Provide Protection in Accordance with 10 CFR Part 50, Appendix R, Section III.G.2.
.9 Electrical Raceway Fire Barrier Systems (ERFBS)
Enclosure
a. Inspection Scope The team walked down accessible portions of the selected fire areas to observe material condition of the electrical raceway fire barrier systems. Additionally, the team selected the Thermo-Lag installation in the CSR for detailed review. The review included design and installation drawings, qualifications testing documents and engineering analyses for selected configurations. The NRC safety evaluations of fire protection features for PBAPS were also reviewed by the team. This was accomplished to verify that the selected portions of the fire barrier system met their design and licensing bases.
b. Findings No findings of significance were identified.
.10 Post-Fire Safe Shutdown Emergency Lighting and Communications a. Inspection Scope The team observed the placement and aiming of eight-hour emergency lighting units (ELUs) throughout the selected fire zones to evaluate their adequacy for illuminating access and egress pathways and equipment requiring local operation for post-fire safe shutdown. In addition, during the alternate shutdown procedure walk through documented in Section 1R05.7, Operational Implementation of Post-Fire Safe Shutdown Capability, the team verified that emergency lights were provided where needed.
The team reviewed surveillance and preventive maintenance procedures to ensure operational readiness of the ELUs. Additionally, the team reviewed Exelons ELU action plan to determine what actions were planned to improve ELU performance.
The team reviewed radio repeater location and power sources to ensure that the fire brigade and operators could maintain communications for fire fighting in the selected areas and in the event of shutdown from outside of the control room.
b. Findings No findings of significance were identified.
4. OTHER ACTIVITIES 4OA2 Identification and Resolution of Problems
.1 Corrective Actions for Fire Protection Deficiencies a. Inspection Scope Enclosure
The team reviewed the fire impairments log, fire protection system health reports, open corrective maintenance backlog for fire protection and safe shutdown equipment, selected condition reports (CRs) for fire protection and safe shutdown issues to evaluate the prioritization for resolving fire protection related deficiencies and the effectiveness of corrective actions. The team also reviewed recent quality assurance (QA) audits, fire protection self-assessments of the fire protection program and recent field observations to determine if PBAPS personnel were identifying fire protection program and equipment deficiencies and implementing appropriate corrective actions.
b. Findings No findings of significance were identified.
4OA6 Meetings, Including Exit
.1 Exit Meeting Summary The team presented their preliminary inspection results to Mr. Rusty West and Mr. John Stone and other members of the Exelon staff at an exit meeting on April 25, 2003.
Exelon acknowledged the conclusions and observations presented.
The team asked Exelon if any of the information provided during the inspection was proprietary. Proprietary information was identified and returned to Exelon prior to leaving the site. No proprietary information was included in this inspection report.
Enclosure
SUPPLEMENTAL INFORMATION KEY POINT OF CONTACT PPL Susquehanna LLC Mike Alfonso Work Management Steve Beck Reg. Assurance Chuck Behrend Senior Manager - Plant Engineering Russ Bleeker Engineering Paul Davison Maintenance Dan Duane Operations C. Howell Designer (Penetration Seals)
K. Kauffman DC System Manager (ELUs)
Chris Kerr Engineering P. Kopicki Engineer, Engineering Support Group Jim Kovalchick Operations Jay Lyter Operations Support George McCarty Radiation Protection M. McCrea System Manager (Communications)
Albert Piha Engineering Tom Powell NOS Chris Pragman Exelon Corporate Paul Rau Engineering Cliff Sinopoli Engineering Garey Stathes Engineering Director John Stone Plant Manager Frank Sturniolo Engineering Rusty West Site Vice President Nuclear Regulatory Commission J. Linville Chief, Electrical Branch, DRS A. McMurtray Senior Resident Inspector, Peach bottom Atomic Power Station M. Buckley Resident Inspector, Peach Bottom Atomic Power Station LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Opened and Closed 50-277 & 278/03-009-01 NCV Failure to Provide Cable Protection in Accordance with 10 CFR Part 50, Appendix R, Section III.G.2.
Attachment
LIST OF ACRONYMS USED ASD Alternative Shutdown BOP Balance of Plant CAP Corrective Action Program CARDOX Carbon Dioxide CFR Code of Federal Regulations CO2 Carbon Dioxide CR Condition Report CRD Control Rod Drive CSR Cable Spreading Room ECR Engineering Change Request ELU Emergency Lighting Unit EOP Emergency Operating Procedures ERFBS Electrical Raceway Fire Barrier System ESW Emergency Service Water HPCI High Pressure Coolant Injection HPSW High Pressure Service Water INDMS Integrated Nuclear Data Management System IP Inspection Procedure IPEEE Individual Plant Examination of External Events MG Motor Generator MOD Modification NCV Non-Cited Violation NFPA National Fire Protection Association NRC Nuclear Regulatory Commission P&ID Piping and Instrument Diagram PBAPS Peach Bottom Atomic Power Station PCC Primary Containment Control PECO Philadelphia Electric Company QA Quality Assurance RCIC Reactor Core Isolation Cooling RHR Residual Heat Removal RPV Reactor Pressure Vessel RT Routine Test SCBA Self Contained Breathing Apparatus SCC Secondary Containment Control SDP Significance Determination Process SSA Safe Shutdown Analysis SSC Structures, Systems, Components SRV Safety Relief Valve ST Surveillance Test Attachment
LIST OF DOCUMENTS REVIEWED Fire Protection Program Documents FF-01 Fire Fighting Plan, Rev. 7 FPP Fire Protection Program, Rev 13, April, 2001 FPP Fire Protection Program, Table A-4, Rev 4, January 1991 NE-00296 Post-Fire Safe Shutdown Program Specification, Rev 0, November 23, 1999 NE-00256 Design Criteria for Electrical Separation, Rev 0 PF-0016-004 Fire Area 04 - Fire Safe Shutdown Analysis, Rev 0 PF-0016-025 Fire Area 25 - Fire Safe Shutdown Analysis, Rev 0 PF-0016-032 Fire Area 32 - Fire Safe Shutdown Analysis, Rev 0 PF-0016-034 Fire Area 34 - Fire Safe Shutdown Analysis, Rev 0 PF-108 Control Room, Rev 2 PF-108A Fan Room, Rev 2 PF-117 Unit 3 Emergency Battery and Switchgear Rooms, Rev 3 PF-127 Unit 2 Emergency Battery and Switchgear Rooms, Rev 3 PF-78H CSR and Computer Room, Rev 2 PF-4C Unit 2 Rx Recirc. Pump MG Set Room, Rev 3 RT-S-037-709-2 Accessible Safe Shutdown Emergency Lighting Battery Pack Inspection RT-S-037-710-2 Complete Safe Shutdown Emergency Lighting Battery Pack Inspection, Rev. 5 RT-S-037-719-2 Emergency Lighting Inspection (Alternate Shutdown Control Station Access/Egress Lights), Rev. 3 Calculations and Engineering Evaluations A1373246 00 01 Fire Protection System Impairment Evaluation, Cable Spreading Room and Computer Room CARDOX, June 14, 2002 PE-0182 Perform 125 V DC Voltage Analysis Automatic vs. Manual Initiation of CO2 in The Cable Spreading Room, April 22, 2003 CARDOX, Low Pressure Carbon Dioxide Flow Calculations For PBAPS CSR, January 31, 1991 CARDOX, Initial Discharge Testing Data, July 6, 1973 Drawings A-12, Architectural Floor Plan, EL. 135'-0", Rev. 35 A-13, Architectural Floor Plan, EL. 165'-0", Rev. 30 A-486, Barrier Plans EL. 135'-0" E1 Single Line Diagram Station, Rev 40 E5 Single Line Meter & Relay Diagram, 13.8KV Aux. Power System, Unit 2, Rev 12 E-5-7, (Sh 6 & 17) Electrical Schematic Diagram - Standby Diesel Engine Generators E7 Single Line Meter & Relay Diagram, 13.8KV Aux. Power System, Unit 3, Rev 14 E8 Single Line Meter and Relay Diagram Standby Diesel Gens & 4160 Volt Emer. Power System, Unit 2, Sh 1 & 2 E12 Single Line Meter and Relay Diagram Standby Diesel Gens & 4160 Volt Emer. Power System, Unit 3, Sh. 1 & 2 Attachment
E-17-219, (Sh 1 & 2) Transmitter Loop Diagram - Wiring Diagram E-17-222,(Sh 1 & 2) Transmitter Loop Diagram - Wiring Diagram E26 Single Line Diagram, 125/250 VDC System, Unit 2, Sh. 1-3 E27 Single Line Diagram, 125/250 VDC System, Unit 3, Sh. 1-3 E28 Single Line Diagram, Instrumentation & Uninterruptible AC System, Unit 2
& Common, Sh. 1 & 2 E28 Single Line Diagram, Instrumentation & Uninterruptible AC System, Unit 3, Sh. 1 & 2 E-47, (Sh 1 - 3C) Schematic Meter & Relay Diagram - 4160V Emergency Auxiliary Power System (3-line)
E-71, (Sh 1 & 2) Emergency Auxiliary Switchgear Regulating Transformer Source 4.16kV Circuit Breaker (2A1501)
E-71, (Sh 3 & 4) Emergency Auxiliary Switchgear Regulating Transformer Source 4.16kV Circuit Breaker (2A1601)
E-71, (Sh 5 & 6) Emergency Auxiliary Switchgear Regulating Transformer Source 4.16kV Circuit Breaker (2A1701)
E-71, (Sh 7 & 8) Emergency Auxiliary Switchgear Regulating Transformer Source 4.16kV Circuit Breaker (2A1801)
E-150, (Sh 6) Electrical Schematic Diagram - Miscellaneous Motor Operated Valves 480V Starters E-183, (Sh 1) Electrical Schematic Diagram - Core Spray Pump 4.16kV Circuit Breaker, Rev. 20 E-184, (Sh 1 & 2) Electrical Schematic Diagram - RHR Pump 4.16kV Circuit Breaker, Rev
E-185, (Sh 1-3) Electrical Schematic Diagram - High Pressure Service Water Pump 4.16kV Circuit Breaker, Rev. 19 E-187, (Sh 1-4) Electrical Schematic Diagram - Emergency Service Water Pump 4.16kV Circuit Breaker (2A1603 & 2A1706)
E-187, (Sh 2) Electrical Schematic Diagram - Emergency Service Water Pump 4.16kV Circuit Breaker (2A1603) as revised by ECR 97-01659, R0 E-265, (Sh 2 & 3) Electrical Schematic Diagram - BOP Temperature Readout, Rev. 27 E-266, (Sh 1 & 2) Cable Block Diagram - BOP Instrumentation E-345 Electrical Schematic Diagram - Emergency Cooling System - High Pressure Service Water Discharge to Reservoir E-346 Electrical Schematic Diagram - Emergency Cooling System - Cooling Tower Fan Inlet Valves E-352 Cable Block Diagram - Steam Leak Detection System (Sh 1)
E-539-58 Parts List for Unit 2 Panels 20C04BX and 20C03-2X (6 sheets)
E-539-59 Nameplate Engraving for Unit 2 Panels 20C04BX and 20C03-2X (12 shts)
E-539-60 Panel Arrangement HPCI & RHR Alternative Control Panels 20C04BX and 20C03-2X (Unit 2), Rev 6 E-540-13 "2AC043 & 2BC043 Remote Shutdown Panel Enhancement Arrangement," R4 E-540-15 "3AC043 & 3BC043 Remote Shutdown Panel Enhancement Arrangement," R3 E-540-123 Panel 20C04BX and 20C03-2X HPCI & RHR Alternative Control Enhancement Arrangement (Unit 2) (2 sheets)
Attachment
E-1140 Raceway Layout Turbine Bldg Area 3, El. 135'-0", Sh. 1 and 3A E-11401 Tray Layout Turbine Bldg Area 3, El. 150'-0", Sh. 1 and 2 E-1147 Raceway Layout Turbine Bldg Area 3, El. 165'-0", Sh. 1 and 2 E-1154 Conduit Layout Cable Spreading Room, Turbine Bldg Area 3, El. 150'-0",
Sh. 1, Rev 110 E-1188 Raceway Layout Radwaste Bldg Area 10, El. 150'-0", Sh. 1, Rev 51 E-1191 Raceway Layout Radwaste Bldg Area 10, El. 165'-0", Sh. 1, 1A and 2A E-2056, (Sh 1) Elementary Wiring Diagram - Torus Water Level Instrumentation E-2357, (Sh 1 & 5) Electrical Schematic Diagram - Post Accident Monitoring System E-2394, (Sh 1) Electrical Schematic Diagram - Suppression Pool Temperature Monitoring System, C-Channel E-2471, Raceway Encapsulation Notes and Details, Rev. 0 E-2557, (Sh 1-3) Electrical Schematic Diagram - Alternative Control Instrumentation (Unit 3)
E-2598, (Sh 1 & 3) Electrical Schematic Diagram - Process & Diagnostic Instrumentation Required for Appendix R - Safe Shutdown E-2903, (Sh 1-3) Electrical Schematic Diagram - Alternative Control Instrumentation (Unit 2)
M-1-EE-461, (Sh 1) Functional Diagram - Reactor Water Level - Wide Range Pressure Compensation M-1-EE-468, (Sh 1) Functional Diagram - Reactor Water Level - Fuel Zone Pressure Compensation Cabinets, Rev 8 M-1-S-23 Electrical Schematic Diagram - Primary Containment Isolation System (Sh 27 & 31)
M-1-S-25 Electrical Schematic Diagram - Feedwater Control System (Sh 4 & 6)
M-1-S-36 Electrical Schematic Diagram - High Pressure Coolant Injection System (Sh 12 & 13)
M-1-S-40 Electrical Schematic Diagram - Core Spay System (Sh 1 thru 13)
M-1-S-42 Electrical Schematic Diagram - Reactor Core Isolation Cooling System (Sh 7 & 18)
M-1-S-44 (Sh 4) Electrical Schematic Diagram - Nuclear Boiler Process Instrumentation M-1-S-52 Electrical Schematic Diagram - Automatic Blowdown System (Sh 3, 4 & 8)
M-1-S-65 Electrical Schematic Diagram - Residual Heat Removal System (Sh 1-36D)
M-3, General Arrangement Plan at EL. 135'-0", Rev. 21 M-4, General Arrangement Plan at EL. 165'-0", Rev. 25 M-10, Equipment Location Turbine Building Unit No. 2 Plan at 165'-0", Rev. 13 M-16, Equipment Location Reactor and Radwaste Building Unit No. 2, Rev. 15 M-23, Equipment Location Turbine Building Unit No. 3 Plan at EL. 135'-0", Rev.
M-24, Equipment Location Turbine Unit No. 3 Plan at EL. 165'-0" M-315 Emergency Service Water and High Pressure Service Water Systems (9 sheets)
M-318 Fire Protection System P&IDs (10 sheets)
M-351 Nuclear Boiler (8 sheets)
M-352 Nuclear Boiler Vessel Instrumentation (8 sheets)
M-359 Reactor Core Isolation Cooling System (4 sheets)
Attachment
M-360 RCIC Pump/Turbine Details Lube Oil & Control 'System (6 sheets)
M-361 Residual Heat Removal System (8 sheets)
M-362 Core Spray Cooling System (4 sheets)
M-363 Fuel Pool Cooling and Clean-Up System (4 sheets)
M-365 High Pressure Coolant Injection System (4 sheets)
M-366 HPCI Pump/Turbine Details (5 sheets)
PD-1, Typical Penetration Seal Details Cross Reference, Rev. 0 PD-3, Typical Penetration Seal Details Internal Conduit Seal, Rev. 0 PD-6, Typical Penetration Seal Detail Cable Tray Floor Seal, Rev. 0 PD-7, Typical Penetration Seal Detail Cable Tray Wall Seal, Rev. 0 PD-9, Typical Penetration Seal Detail Penetration Through Barrier Less Than Required Thickness, Rev. 0 PD-27, Typical Penetration Seal Detail Grout Seal, Rev. 0 PS-302, Penetration Seal Locations Controlled Barriers - Room Number 302, Unit 2 and 3, Area 3 EL. 150'-0", Rev. 1 S-68, Area Number 3, Turbine Building Plan at EL. 150'-0", Rev. 33 S-1232, Fire Damper Details For Doors 284 and 286 Peach Bottom A.P.S. Units 2 and 3, Rev. 0 Procedures A-C-134 Control of Hazard Barriers, Rev. 4 A-C-134-6 Control of Hazard Door/Hatches and Penetrations at Peach Bottom, Rev.
9 CC-AA-211 Fire Protection Program, Rev. 0 OP-AA-201-001 Fire Marshal Tours, Rev. 1 OP-AA-201-002 Fire Reports, Rev. 1 OP-AA-201-003 Fire Drill Performance, Rev. 5 OP-AA-201-005 Fire Brigade Qualification, Rev. 2 OP-AA-201-006 Control of Temporary Heat Sources, Rev. 0 OP-AA-201-008 Pre-Fire Plans, Rev. 1 OP-AA-201-009 Control of Transient Combustible Material, Rev. 2 OP-MA-201-004 Fire Prevention for Hot Work, Rev. 0 OP-MA-201-007 Fire Protection System Impairment Control, Rev. 1 RT-O-006-450-2(3) Feedwater Stop Valve MO-2-02-029A Alternative Control Test, Rev. 0(0)
RT-O-010-304-2(3) RHR/HPSW System Valves Alternative Control Testing, Rev. 6(6)
RT-O-010-310-(2)3 RHR System Functional From The Alternative Control Panels, Rev. 9(6)
RT-O-22C-910-2(3) Alternative Shutdown Communication Functional Test, Rev. 2(2)
RT-O-023-750-2(3) HPCI Functional Test From Alternative Control Panels, Rev. 14(12)
RT-O-023-760-(2)3 HPCI Valve And Component Test From Alternative Control Panel, Rev.
8(10)
RT-O-023-770-2(3) Alternative Control Panel Power And Logic Relays Check, Rev. 3(4)
RT-O-052-750-2 Diesel Shutdown Control Functional, Rev. 7 RT-O-052-760-2 Diesel And "A" ESW Pump Alternative Shutdown Control Panel, Rev. 9 RT-O-100-990-2, Participants Record Documentation for STs, RTs, Clearances and Checkoff Lists (COLs), Rev. 1 SE-1 SE-1 Plant Shutdown from the Remote Shutdown Panel, Rev. 17 SE-10, Sh 1 ASD - Alternative Shutdown Flow Chart, Rev. 13 SE-10, Sh 2 ASD - Alternative Shutdown Flow Chart, Rev. 13 Attachment
SE-10 BASES SE-10 Plant Shutdown from the Alternate Shutdown Panels, BASES, Rev.
SE-10.1 Alternative Shutdown Restoration, Rev. 11 SE-10 Att. 1 Operation of MO-2-10-154B from the MCC, Rev. 3 SE-10 Att. 2 Operation of MO-3-10-154B from the MCC, Rev. 3 SE-10 Att. 3 Operation of MO-2-10-089D from the MCC, Rev. 4 SE-10 Att. 4 Operation of MO-3-10-089B from the MCC, Rev. 4 SE-10 Att. 5 Alternate RPV Injection Using CRD, Rev. 2 SE-10 Att. 6 4kv Alternate Shutdown Panel Setup and Transfer of 125v battery Charger 2BD003 to Alternate Power Source, Rev. 3 SE-10 Att. 7 RCIC Operation at the Remote Shutdown Panel, Rev. 0 SE-10-Att. 8 NRC Notifications from the ASD Panels, Rev. 1 SE-10 Att. 9 HPCI Operations from the Alternate Shutdown Panel, Rev. 1 SE-10 Att. 10 Depressurization Cooldown Log, Rev. 0 SE-10 Att. 11 Alternate Shutdown Cooling Cooldown Log, Rev. 0 SE-10 Att. 12 Bypass of 8130A, Rev. 0 SE-10 Att. 13 Bypass of 9130A, Rev. 0 SE-10 Att.14 Reactor Protection System De-Energization, Rev. 0 SE-10 Att. 15 Reactor Protection System De-Energization, Rev. 0 SE-10 Att. 16 HPSW Pump Room Temperature Local Monitoring, Rev. 0 ST-I-037-223-3 Unit 3 4kV Switchgear & Battery Room Smoke Detectors Functional Test, Rev. 6.
ST-I-037-284-2 Fan Room Smoke Detectors Functional Test, Rev. 4 ST-I-037-289-2 Cable Spreading Room Smoke Detectors Functional Test, Rev. 6 ST-I-037-290-2 Computer Room Smoke Detectors Functional Test, Rev. 3 ST-I-37A-310-2 Cable Spreading Room And Computer Room Cardox Simulated Actuation And Air Flow Test, Rev. 4 ST-M-037-310-2(3) Visual Walkaround Inspection of Fire Barriers, Rev. 3(4)
ST-M-037-311-2(3) Detailed Visual Inspection of Penetration Seals and Difficult to View Fire Barriers, Rev. 3(4)
ST-O-37B-323-3 Unit 3 Battery Rooms And 4kv Switchgear Rooms Sprinkler System Actuation, Rev. 2 ST-O-37B-314-2 Fan Room Sprinkler System Actuation, Rev. 2 ST-O-37C-330-2 Motor Driven Fire Pump Flow Rate Test, Rev. 5 ST-O-37C-360-2 Motor Driven Fire Pump Operability Test, Rev. 8 ST-O-37D-340-2 Diesel Driven Fire Pump Flow Rate Test, Rev. 6 ST-O-37D-370-2 Diesel Driven Fire Pump Operability Test, Rev. 16 T-101 RC - RPV Control Flow Chart, Rev. 17 T-102, Sh 1 PCC - Primary Containment Control Flow Chart, Rev. 15 T-102, Sh 2 14 PCC - Primary Containment Control Flow Chart, Rev. 14 T-102, Sh 3 13 PCC - Primary Containment Control Flow Chart, Rev. 13 T-103 14 SCC - Secondary Containment Control Flow Chart, Rev. 14 T-111 11 LR - Level Restoration Flow Chart, Rev. 11 T-112 14 EB - Emergency Blowdown Flow Chart, Rev. 14 T-300 Fire Procedure (8 sheets)
T-304-2(3) Fire Guide for Fire Area 4 (Unit 2(3)), Rev. 0(0)
T-325-2(3) 0(0) Fire Guide for Fire Area 25 (Unit 2(3)), Rev. 0(0)
Attachment
T-332-2(3) 0(0) Fire Guide for Fire Area 32 (Unit 2(3)), Rev. 0(0)
T-334-2(3) 0(0) Fire Guide for Fire Area 34 (Unit 2(3)), Rev. 0(0)
TRM 3.14 Fire Protection Portion of the Technical Requirements Manual. Only Unit 2 provide, (Unit 3 is identical)
Hot Work Permits & Transient Combustible Permits C0193304 01 01, C0204308 14 01, R0005863 16 01 ,R0860952 04 01, R0880909 02 01, R0898473 01 01, A1391378 Fire Brigade Qualifications Report and Training Documents Fire Brigade Individual Qualifications Report, April 2, 2003 Fire Drills Fire Drill, U/2 180' Reactor Building, March 20, 2002 Fire Drill (No. 16), Cable Spreading Room, September 4, 2002 Fire Drill (No. 20), 116' Radwaste Extension Building, November 6, 2002 Fire Drill (No. 1), U/2 13 KV Bus, January 7, 2003 Fire Drill (No. 2), U/2 13 KV Bus, January 7, 2003 Fire Drill (No. 14), U/3 HPCI Room, April 23, 2003 Lesson Plans PFBL-0010 Fire Brigade Leader, Rev. 1 PFBL-0020 Functions of Command, Rev. 0 PFBL-0030 Command Strategy For Fire Control, Rev. 0 PFBL-0040 Management of Fire Streams, Rev. 4 PFBL-0050 Commanding The Rescue, Rev. 0 PFBL-0060 Commanding The Support Activities, Rev. 0 PFBS-0010 Fire Brigade Training, Rev. 1 PFBS-0020 Fire Hazards, Rev. 0 PFBS-0030 Products of Combustion, Rev. 0 PFBS-0040 Fire Brigade Site Specific Training, Rev. 3 PNL.OC-02 Fourth Quarter 2002 Fire Brigade Training (Offsite Training), Rev. 0 Completed Tests/Surveillance RT-O-006-450-2 Feedwater Stop Valve MO-2-02-029A Alternative Control Test -
completed 11 Sept 2002, Rev. 0 RT-O-010-304-2 RHR/HPSW System Valves Alternative Control Testing - completed 10 May 2001, Rev. 5 RT-O-010-310-2 RHR System Functional From The Alternative Control Panels - completed 08 May 2001, Rev. 6 RT-O-010-750-2 MO-2-10-016D Power Supply Operational Check - completed 02 Mar 2001, Rev. 3 RT-O-22C-910-2 Alternative Shutdown Communication Functional Test - completed 19 Nov 2002, Rev. 2 RT-O-023-750-2 HPCI Functional Test From Alternative Control Panels - completed 15 Mar 2002, Rev. 11 Attachment
RT-O-023-760-2 HPCI Valve And Component Test From Alternative Control Panel - 12 Mar 2002, Rev. 6 RT-O-023-770-2 Alternative Control Panel Power And Logic Relays Check - completed 14 May 2001, Rev. 1 RT-O-052-750-2 E2 Diesel Alternative Shutdown Control Functional - completed 27 Dec 2001, Rev. 6 RT-O-052-760-2 Diesel And "A" ESW Pump Alternative Shutdown Control Panel -
completed 03 Sept 2001, Rev. 9 RT-O-100-950-2 Alternative Shutdown Key Accountability Verification - completed 10 Dec 2002, Rev. 4 ST-I-037-223-2 Unit 2 4KV Switchgear and Battery Room and Radwaste 135' Corridor Smoke Detectors Functional Test, Completed October 29, 2002, and September 15, 2003 ST-I-037-284-2 Fan Room (Room No. 381, Radwaste EL. 165') Smoke Detectors Functional Test, Completed August 8, 2001, and October 11, 2002 ST-I-037-288-2 Cable Spreading Room Smoke Detectors Functional Test, Completed August 27, 2001, and August 20, 2002 ST-I-037-289-2 Cable Spreading Room Smoke Detectors Functional Test, Completed August 27, 2001, and August 20, 2002 ST-I-37A-310-2 Cable Spreading and Computer Room CARDOX Simulated Actuation and Air Flow Test, Completed January 4, 2001, and April 9, 2003 ST-I-37B-323-2 Unit 2 Battery Rooms, 4KV Switchgear Rooms, and Radwaste Corridor Area Sprinkler System Actuation, Completed July 31, 2001 ST-I-037-223-3 Unit 3 4KV Switchgear and Battery Room Smoke Detectors Functional Test, Completed November 14, 2001, and August 7, 2002 Functional Teat, Completed November 14, 2001, and August 7, 2002 ST-I-037-292-2 Recirc. Pump M/G Set Room 135' Smoke Detectors Functional Test, Completed November 5, 2001, and November 7, 2002 ST-O037B-314-2 Fan Room (Room #381, Radwaste EL. 165') Sprinkler System Actuation, Completed October 7, 1999, and September 17, 2001 ST-O-37B-323-2 Unit 2 Battery Rooms, 4KV Switchgear Room, and Radwaste Corridor Area Sprinkler System Actuation, Completed October 7, 1999 ST-O-37B-323-3 Unit 3 Battery Rooms and 4KV Switchgear Rooms Sprinkler System Actuation, Completed October 7, 1999, and August 7 2001 ST-O-37B-324-2 Recirc. Pump MG Set Sprinkler System Actuation, Completed July 17, 2001, and October 16, 2001 ST-O-37B-381-2 Underground Fire Main Flow Test, November 14, 1997, and June 26, 2001 ST-O-37C-330-2 Motor Driven Fire Pump Flow Rate Test, Completed December 8, 200, and January 8, 2002 ST-O037C-360-2 Motor Driven Fire Pump Operability Test, Completed December 24, 2002 and January 20, 2003 ST-O-37D-340-2 Diesel Driven Fire Pump Flow Rate Test, Completed November 28, 2001 and November 29, 2002 ST-O-37D-370-2 Diesel Fire Pump Operability Test, Completed December 11, 2002, and January 7, 2003 Test Reports Attachment
Metal Clad Fire Wall Penetration Barrier Fire Testing, BISCO Test No. 748-14, May 21, 1979 BISCO Three Hour Fire Test of Various Electrical and Mechanical Seal Configurations, August 4, 1986 Three Hour Fire Tests of Multiple Penetrations Sealed With 9" of SF-20 and 1" Ceramic Board, BISCO Fire Test 748-255, August 17, 1990 Fire Test Configuration For Silicone Foam Fire Barriers in Gypsum Board Stud Partitions, BISCO Report No. 1064-10, June 20, 1979 Factory Mutual Research, Fire Endurance Test of Silicone Foam Penetration Seal in a Masonry Floor Design FC-270, December 14, 1978 Technical Report 00067-0027-TR-01, PBAPS Thermo-Lag and Darmatt Fire Endurance Qualification Report, Rev. 0 Vectra Technologies, Inc., Project No. 14980-100123, One Multiple Conduit Enclosure (Continuing One 1in. And Two 6 in. conduits), One Close-Mounted Rigid Steel 1 in. Conduit, One Rigid Steel 1 in. Conduit, One Small Aluminum Junction Box And One Large Aluminum Junction Box, August 1, 1996 319A Fire Damper Data, April 8, 2003 Design Change Packages/Evaluations ECR 99-00979 Control Room Emergency Ventilation ECR 00-00162 Unit 2 Condensate Pump Room Smoke Detection Installation (P00889)
ECR 00-01805 Unit 2 Control Room Battery Replacement ECR-01-00561 Install Cable Tray Covers on 3 Trays In Room 222 MOD 95-04933 HISTRY - MOD P00571 - Breaker E23 (1605), (Mother ECR), Rev. 0 MOD 95-04934 APPVD - MOD P00571 - Breaker E22 (1603) Rev. 1 and 50.59 Safety Evaluation - Rev. 1 (Child ECR)
MDCH 97-01659 APPVD - MOD P00571 - Breaker E22 (1603), Rev. 0 NCR 95-00025 APPRVD - DC Motors not Modeled Correctly in Battery and VDROP Calcs, Rev.2 Quality Assurance Audits, Self-Assessments and Field Observations NOSA-PB-3Q-02 QA Audit - Biennial Fire Protection Assessment by Independent Contractor AR130276130276Focused Area Self Assessment Report Appendix R Post-Fire Safe Shutdown Manual Action Feasibility, December 9-20, 2002 AR 141985141985Pre-Inspection Self-Assessment in Preparation for NRC Triennial Fire Protection Inspection, February 24 - March 14, 2003 Field Observation of Fire Door and Combustible Material Compliance, July 24, 2001 PIMs Review of Fire Protection RT/STs, August 9, 2001 PIMs Review of Fire Protection RT/ST Performance, August 24, 2001 Field Observation for Fire Protection and Housekeeping, September 14, 2001 Field Observation for Fire Protection and Housekeeping, September 17, 2001 Plant Fire Protection Plant Review, October 25, 2001 Appendix R - Safe Shutdown From Alternate Shutdown Panels; SE-10 Implementation, December 17, 2001 NOS December 2002 Housekeeping Walkdown Area 11, December 22, 2002 Fire Brigade Training and Qualifications, March 11, 2002 Surveillance Test Package Reviews, April 9, 2002 Attachment
Observations of May 30, 2002, Fire Brigade Annual Training at Conshohocken Fire School, June 6, 2002 Fire Brigade Refresher Training, June 4, 2002 Fire Protection Related Tests, June 25, 2002 Observations of Unexpected Fire System Actuation, July 23, 2002 Fire Watches and Fire System Impairments, July 31, 2002 Observation of Hot Work Fire Watch Training, August 15, 2002 Roving and Continuous Fire Watches, September 5 - 11, 2002 Fire Watches, September 25, 2002 2R14 Observations, September 25, 2002 January 22, 2003, Integrated Fire Drill, January 23, 2003 February 4, 2003, Integrated Fire Drill - Simulator Performance, February 14, 2003 Miscellaneous Documents NE-CG-931 Fuse & Molded case Circuit Breaker Application Design Guide, Rev. 4 ON-114, Actual Fire Reported In The Power Block, Diesel Generator Building, Emergency Pump, Inner Screen or Emergency Cooling Tower Structures -
Bases, Rev. 9 and Rev. 10 P-S-51 Design Baseline Document (DBD) for Fire Protection System, Rev 9 P-T-10 Topical Design Baseline Document (DBD) for Fire Safe Shutdown, Rev 8 SE-02, CARDOX Injection Into The Cable Spreading Room, Rev. 9 IPEEE results Safety Evaluation Report by The Office of Nuclear Reactor Regulation, dated May 23, 1979 Safety Evaluation Report by The Office of Nuclear Reactor Regulation, dated Sept. 16, 1993 Supplement No. 1 to The Safety Evaluation Report of The Peach Bottom Atomic Power Station Fire Protection Program, PECO, dated August 14, 1980 Supplement Number 2 to The Safety Evaluation Report of The Peach Bottom Atomic Power Station Fire Protection Program, PECO, dated September 15, 1980 Supplement Number 3 to The Safety Evaluation Report of The Peach Bottom Atomic Power Station Fire Protection Program, PECO, dated October 10, 1980 Supplement Number 4 to The Safety Evaluation of The Peach Bottom Atomic Power Station Fire Protection Program, PECO, dated November 24, 1980 Fire Protection Rule-Alternate Safe Shutdown Capability Sections III.G.3 and III.L of Appendix R to 10 CFR Part 50- Peach Bottom Atomic Power Station Units 2 and 3, dated May 4, 1984 Exemption From Certain Requirements of Appendix R to 10 CFR 50, dated March 13, 1985 Peach Bottom Atomic Power Station, Units 2 and 3, Fire Protection Program, dated 10/10/1985 Exemption From Appendix R to 10 CFR 50 Concerning Penetration Seals and Fire Detection, dated November 14, 1986 Exemption From 10 CFR Appendix R Regarding Dampers, Structural and Automatic Fire Suppression Peach Bottom Atomic Power Station Units 2 and 3, dated December 31, 1986 Exemption From The Requirements of 10 CFR Part 50, Appendix R, Peach Bottom Atomic Power Station, Units 2 and 3, dated October 3, 1991 Miscellaneous INDMS Reports for Cable and Raceway Locator.
Emergency Light Unit Action Plan, February 15, 2003 Fire System Impairment Log, April 8, 2003 NFPA 12, Carbon Dioxide Extinguishing Systems, 1968 Attachment
Maintenance Rule Expert Panel, System 37, Fire Safe Shutdown Emergency Lighting Units A1 Action Plan, March 24, 2003 Peach Bottom Fire Protection/Fire Safe Shutdown Program Controlling Document: CC-AA-211, Fire Protection Program, Fourth Quarter, 2002 and First Quarter, 2003 Condition Reports TOP 2000 0 507, TOP 2000 - 842, TOP 2000 - 1520, TOP 2001 - 2403, TOP 2001 - 2410, TOP 2001 - 4825, TOP 2001 - 6320, PEP I0011855, PEP I0012053 CR 00060717, CR 00060814, CR 00061061, CR 00061214, CR 00071321, CR 00078320, CR 00084705, CR 00084992, CR 00088462. CR 00091134, CR 00093991, CR 00098512, CR 00098906, CR 00099362, CR 00105906, CR 00109061, CR 00110049, CR 00113940, CR 00114908, CR 00116185, CR 00116949, CR 00117426, CR 00119365, CR 00124757, CR 00132522, CR 00132679, CR 00132812, CR 00132839, CR 00133630, CR 00138195, CR 00144089, CR 00144428, CR 00146157, CR 00146448, CR 00147226, CR 00148989 AR A1410440, AR A1410451, AR A1412383, AR A1412567, AR A1412383, AR A1413372, AR A1414771, AR A1414772, AR A1414996, AR A1414963, AR 00150436, AR 00152980, AR 00153227, AR 00153232 Attachment