L-17-189, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805
L-PI-16-090, Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors
2CAN101601, License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications
NRC 2016-0039, Fire Protection Evaluation Report, Revisions 16 and 17
CNS-16-030, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants - LAR Supplement to Address .
1CAN051602, Update to Tables S-1 and S-2 - Adoption of National Fire Protection Association Standard NFPA-805
1CAN011601, Response to Round 3 Request for Additional Information, Adoption of National Fire Protection Association Standard NFPA-805
MNS-15-099, Submittal Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program
Information Notice 1992-18, Potential for Loss of Remote Shutdown Capability During a Control Room Fire
Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections
PLA-4505, Provides Util Interpretation & Application of App R,Spurious Operations Criteria at Susquehanna Ses.Closure of Listed Issues Re App R Safe Shutdown for Sses,Requested to Satisfy Remaining Issues
1CAN111501, Second Set of Round 2 Responses to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805
1CAN081501, 120-Day Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805
L-PI-15-052, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information - 90-Day Responses
W3F1-2015-0025, Responses to Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805 License Amendment Request (LAR) Waterford Steam Electric Station, Unit 3 (Waterford 3)
PNP 2014-080, Response to Request for Additional Information - License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors
2CAN081401, Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805
CP-201400684, Revised Completion Date for Multiple Spurious Operation Circuit Interactions Resolution Implementation Plan
W3F1-2014-0025, Updated Responses to Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805 License Amendment Request (LAR)
2CAN011401, Response to Request for Additional Information, Adoption of National Fire Protection Association Standard NFPA-805
W3F1-2013-0048, Supplement to NFPA 805 License Amendment Request (LAR)
CNL-13-141, Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants - Set 1
2CAN121302, Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805
NL-13-2039, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants
PNP 2013-079, Response to Request for Additional Information License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors
W3F1-2013-0022, Response to 2nd Round Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805
AEP-NRC-2013-17, Response to a Request for Additional Information (RAI 29.01, 61, and 62) Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805
L-MT-13-033, Extended Power Uprate: Secy 11-0014 Use of Containment Accident Pressure - Responses to Requests for Additional Information
NG-13-0056, Response to RAI, License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants
1CAN121204, Response to Request for Additional Information, Request for Extension of Enforcement Discretion
1CAN121202, Response to Request for Additional Information, Request for Extension of Enforcement Discretion
1CAN111204, Response to Request for Additional Information Request for Extension of Enforcement Discretion
L-2012-354, Supplemental Information Regarding License Amendment Request No. 216 Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)
W3F1-2012-0064, Response to Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805 License Amendment Request
1CAN081202, Request for Extension of Enforcement Discretion
2CAN081202, Request for Extension of Enforcement Discretion
AEP-NRC-2012-29, Response to Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805
RA-11-019, Request for Extension of Enforcement Discretion and Commitment to Submittal Dates for 10 CFR 50.48(c) License Amendment Requests
L-PI-18-005, License Amendment Request to Revise License Condition Associated with Implementation of NFPA 805
WM 16-0008, Wolf Creek Generating Station Updated Safety Analysis Report (Usar), Redacted Version of Revision 29, E-1F9915, Rev 8, Design Basis Document for Ofn RP-017, Control Room Evacuation
ULNRC-05781, Callaway Plant NFPA 805 Transition Report, Attachment a - NEI 04-02 Table B-1 and Attachment B - NEI 04-02 Table B-2
NL-10-100, Response to August 11, 2010 Request for Additional Information Regarding Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2
NL-10-101, Response to August 11, 2010 Request for Additional Information Regarding Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual
NL-10-042, Response to January 20, 2010 Request for Additional Information Re Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
SECY-04-0233, Atch3 - Draft Regulatory Guide 1136, Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire
NRC-2017-0197, FRN: Exemption - Millstone Power Station, Unit No. 2 - Request for Exemption from Appendix R to 10 CFR Part 50, Section Iii.G (CAC No. MF8789; EPID L-2016-LLE-0002)
NRC-2012-0158, Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section lll.G.2
L-17-197, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
MNS-16-077, Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program
L-PI-16-005, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information
L-PI-03-102, Safety Evaluation Summary Report
AEP-NRC-2013-75, Response to a Request for Additional Information (RAI 63) Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805
AEP-NRC-2013-09, Revised Response to First Round Request for Additional Information Re Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805
NMP2L2745, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
RBG-44551, Responds to NRC Re Fire Protection Functional Insp Rept 50-458/97-201 on 970616-20 & 0630-0703.Requested Addl Info in Re Review of Certain Issues Found During Insp,Also Included
SVP-98-165, Provides Notification of Completion of Actions Listed in NRC CAL RIII-98-01,in Response to Directions of CAL to Notify NRC in Writing When Actions Listed in CAL Have Been Completed
SVP-98-135, Forwards Rept Crn 98-02, Safe Shutdown Rept for Quad Cities Station,Units 1 & 2. Safe Shutdown Rept Provided Quad Cities Revised Safe Shutdown Analysis in Event of Fire. Overview of Contents,Encl
3F0997-02, Forwards Summary of Plant App R Restart Design Items Covered Under Restart Item D-11,in Response to 970707 Rai.Schedule Shows That Most App R Related Construction Will Be Completed by Last Half of Nov 1997
3F0997-06, Provides Further Detail & Status on Unit 3 Resolution Plan for Information Notice 92-010 Re Potential for Loss of Remote Shutdown Capability During CR Fire
B17820, Annual Rept for Jan- Dec 1998. with
LIC-98-0021, Provides Info on Util Licensing & Design Basis for 10CFR50, App R,In Response to 980204 Telcon.Appendix R Design Basis for Fire in Cable Spreading Room,Encl
3F0298-03, Summarizes Key Elements of App R Restart Issue Work Scope & Provides NRC W/Clarifications of Two SERs Which Resulted,In Part,From Mods Made During Present & Previous Outages
RBG-36803, Responds to NRC Re Violations Noted in Insp Rept 50-458/92-04.Corrective Actions:Test Procedure Developed
U-603185, Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program
3F0797-33, Provides Addl Info on Independent Assessment That Was Conducted on Certain Portions of Fire Protection Program & Listing of Issues & Tracking Status
NPL-99-0219, Provides Final Notification of Change to Commitments Documented in LER 266/97-022-00 Re Electrical Short Circuits During CR Fire
BVY-96-130, Submits App R Fire Area Matrix,Specifying Station Shutdown Methods,Capabilities & Compensatory Actions for pre-outage
TXX-9529, Submits Suppl to Util W/Respect to Evaluations Performed for in 92-018, Potential for Loss of Remote Shutdown Capability During CR Fire
05000461/LER-1997-025, :on 971002,design Deficiency Resulted in Plant Being Outside Design Basis for Fire in Main CR Potentially Damaging Valves Required in Safe Shutdown of Plant.Cause Could Not Be Determined.Will Analyze MOV Control Circuits
05000285/LER-1997-009, :on 970619,potential Loss of Remote Shutdown Capability Occurred Due to Fire Induced Damage.Caused by Inadequate Design Basis Documentation.Operations Memo Provided Evacuation Criteria
05000254/LER-1997-002-02, :on 970127,several Isolable Piping Sections Could Experience Stresses Above Update FSAR Allowables Due to post-loss of Coolant Accident Thermal Pressurization. Initial Operability Evaluation Was Completed on 970124
05000373/LER-1996-016-03, :on 961106,discovered Hot Short Could Result in Damage to MOVs Required for Safe Hot Shutdown.Caused by Failure to Recognize Potential for Mechanical Valve Damage from Hot Shorts & Design Deficiency
05000440/LER-1996-006, :on 960718,MOV Control Circuitry Design Deficiency Resulted in Fire Protection Violation.Fire Impairment Was Issued for Control Room Fire Protection Features & Addl MOVs Considered for Mod
NSD-NRC-96-4908, Forwards Copies of Westinghouse Responses to NRC Request for Addl Info on AP600 Topics.Responses to Open RAI on SSAR Including 280.20,440.585,440.586 & 440.587
05000271/LER-1995-014, :on 950725,identified Deficiencies in Safe Shutdown Capability Analysis Resulted in Incomplete Implementation of 10CFR50 App R.Implemented Enhanced Awareness of Potential App R Vulnerabilities
05000254/LER-1996-011-02, :on 960708,determined Postulated Fire Could Have Caused Disabling Damage to Selected Motor Operated Valves.Caused by Inadequate Design Analysis Review.Movs Analyzed for Susceptibility to Single Failure
05000346/LER-1996-002, :on 960320,noted Potential for Loss of Remote Shutdown Capability.Caused by Fire Induced Hot Short Which Could Bypass Valve Protection Features.Implemented Hourly Roving Fire Watches & Completed Evaluations
NL-19-0536, Response to Request for Additional Information Regarding License Amendment Request for Transition to 1O CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants
NL-17-1962, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
PLA-4321, Responds to Request for Addl Info Re App R Safe Shutdown Analysis Fire Protection Review Rept,Rev 4
05000321/LER-2017-001, Regarding Unanalyzed Conditions for a Postulated Fire Discovered During NFPA 805 Transition
05000293/LER-2015-010, Regarding Motor-Operated Valve Control Circuit Vulnerability to Information Notice 92-18 Concern
05000454/LER-2015-004, Regarding Unanalyzed Condition Due to a Design Deficiency with Pressurizer Power Operated Relief Valve Circuitry That Could Prevent Valve Manual Closure to Mitigate Spurious Operation
05000413/LER-2014-002, Regarding Unanalyzed Condition Due to Deviations from Fire Protection Current Licensing Basis Identified During NFPA 805 Transition
NOC-AE-130029, License Amendment Request for Approval of a Revision to the South Texas Project Fire Protection Program Related to the Alternative Shutdown Capability
05000369/LER-2012-001, Regarding Appendix R Non-Compliance Could Have Potentially Affected Cold Shutdown
05000259/LER-2012-002, Regarding Fault Propagation During a Postulated Appendix R Event Could Result in an Inability to Close Motor Operated Valves
05000482/LER-2011-008, Regarding Post-Fire Safe Shutdown Latent Design Issue May Cause Essential Service Water System Flow Imbalance
HNP-10-008, Response to Second Request for Additional Information Regarding License Amendment Request to Anfp Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants
HNP-09-086, Second Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-based Standard for Fire Protection for Light Water Reactor.
RNP-RA/10-0090, Response NRC Request for Additional Information Related to Letter, Request for Extension of Enforcement Discretion During Transition to National Fire Protection Association Standard NFPA-805
05000269/LER-2003-001, For Oconee Nuclear Station, Regarding Design Oversight Resulting in Appendix R Control Cable Separation Issue
05000483/LER-2003-001, Re Improper Administrative Controls Result in Technical Specification Violation
RIS 2005-30, Clarification of Post-Fire Safe-Shutdown Circuit Regulatory Requirements
05000282/LER-2016-001, Regarding Unanalyzed Condition Due to Non-Compliant Fire Protection Manual Operator Actions
AEP-NRC-2013-55, Response to a Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 TAC (ME6629 and ME6630)
05000298/LER-1992-009, :on 920611,noncompliance w/10CFR50 App R, Failure of Post Fire Safe Shutdown Equipment Discovered. Caused by Inadequate Alternate Shutdown (ASD) Design Criteria.Asd Procedures Revised