CNL-17-024, Update to License Amendment Request to Revise NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor - Revision to Tables S-2 and S-3
CNL-17-130, Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for
CNL-17-109, Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Genera
PLA-7285, Revision (X) to EP-RM-004, EAL Classification Bases
L-2014-303, Response to Request for Additional Information Re License Amendment Request No. 216 - Transition to 10CFR50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
RS-13-117, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachments Iii, Iv, V & Vi: Technical Bases for Proposed EALs (Clean Copy), NEI 99-01 Revision 6 EA
RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. EPP-108, Enclosure 1, Revision 01 (Draft E)
NRC-2009-0046, Annual Monitoring Report, Cover Letter Through Part D, Groundwater Monitoring
RNP-RA/16-0079, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants
NRC 2013-0028, Point Beach Nuclear Plant, Units 1 and 2: License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2
RS-07-134, Co. and Amergen Energy Co., LLC, Response to Request for Additional Information Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
RA-18-0248, Response to Request for Additional Information Regarding License Amendment Request for Emergency Action Level Scheme Change
RA-20-0050, Emergency Action Levels CSD-EP-RNP-0101-02, Revision 0
ET 06-0004, Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program
NRC 2003-0081, Revised Emergency Plan Implementing Procedures
NRC 2003-0002, Emergency Plan Implementing Procedure Revisions
NL-20-1000, Responses to NRC Requests for Additional Information to License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time
A07137, Responds to SALP Repts 50-245/86-99 & 50-336/86-99 for June 1986 - Dec 1987.Util Responding W/Particular Emphasis on Board Recommendations for Individual Evaluation Categories
LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 2022
B10942, Forwards Response to Request for Addl Info,Question E291.19, Consisting of Documented Telcons Re Environ Rept - OL Stage
05000440/LER-1987-055, :on 870729,reactor Protection Sys Actuation Occurred Due to Trip Signal Generated by Neutron Monitoring Sys Aprm.Caused by Misposition of Switch S-3 on APRM Card. Failed APRM Card Replaced & Tested
05000482/LER-1986-050, :on 860925,resident Inspector Discovered That Fire Door 15031 Defeated by Piece of Foreign Matl,Violating Tech Spec 3.7.11.Caused by Personnel Neglecting to Ensure Proper Closure of Door.Personnel Counseled
U-600975, Forwards Dcrdr Final Rept Addressing Completion of Items Listed in Sser 5,Section 18.3.Attachment 2 Summarizes Human Engineering Observations & Deficiencies Identified & Assessed as Result of Review
05000348/LER-1981-059-03, /03L-0:on 810817,diesel Generator 1-2A Declared Inoperable After Failing to Reach Rated Speed & Voltage within Tech Spec Time Limit.Cause Not Determined.Generator Retested & Returned to Svc
A14212, Environ Temps in Vicinity of Rupture Point of Steam Lines for Equipment Qualification. Description of Equipment Location in Facility Encl
L-05-144, License Amendment Request Nos. 324 and 196 Re Steam Generator Tube Integrity
NRC 2003-0062, Emergency Plan Implementing Procedure Revisions, Point Beach, Units 1 & 2