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IA-85-771, Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities3 January 1986Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities
IR 05000277/198502918 December 1985Insp Repts 50-277/85-29 & 50-278/85-33 on 850914-1025. Violations Noted:Failure to Calibr Portal Monitor,Failure to Manually Test Relief Valves During Cycle 6 & Failure to Rept Reactor Protection Sys Actuations from 850829-1015
IR 05000277/198600723 May 1986Insp Repts 50-277/86-07 & 50-278/86-07 on 860327-0509. Violation Noted:Failure to Perform Jet Pump Operability Surveillance Requirements During Unit 3 Single Loop Operation
IR 05000277/198601624 October 1986Insp Repts 50-277/86-16 & 50-278/86-17 on 860816-0926. Violation Noted:Inadequate Planning & Procedures for DHR & Loss of Shutdown Cooling
IR 05000277/198601925 November 1986Insp Repts 50-277/86-19 & 50-278/86-20 on 860927-1107.No Violations Noted.Major Areas Inspected:Operational Safety, Radiation Protection,Physical Security,Control Room Activities,Licensee Events,Surveillance Testing & Maint
IR 05000277/198702328 October 1987Insp Repts 50-277/87-23 & 50-278/87-23 on 870810-14 & 17-19. Violations Noted.Major Areas Inspected:Implementation of QA Program for Procurement,Mod Control,Document Control & Records.Effectiveness of Quality Verification Reviewed
IR 05000277/19870248 January 1988Partially Withheld Safety Insp Repts 50-277/87-24 & 50-278/87-24 on 871017-1127 (Ref 10CFR2.790 & 73.21). Violations Noted.Major Areas Inspected:Operational Safety, Radiation Protection & Refueling & Outage Activities
IR 05000277/19880162 September 1988Exam Repts 50-277/88-16OL & 50-278/88-16OL on 880719-21.Exam Results:One Senior Reactor Operator Candidate & Seven Reactor Operator Candidates Passed Exams.One Candidate Failed Written Exam & One Candidate Failed Operating Test
IR 05000277/198901922 August 1989Onsite Regular,Backshift & Deep Backshift Special Power Ascension & Restart Insps 50-277/89-19 & 50-278/89-19 on 890618-0729.No Violations Noted.Major Areas Inspected: Accessible Portions of Units 2 & 3 & Physical Security
IR 05000277/19900175 October 1990Insp Repts 50-277/90-17 & 50-278/90-17 on 900814-0924.No Violations Noted.Major Areas Inspected:Operational Safety, Radiation Protection,Physical Security,Control Room Activities & Surveillance Testing
IR 05000277/199109931 December 1992Initial SALP Repts 50-277/91-99 & 50-278/91-99 for 910804 - 921031 Period
IR 05000277/19940104 August 1994Insp Repts 50-277/94-10 & 50-278/94-10 on 940605-0716.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Surveillance,Engineering & Technical Support
IR 05000277/20030044 November 2003IR 05000277-03-004, IR 05000278-03-004, on 06/29/2003 - 09/27/2003, for Peach Bottom Atomic Power Station, Units 2 and 3; Licensed Operator Requalification, Operability Evaluations, and Emergency Preparedness
IR 05000277/200300523 January 2004IR 05000277-03-005 & 05000278-03-005, on 09/28/2003 - 12/31/2003, for Peach Bottom, Units 2 and 3; Personnel Performance During Non-routine Plant Evolutions, Surveillance Testing, and Access Controls to Radiologically Significant Areas
IR 05000277/200300713 March 2003IR 05000277-03-007, on 01/13-30/2003, Peach Bottom Atomic Power Station; Unit 2. Special Inspection of the December 21, 2002, Unit 2 Automatic Reactor Scram
IR 05000277/200301318 December 2003IR 05000277-03-013, 05000278-03-013; 09/24/2003 - 11/18/2003; Peach Bottom Atomic Power Station, Units 2 and 3; Augmented Inspection Team
IR 05000277/20040045 November 2004IR 05000277-04-004 & 05000278-04-004, on 07/01/2004 - 09/30/2004; Peach Bottom Atomic Power Station, Units 2 and 3; Post-Maintenance Testing and Public Radiation Safety
IR 05000277/20050041 November 2005IR 05000277-05-004, 05000278-05-004; 07/01/2005 - 09/30/2005; Peach Bottom Atomic Power Station, Units 2 and 3; Operator Performance During Non-Routine Evolutions and Events, Emergency Response Organization Augmentation, Radiological..
IR 05000277/20060091 June 2006IR 05000277-06-009, 05000278-06-009; Exelon Nuclear LLC; on 03/17/2006, 03/31/2006, 04/14/2006 and 04/21/2006
IR 05000277/20090065 May 2009IR 05000277-09-006, 05000278-09-006, on 03/16/2009-04/03/2009, Exelon Generation Company LLC, Peach Bottom Atomic Power Station. Triennial Fire Protection Team Inspection
IR 05000277/20120078 June 2012IR 05000277-12-007 & 05000278-12-007, 04/30/2012 - 05/18/2012, Peach Bottom Atomic Power Station, Units 2 and 3, Triennial Fire Protection Baseline Inspection
IR 05000277/20130054 February 2014IR 05000277-13-005, 05000278-13-005; 10/01/2013 - 12/31/2013; Peach Bottom Atomic Power Station (Pbaps), Units 2 and 3; Integrated Inspection Report
IR 05000277/20140054 February 2015NRC Integrated Inspection Report 05000277/2014005 and 05000278/2014005 (October 1 - December 31, 2014)
IR 05000277/20225018 June 2022Emergency Preparedness Biennial Exercise Inspection Report 05000277/2022501 and 05000278/2022501
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position27 September 2021Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
JPN-87-051, Comment Opposing Draft NUREG-1150, Reactor Risk Ref Document. Reduced Uncertainty in Risk Assessment Found to Be Significant W/Respect to NUREG-1150.NUREG Also Does Not Consider Value of Operator Actions.Addl Comments Encl28 September 1987Comment Opposing Draft NUREG-1150, Reactor Risk Ref Document. Reduced Uncertainty in Risk Assessment Found to Be Significant W/Respect to NUREG-1150.NUREG Also Does Not Consider Value of Operator Actions.Addl Comments Encl
ML0204603205 February 2002ERP-101, Revision 23, Classification of Emergencies, and ERP-101 Bases, Revision 3, PBAPS EAL Technical Basis Manual.
ML02119000919 April 2002Part a - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40
ML02119002419 April 2002Part B - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40
ML02119006219 April 2002Part C - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40
ML02119011719 April 2002Part E - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40
ML02119013119 April 2002Part F - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40
ML02119017419 April 2002Part G - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40
ML02170050824 May 2002Final - Lsro Written
ML02171009610 June 2002License Amendment Request 02-00304, Safety Limit Minimum Critical Power Ratio (SLMCPR) Change
ML02259049830 September 2002SER Chapter 2, 2 Structures
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