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 Issue dateTitle
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
L-94-013, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01, for Plant30 November 1994Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01, for Plant
ML02123029925 March 2002Transmittal of Written Summary of Recent Reactor Water Level Indication Issues at Pilgrim Nuclear Power Station
ML03030044023 January 2003Request for Amendment to TS Emergency Core Cooling System Requirements During Shutdown Conditions
ML03097070522 April 2003License Amendment 200 Emergency Core Cooling System Requirements During Shutdown Conditions
ML03113030922 April 2003Tech Spec Pages for Amendment 200 Emergency Core Cooling System Requirements During Shutdown Conditions
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML0416706158 June 2004LER 99-008-01 for Pilgrim Regarding Automatic Scram at 100 Percent Power Due to Turbine Trip
ML06137062211 May 2006LER 06-01-000, Pilgrim Re Manual Scram Due to High Offgas Recombiner Temperature Resulting from Inadequate Preventive Recombiner Preheater Pressure Control Valve Controller
ML06187046930 June 2006Technical Specifications Amendment Request to Revise the Surveillance Requirements for the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems
ML07061045111 December 2006Draft - RO & SRO Written Exam (Folder 2)
ML07082036320 February 2007Final - RO & SRO Written Examination with Answer Key (401-5 Format) (Folder 3)
ML0806704197 March 2008CDBI Findings
ML09140006414 May 2009G20090292/LTR-09-0210/EDATS: SECY-2009-0248 - Mary E. Lampert, Rebecca J. Chin Pilgrim NPS RFO 2009: 2.206 Petition Requesting That NRC Require All Work Packages Inspected Prior to Pilgrim'S Re-start - Urgent Action Requested Due to Timing
ML10077045131 March 2010NEDO-33532, Rev 0, Pilgrim Nuclear Power Station Safety Valve Setpoint Increase.
ML11042030631 January 2011GE Hitachi Nuclear Energy Report, NEDC-33532, Revision 2, Pilgrim Nuclear Power Station Safety Valve Setpoint Increase, Enclosure 4 to 2.11.007
ML1106204747 January 2011Draft Written Exam (Draft 2)
ML11101040624 January 2011Final Written Examination with Answer Key (401-5 Format)
ML11326A1539 November 2011FSAR Update Revision 28, Technical Specifications Bases Changes, 10 CFR 50.59(d) Report, and Commitment Changes
ML13042A3029 February 2013PNO-I-13-001 - Pilgrim Station: Unusual Event Declared Due to Loss of Offsite Power During Winter Storm Nemo
ML13323A51814 November 2013Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel
ML14003A04612 December 2013FSAR Update Revision 29, Technical Specifications Bases Changes, 10 CFR 50.59(d) Report, and Regulatory Commitment Changes
ML15147A41227 May 2015IR 05000293/2015007; 02/02/2015 - 03/20/2015; Pilgrim Nuclear Power Station (Pnps); Special Inspection to Review the January 27, 2015 Partial Loss of Offsite Power (LOOP) and Reactor Scram Event; Inspection Procedure 93812, Special Inspecti
ML15202A41517 July 2015Station'S Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, Submittal of Final Integrated Plan, Response..
ML16055A46118 February 2016Emergency Plan Implementing Procedure Revisions, Including Revision 6 to EP-AD-601 and Revision 8 to EP-IP-261
ML16083A44830 November 2015Redacted - Updated Final Safety Analysis Report (UFSAR) Part 1 - November 2015
ML16083A45330 November 2015Redacted - Updated Final Safety Analysis Report (UFSAR) Part 2 - November 2015
ML16083A46130 November 2015Redacted - Updated Final Safety Analysis Report (UFSAR) Part 3 - November 2015
ML16211A06722 July 2016Errata Change for Final Safety Analysis Report Revision 30
ML17202G68017 July 2017Attachment 1 of Letter Number 2.17.053, EP-AD-601, Emergency Action Level Technical Bases Document, Revision 8 and Associated 10 CFR 50.54(q) Review
ML18158A1307 June 2018Evaluation - Memorandum Regarding Licensee Event Report Safety Significance Review in Response to Findings Associated with Inspection Procedure 95003; Evaluation of NRC Assessment and Inspection Processes at Pilgrim Nuclear Power Station
ML18194A58711 July 2018Attachment 1 to 2.18.045, EP-AD-301, Emergency Action Level Technical Bases Document, Revision 9 and Associated 10 CFR50.54(q) Review
ML19211A15930 October 1979Tech Specs for post-accident Monitoring Instrumentation, Containment Sys & Special Test Exceptions
ML20002C0635 January 1981Responds to NUREG-0737.Provides Info Re Shift Technical Advisor,Guidance for Evaluation & Development of Procedures for Transients & Accidents,Procedures for Feedback of Operating Experience & Training for Mitigating Core Damage
ML20002E38122 January 1981Forwards Addl Info in Response to NUREG-0737 Requirements Re Containment Isolation Dependability,Eccs Outage Rept & Auto Switchover of Reactor Core Isolation Cooling
ML20005D7426 December 1989LER 89-033-00:on 891106,automatic Actuation of Group 1 Portion of Primary Containment Isolation Control Sys (PCIS) Occurred.Caused by High Reactor Vessel Water Level.Manual Valve Closed & PCIS Logic Circuitry reset.W/891206 Ltr
ML20005G0988 January 1990LER 89-038-00:on 891208,unplanned Automatic Reactor Protection Sys Scram Signal & Reactor Scram Occurred.Caused by False Low Reactor Vessel Water Level Signal.Local Level Indicators Satisfactorily calibr.W/900108 Ltr
ML20006A26315 January 1990Forwards Summary of Compliance W/Reg Guide 1.97,Rev 3 Re Emergency Response Capability.Util Endorses BWR Owners Group Position That Fully Qualified Class 1E post-accident Neutron Monitoring Sys Inappropriate
ML20011D16531 December 1989Final Assessment Rept.
ML20012D44915 March 1990Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Core & Containment Cooling Sys & Core Spray & LPCI Sys
ML20012F5756 April 1990LER 90-003-00:on 900311,automatic Actuation of Main Steam Sys Group 1 Portion of Primary Containment Isolation Control Sys Occurred.Caused by False High Reactor Vessel Water Level Signal.Procedure Developed Re backfill.W/900406 Ltr
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