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 Issue dateTitle
L-21-098, Response to Request for Additional Information (RAI) - License Amendment Request to Approve the Pilgrim Nuclear Power Station Independent Fuel Storage Installation Only Emergency Plan7 September 2021Response to Request for Additional Information (RAI) - License Amendment Request to Approve the Pilgrim Nuclear Power Station Independent Fuel Storage Installation Only Emergency Plan
ML21076A40417 March 2021License Amendment Request to Revise Pilgrim Nuclear Power Station Permanently Defueled Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool
L-21-008, License Amendment Request to Approve Pilgrim Nuclear Power Station Independent Spent Fuel Storage Installation Only Emergency Plan18 February 2021License Amendment Request to Approve Pilgrim Nuclear Power Station Independent Spent Fuel Storage Installation Only Emergency Plan
ML19212A65112 August 2019Transmittal of Final Accident Sequence Precursor Report (Licensee Event Report 293-2019-001)
ML19169A27912 August 2019Final Accident Sequence Precursor Analysis- Pilgrim Nuclear Power Station, Reactor Core Isolation Cooling System Declared Inoperable During Surveillance Testing
IR 05000293/201800214 August 2018Integrated Inspection Report 05000293/2018002
ML18218A1741 August 2018Revised the Emergency Plan and Emergency Action Level Scheme to Address the Permanently Defueled Condition
ML18179A16321 June 2018Retraction of Licensee Event Report 2018-002-00, Diesel Generator a Inoperability, a Condition Prohibited by the Plant Technical Specifications
IR 05000293/201700921 December 2017Problem Identification and Resolution Inspection Report 05000293/2017009
IR 05000293/201700214 August 2017Integrated Inspection Report 05000293/2017002
05000293/LER-2017-0107 August 2017Air Accumulation Creates Small Void in Core Spray Discharge Piping
LER 17-010-00 for Pilgrim re Air Accumulation Creates Small Void in Core Spray Discharge Piping
05000293/LER-2017-00325 May 2017Supplement to Suppression Pool Declared Inoperable Due to High Water Level
LER 17-003-00 for Pilgrim Nuclear Power Station Regarding Pressure Suppression Pool Declared Inoperable Due to High Water Level
IR 05000293/201700115 May 2017Integrated Inspection Report 05000293/2017001
IR 05000293/201601110 May 2017Supplemental Inspection Report (Inspection Procedure 95003 Phase 'C') 05000293/2016011 and Preliminary Greater-than-Green Finding
05000293/LER-2016-0089 December 2016Emergency Diesel Generator 'A' Past Inoperability
LER 16-008-00 for Pilgrim Nuclear Power Station Regarding Emergency Diesel Generator 'A' Past Inoperability
ML16320A15515 November 2016Region I Response to Lochbaum E-mail a and B EDG Operability Concerns
IR 05000293/201500211 August 2015IR 05000293-15-002; 04/01/2015 - 06/30/2015; Pilgrim Nuclear Power Station (Pilgrim); Equipment Alignment, Operability Determinations and Functionality Assessments, and Follow-Up of Events and Notices of Enforcement Discretion
ML14094A15525 March 2014Final Written Examination with Answer Key (401-5 Format) (Folder 2)
IR 05000293/201100328 July 2011IR 05000293-11-03, on 04/1/11 - 06/30/11; Pilgrim Nuclear Power Station NRC Integrated Inspection Report
ML10295057223 January 2009Task Interface Agreement - Evaluation of Application of Technical Specification 4.0.3, Surveillance Requirement Applicability, at Pilgrim
ML08366017423 January 2009TIA - Task Interface Agreement - Evaluation at Pilgrim of Application of TS 4.0.3, 12/31/08
ML10295057623 January 2009Task Interface Agreement Evaluation of Application of Technical Specification 4.0.3, Surveillance Requirement Applicability, at Pilgrim
ML09103048821 November 2008Draft - RO & SRO Written Exam (Folder 2)
ML07261019718 September 2007Technical Specifications, Adoption of Technical Specification Task Force (TSTF) Change TSTF-372, the Addition of Limiting Condition for Operation (LCO) 3.0.8 on the Inoperability of Snubbers
ML0631303512 November 2006Application for Technical Specification (TS) Change to Add LCO 3.0.8 on the Inoperability of Snubbers (and Adoption of TS Bases for LCO 3.0.8) Using the Consolidated Line Item Improvement Process (CLIIP)
ML05076017716 March 2005Tech Spec Pages for Amendment No. 211, Revise Reactor Vessel Hydrostatic and Leak Testing Requirements
IR 05000293/200400416 July 2004IR 05000293-04-004, on 04/01/2004 - 06/30/2004, Pilgrim Nuclear Power Station; Maintenance and Risk Assessment and Emergent Work Control
ML04113027914 April 2004Request for Amendment to the Technical Specifications Reactor Vessel Hydrostatic and Leak Testing Requirements
ML03274027830 September 2003Technical Specification Pages, Adding New Technical Specification Requirement as 4.0.3
ML0316813876 June 2003Request for Additional Information Request for Amendment to the Technical Specifications Consolidated Line Item Improvement Process (CLIIP) Implementation of TSTF-358 - Missed Surveillance Requirements
ML02238034616 August 2002Request for Amendment to the Technical Specifications Consolidated Line Item Improvement Process (Clip) Implementation to TSTF-358 - Missed Surveillance Requirements
ML20137E56718 March 1997Insp Rept 50-293/97-01 on 970112-0302.Violations Noted.Major Areas Inspected:Operations,Engineering & Plant Support
IR 05000293/199600630 October 1996Insp Rept 50-293/96-06 on 960729-0923.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support
Information Notice 1996-44, Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly5 August 1996Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly
ML20094C8971 November 1995Part 21 Rept Re Valves Being Supplied W/Bushings Made of Babbitt Graphalloy Instead of Graphite.Corrective Actions: Ring-O-Valve Spa Supplied Replacement Nickel Graphalloy Bushings
ML20042F59130 April 1990LER 90-006-00:on 900330,determined That Position of Primary Containment Sys Isolation Valve Not Recorded Daily,Per Tech Specs.Review Performed to Determine If Other Problems Existed.Plant Shut Down & Review performed.W/900430 Ltr
ML20012E98330 March 1990LER 90-002-00:on 900228,determined That Max Fraction of Limiting Power Density Not Checked Daily During Reactor Power Operation,Per Tech Spec 4.1.B.On 900323,addl Tech Spec Issue Discovered.Tech Specs changed.W/900330 Ltr
ML19351A4586 December 1989LER 89-034-00:on 891108,determined That Reactor Pressure Exceeded 150 Psig on 891107 W/O Performing Surveillance Procedure 8.5.4.4, HPCI Valve Operability Test. Caused by Personnel Error.Procedure initiated.W/891206 Ltr
ML20151C67430 March 1988Partially Withheld Enforcement Conference Insp Rept 50-293/87-30 on 870909 (Ref 10CFR73.21).Major Areas Discussed:Status of Security Program & Allegations Re Deficiencies in Security Program
IR 05000293/198701622 May 1987Insp Rept 50-293/87-16 on 870221-0406.One Violation Noted: Failure to Properly Implement Fire Protection Equipment Surveillance Procedures
IR 05000293/198600628 March 1986Insp Rept 50-293/86-06 on 860218-0307.Violation Noted: Replacement Squib Charges Installed in Standby Liquid Control Sys (SLCS) from Batch Not Tested During Manual Initiation of SLCS
ML20137Y55031 December 1985AEOD/T516, HPCI Overspeed Trip Loss Events & Subsequent Damage Due to Water Hammer, Technical Review Rept.Item Remains Unresolved Pending Development & Approval of Licensee Final Corrective Action
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