05000400/LER-2001-004, Re Reactor Coolant Loops Made 4 Technical Specification Violation
2CAN071701, License Amendment Request, Application for Technical Specification Improvement to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-1432
L-2016-227, License Amendment Request Change to P /T Limit Curve and LTOP Period of Applicability
2CAN121303, Response to Request for Additional Information Adoption of Technical Specification Task Force (TSTF)-422
2CAN071201, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
2CAN041201, License Amendment Request, Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases
L-2011-438, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205
NUREG-1432, Issuance of Amendment No. 310 Technical Specification Changes to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-1432, Revision 4 (CAC No. MG0016; EPID L-2017-LLA-0268)
LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power Oscillations
L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08
L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007
RC-07-0025, License Amendment Request - LAR 05-3594 Steam Generator Tube Integrity
L-2006-229, Response to Request for Additional Information - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
HNP-06-116, Response to Request for Additional Information Regarding License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
L-06-131, Core Operating Limits Report, COLR 18-1 Pressure and Temperature Limits Report, Revision 2
HNP-06-060, License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
L-2006-094, Proposed License Amendment Steam Generator Tube Integrity Pursuant to 10 CFR 50.90
2CAN050601, Response to NRC Request for Additional Information on ANO-2 Steam Generator Tube Inservice Inspection Program
L-2006-074, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
W3F1-2006-0016, To Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program
W3F1-2006-0007, Supplement to Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program
2CAN081903, License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-1432
L-05-063, Pressure and Temperature Limits Reports, Revision 1
SBK-L-19129, Submittal of Changes to the Seabrook Station Technical Specification Bases
W3F1-2003-0075, Ses, Unit 3, License Amendment Request NPF-38-250, Revision to Pressure/Temperature and Low Temperature Overpressure Protection Limits for 32 Effective Full Power Years
L-03-151, Original Issuance of the Pressure and Temperature Limits Report
L-2003-140, Response to Request for Additional Information for Proposed License Amendment - Administrative Update of Technical Specifications
W3F1-2002-0095, License Amendment Request NPF-38-243 Reactivity/Boron Concentration Changes
L-2002-074, Emergency Plan Implementing Procedure Changes
HL-4587, Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained
2CAN052103, Response to Request for Additional Information Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP)
B17261, Responds to NRC Re Violations Noted in Insp Rept 50-423/97-83.Corrective Actions:Deficient Surveillance Procedures Were Corrected,Dc 4 Re Procedure Compliance Was Revised & Presentations Were Given Personnel Re DC 4
B12676, Forwards Response to 870709 Generic Ltr 87-12 Re Loss of RHR While RCS Partially Filled.Description of Circumstances & Conditions Under Which Facilities Would Enter Draindown Process W/Rcs Partially Filled Encl
B17128, Forwards Response to Request for Addl Info Re Proposed Rev to TS Reactor Coolant Sys Heatup/Cooldown Limits & Low Temp Overpressure Protection
SBK-L-21104, Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension
B12359, Application for Amend to License NPF-49,changing Tech Spec Sections 3.4.1.3 & 3/4.4.1 Re Limiting Condition for Operation for Number of Reactor Coolant Loops in Operation During Hot Shutdown Conditions.Fee Paid
B16845, Responds to 971028 RAI Re Util 970829 Amend to License NPF-49 to Revise TS to Resolve Inconsistencies Re Cold Overpressure Protection Sys Enabling Temperature & Eccs/ Charging Sys Mode 3 Requirements
B16519, Monthly Operating Rept for May 1997 for Millstone Nuclear Power Station,Unit 2
B16464, Monthly Operating Rept for Apr 1997 for Millstone,Unit 2
B16376, Monthly Operating Rept for Mar 1997 for Mnps,Unit 2
2CAN112104, Response to Request for Additional Information 2 Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP)
BSEP-92-0050, Annual Rept Per 10CFR50.59 for 1991. Rept Contains Tests & Experiments Conducted in 1991 But Not Described in Fsar
RC-96-0182, Responds to RAI Re GL 95-07, Pressure Locking and Thermal Binding of Safety-Related Power Operated Gate Valves
B14108, Application for Amend to License NPF-49,changing TS Figure 3.1-5, Required Shutdown Margin for Mode 5 W/Rcs Loops Not Filled, Section 3.4.1.3, RCS - Hot Shutdown & 4.4.1.1.3, RCS - Hot Shutdown Surveillance Requirements
ELV-01901, Application for Amends to Licenses NPF-68 & NPF-81,revising Tech Spec (TS) 3.4.1.3 Re Starting Reactor Coolant Pump & Providing Consistency Between Ts,Rcs Analysis Assumptions Demonstrating Compliance W/App G Limits & RHR Analysis
L-05-177, Responses to a Request for Additional Information (RAI Dated November 1, 2005) in Support of License Amendment Request Nos. 302 and 173
L-04-074, License Amendment Request Nos. 326 and 177
L-2006-089, Proposed License Amendment Steam Generator Tube Integrity
L-2007-071, Reply to Request for Additional Information Re Steam Generator Tube Integrity Amendment Request
B16559, Proposed Tech Specs Revising TS 4.6.1.1,3/4.6.1.2 & 3/4.6.1.3 & Bases Sections 3/4.6.1.1,3/4.6.1.2 & 3/4.6.1.3 Modifying List of Valves That Can Be Opened in Modes 1 Through 4 & Adding Footnote on Procedure Controls
L-2022-176, License Amendment Request to Revise Cooling Tower Service Water Loop or Cell Requirements
L-2008-149, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
RC-06-0084, License Amendment Request - LAR 05-3594, Steam Generator Tube Integrity
L-2019-076, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
05000382/LER-1988-013, :on 880528,fire Protection Sprinkler Found Isolated After Restoration from Testing.Caused by Personnel Error.Procedures Being Revised to Require Contaminated Valve Lineup Sheets Be Photocopied or Verified
05000454/LER-1997-004-01, :on 970215,thrust Bearings Were Installed Backwards on Rh & CS Pumps Due to Lack of Specific Sys/Component.Completion of Nwrs Written to Check End Play on Rh & CS Pump Motors Will Be Tracked
05000344/LER-1992-032, :on 921111,identified That Operating Procedures Allowed RHR Sys Flow Rate to Be Less than Rate Assumed in Accident Analysis Due to Personnel Error.Analysis & Procedures Revised
05000336/LER-1996-001, :on 960625,discovered Reactor Coolant Sys Heatup Rate Exceeded Tech Spec.Caused by Design & Procedural Weaknesses Re Plant Heatup Controls.Revised Plant Operating Procedures & Heatup/Cooldown Computer Program
NRC-98-0003, Application for Amend to License NPF-43,revising Tech Specs to Improve Administrative Controls Re thermal-hydraulic Stability & Idle Recirculation Loop Startup & Eliminating Neutron Flux Indication from TS
05000389/LER-1983-056-03, /03L-0:on 830907,w/shutdown Cooling (SDC) Train 2B in Operation,Sdc Train 2A in Injection Mode & Loop B Reactor Coolant Pumps Inoperable,Loop a Pumps Made Inoperable.Caused by Erroneously Racking Out Pumps
AECM-90-0089, Forwards Draft Tech Specs for Power Distribution Limits,Rcs, ECCS & Plant Sys as Part of Util Involvement W/Bwr Owners Group as BWR-6 Lead Plant
05000325/LER-1982-003-01, /01T-0:on 820118,idle Reactor Recirculation Pump Allowed to Start W/Greater than 50% Operating Loop Flow. Caused by Failure to Revise Applicable Plant Procedures. Procedures Revised
ST-HL-AE-3659, Forwards Response to Generic Ltr 90-06, Resolution of Generic Issue 70, PORV & Block Valve Reliability & Generic Issue 94, Addl Low Temp Overpressure Protection for Lwrs. License Amend Submitted on 901222 Re Generic Ltr
05000327/LER-1981-021-03, /03L-0:on 810211,reactor Coolant Pumps 1 & 2 Were Stopped.Caused by RCS Pressure Going to Zero After RHR Containment Spray Isolation Valve Inadvertently Opened.Pumps Returned to Operable Status in Approx 1-h
HNP-12-130, Transmittal of Technical Specifications Bases
HNP-15-046, Transmittal of Technical Specifications Bases
2CAN121901, License Amendment Request Technical Specification Deletions, Additions, and Relocations
L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
LR-N970150, Application for Amends to Licenses DPR-70 & DPR-75, Correcting Editorial & Administrative Errors in Ts,Which Existed Since Initial Issuance
L-2018-075, Response to Request for Additional Information Regarding License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications .
L-96-177, Forwards Revisions to EPIP-20106, Natural Emergencies. Provisions for Seismic Event Have Been Added to Address GL 87-02
05000250/LER-1988-030, :on 881202,determined That Safety Injection Accumulator Level Tech Spec Limits Possibly Exceeded During Operation.Caused by Errors in Design Which Installed Transmitters.Transmitters Being Replaced
05000335/LER-1995-006, :on 950810,reactor Coolant Inventory Through Shutdown Cooling Relief Valve Was Lost Due to Lack of Design Margin.Increased Lift Setpoint Pressure & Reduced Minimum Required Blowdown
05000397/LER-1996-003, :on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures Revised
05000397/LER-1991-002, :on 910110,reactor Recirculation Sys Jet Pump Operability Surveillance Testing Did Not Meet Literal Compliance W/Tech Specs.Caused by Inadequate Procedure. Procedure Revised
2CAN121403, License Amendment Request Supplemental Adoption of Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186)
2CAN031303, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-422, Revision 2 ‘‘Change in Technical Specifications End States (CE NPSD-1186)
L-2009-099, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4
L-02-094, Technical Specifications Bases Change Submittal
05000354/LER-2008-001, Reactor Recirculation Pump Motor Generator Set Scoop Tube Mechanical and Electrical Stop Over Speed Set Points Found Outside of Technical Specification Limits
05000251/LER-2005-005, Re Loss of Offsite Power Causes Engineered Safety Feature Actuations
B18615, Changes to Technical Specifications Bases
B18556, Technical Specifications Change Requests 2-21-01 and 3-18-01 Re Relocation of Selected Technical Specifications Related to the Reactor Coolant System and Plant Systems
L-98-065, Forwards Revised Epips,Including 0-EPIP-20106, Natural Emergencies, 0-EPIP-20132, Technical Support Center Activation & Operation, & 0-EPIP-20133, Operations Support Center Activation & Operation
RA-21-0282, Submittal of Updated Final Safety Analysis Report (Amendment 64), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes
2CAN112004, License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP)
L-2016-084, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2, Change in Technical Specifications End States
2CAN061302, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471