LR-N16-0164, Core Operating Limits Report, Reload 19, Cycle 20, Revision 12
LR-N15-0071, Core Operating Limits Report, Reload 18, Cycle 19, Revision 10
LR-N13-0253, Core Operating Limits Report, Reload 18, Cycle 19, Revision 9
LR-N12-0148, Attachment 2 to LR-N12-0148 - Core Operating Limits Report, Reload 17, Cycle 18, Revision 7 (Non-Proprietary Version)
LR-N12-0075, Core Operating Limits Report, Reload 16, Cycle 17, Revision 6
LR-N11-0366, Core Operating Limits Report, Reload 16, Cycle 17, Revision 5
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
HNP-11-001, Request for License Amendment, Measurement Uncertainty Recapture Power Uprate
LR-N18-0055, Hope Creek - Attachment 2 to LR-N18-0055, Core Operating Limits Report, Reload 21, Cycle 22, Revision 14
LR-N17-0044, Hope Creek - License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate
LR-N10-0355, Hope Creek, HC.OP-AR.ZZ-0011(Q), Rev. 53, Overhead Annunciator Window Box C6
RS-10-002, Request for License Amendment Re Measurement Uncertainty Recapture Power Uprate
LR-N09-0164, License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items
LR-N09-0143, License Amendment Request to Relocate the Reactor Recirculation System Motor-Generator (MG) Set Scoop Tube Stop Setting Surveillance
LR-N09-0115, Core Operating Limits Report, Reload 15, Cycle 16, Revision 3
LR-N09-0046, Request for Relief from ASME OM Code Test Intervals for Pressure Relief Valves
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
LR-N08-0205, Clarifications to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174
LR-N08-0211, Core Operating Limits Report, Reload 14, Cycle 15, Revisions 1 and 2
LR-N07-0275, Core Operating Limits Report - Cycle 15
L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
LR-N07-0228, Core Operating Limits Reports - Cycle 14, Revision 1
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-2007-003, Reply to Request for Additional Information, Steam Generator Tube Integrity Amendment Request
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-06-132, Supplement to License Amendment Request No. 183 - Submittal of Final Proposed Technical Specification Changes
L-06-119, Supplement to License Amendment Request Nos. 324 and 196, Steam Generator Tube Integrity
L-06-088, Supplement to License Amendment Request Nos. 324 & 196 Steam Generator Tube Integrity
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
LR-N06-0214, Core Operating Limits Report - Cycle 14
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
LR-N06-0008, Core Operating Limits Report - Cycle 13, Revision 3
05000272/LER-1993-006, :on 930221,station Power Transformers 12 & 22 Deenergized Due to Tripping of Common 13 Kv Ring Bus Section 4 Breakers & 500 Kv Section 1 Breakers.Caused by Inadequate Communication.Caution Tags Hung on Breakers
LR-N05-0538, Core Operating Limits Report - Cycle 13, Revision 2
LR-N19-0101, Submittal of Core Operating Limits Report, Reload 22, Cycle 23, Revision 17
LR-N05-0096, Core Operating Limits Report - Cycle 13
LR-N05-0001, Restart Readiness Hope Creek Generating Station. Includes HC.ER-AP.BB-0001 (Z) Rev. 0, HC.OP-AB.RPV-0003(Q) Rev 7, HC.OP-AR.ZZ-0008(Q) - Rev. 27
05000366/LER-1981-030-03, /03L-0:on 810413,valve Position Indicating Lights for Recirculation Pump B Discharge valve,2B31-F031B,found Extinguished.Caused by Blown Fuse in Control Circuit. Integrity of Circuit Verified & Fuse Replaced
05000366/LER-1981-017-03, /03L-0:on 810305,recirculation Pump B Failed During Power Changes from 1343 Mwt.Caused by Undervoltage from Exciter of Recirculation Motor Generator Due to Loss of Excitation from Collector Ring & Brush Degradation
PLA-4055, Forwards Proposed Amend 117 to License NPF-22 Re Power Uprate W/Increased Flow
LR-N20-0064, Core Operating Limits Report, Reload 22, Cycle 23, Revision 18
LR-N20-0083, Core Operating Limits Report, Reload 22, Cycle 23, Revision 19
LR-N21-0042, Core Operating Limits Report, Reload 23, Cycle 24, Revision 21
B16595, Application for Amend to License DPR-65,incorporating Various Compliance Issues Identified in TS
L-96-034, TER on Third 10-Yr Interval ISI Program Plan:Nppd Cns
SNRC-1570, Forwards Changes to Initial Test Program Described in Chapter 14 of Plant Usar.Changes Include Deletions/Revs of Startup Test Procedures & Station Procedures Described in Facility USAR
RBG-40869, Provides Response to GL 94-02, Long-Term Solutions...For Thermal-Hydraulic Instabilities in Bwrs. Util Has Elected to Implement Enhanced Option I-A as long-term Stability Option.Enhanced Option I-A Described in NEDO-32339
NRC-97-0084, Responds to Violations Noted in Insp Rept 50-341/97-07. Corrective Actions:Personnel Initiated DER 97-1012 & Removed MDCT Tag,Conducted Lessons Learned Meeting,Verified Enclosure Internal Strip Heater to Working & Repaired Door
PY-CEI-NRR-0933, Submits Supplemental Response to NRC Bulletin 88-007 Re Proposed Changes to Avoid Power/Flow Region of Potential Instability & Further Instructions for Cram Rod Insertion or Manual Scram Under Particular Conditions
PY-CEI-NRR-1951, Forwards Supplemental Info Re Previous Applications for Amend to License NPF-58 for Conversion of Current TS to TS Based on NUREG-1434, Improved BWR6 TS, Per Discussions W/ NRC Re Acceptability of Proposed Changes to LCO 3.0.4
L-2006-212, Reply to Request for Additional Information Steam Generator Tube Integrity Amendment Request
2CAN121903, License Amendment Request, Revise Control Element Assembly Drop Time
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
LR-N03-0511, Request for Change to Technical Specifications Regarding Fuel Vendor Change
L-2008-149, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
LR-N05-0357, Core Operating Limits Report - Cycle 13, Revision 1
LR-N19-0015, Core Operating Limits Report, Reload 21, Cycle 22, Revision 15
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
05000324/LER-1986-022-01, :on 861003,reactor Shut Down Due to Unsuccessful Restart of Motor Generator Set.Caused by Opened Fuses.Fuse 7 Transformer Replaced,Motor Generator Restarted & Loop Returned to Svc
05000446/LER-1998-001-01, :on 980116,TS Surveillance for Reactor Trip Sys Instrumentation Was Missed Due to Personnel Error.Lessons Learned & Managements Expectation W/Respect to Completing Required Surveillance Have Been Reemphasized
05000458/LER-1988-006, :on 880219,reactor Shutdown Required by TS Due to Reactor Recirculation Pump Motor Trip.Caused by Moisture Intrusion from Leaking Svc Water Valve.Leaking Valve Repaired & Termination Cabinet Cleaned & Dried
05000373/LER-1996-010, :on 960829,violations of TS & Design Basis Occurred.Caused by Inadequate Standards for TS Clarification.Deleted Clarifications in Question on 960829 & Revised One Clarification
05000397/LER-1985-049, :on 850720,core Pressure Drop Baseline Data Not Obtained While Increasing Power Above 50% Rated Core Thermal Power in Single Recirculation Loop Operation.Power Reduced to Thermal Power Limit for Data
05000389/LER-1985-009-02, :on 850910,high Vibrations Occurred on Reactor Coolant Pump 2A2,causing Manual Trip.Caused by Pump Vibration Permitting Oil Slinger Ring to Break Free & Damaged Oil Seal in Oil Reservoir
05000324/LER-1983-074-03, /03L-0:on 831006,reactor Recirculation Pump 2A Tripped Due to Motor Generator Set High Fluid Drive Temp. Caused by Slight Mechanical Shock of Motor Generator Set Fluid Drive High Temp Trip Device
05000324/LER-1983-087-03, /03L-0:on 830920,reactor Recirculation Pump 2A Tripped Due to Unintentional Actuation of Atws/Rpts Instrument B21-LTM-NO24A.Caused by Inadvertent Selection of Card File Location 3.Trip Condition Reset
05000324/LER-1983-067-03, /03L-0:on 830724,while Performing Rpts,Reactor Low Water Recirculation Pump 2A Tripped When Temporary Electrical Jumper Removed.Caused by Removal of Wrong Jumper
05000324/LER-1983-009-03, /03L-0:on 830118,reactor Recirculation Pump 2A Tripped When Pump Motor Generator Set Drive Motor Tripped. Caused by Actuation of Motor Generator Set Drive Motor Field Overcurrent Relay Device 27.Trip Signal Reset
05000387/LER-1983-025-03, /03L-0:on 830204,reactor Recirculation Pump a Tripped off-line During Startup Test Program.Caused by Deficiency in Silicon Controlled Rectifier,Resulting in High Field Circuit Current.Voltage Regulator Board Replaced
05000328/LER-1990-017-02, :on 901123,reactor Trip Occurred as Result of low-pressurizer Pressure.Caused by Misunderstanding by Lead Reactor Operator & Failure to Maintain T Average & T Ref During Shutdown
05000325/LER-1982-022-03, /03L-0:on 820417,reactor Circulation Pump 1A Tripped Due to Motor Generator Set Undervoltage,Resulting from Spurious Opening & Closing of Unit Switchyard Pcb 23A & 23B.Caused by Transmission Line Perturbations
05000325/LER-1982-023-03, /03L-0:on 820211,during Operation,Amplifier Board Circuitry of Dc Electrical Battery Charger 1B-2 Experienced Momentary Failure Resulting in High Charger Output Voltage Which Caused Div II Analog Power Supply Inverters to Tr
05000366/LER-1993-005-02, :on 930521,unplanned Insertion of Manual Scram Initiated Due to Personnel Error.Personnel Involved Temporarily Removed from License Duties & Being Subjected to Formal Discipline
05000289/LER-1990-003, :on 900227,turbine Bypass Valves Isolated During Plant Heatup Due to Main Steam Valve Closure.Caused by Personnel Error.Personnel Reviewed Event to Emphasize Need to Follow Administrative Requirements
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
05000324/LER-1982-016-03, /03L-0:on 820214,during Plant Operation,Reactor Recirculation Pump Tripped.Caused by Accidental Dropping of RTGB On/Off Indication Lights for Pump Motor Generator Set Drive Motor Power Supply Breaker Into Module Socket
05000325/LER-1982-011-03, /03L-0:on 820118,1B Reactor Recirculation Pump Tripped While Technicians Were Investigating Slight Indication Variance of ATWS-RPT instrument,1-B21-LTM-N025B-2 to Other Redundant Indications.Caused by Use of Wrong Meter
05000413/LER-1990-020, :on 900324,low Pressure Indication Noted on Cardox Carbon Dioxide Storage Unit & Continuous Fire Watch Not Provided within 1 H.Caused by Personnel Lack of Attention to Detail.Fire Watch Established
05000324/LER-1981-052-03, /03L-0:on 810609,reactor Recirculation Pump Motor Generator 2A Tripped During Unit Load Changes.Cause Unknown. Dirty Electrical Contacts Found in Field Breaker Closure Circuitry Cleaned
05000325/LER-1981-033-03, /03L-0:on 810305,brushes on 1A Reactor Recirculation Pump Motor Generator Found Arcing.Caused by Oily Film on Exciter Collector Rings Which Allowed Accelerated Brush Wear.Rings Cleaned & Brushes Replaced
05000325/LER-1980-058-03, /03L-0:on 800822,during Normal Surveillance, Drywell Flow Integrator Failed to Change While Sump Pump Was Running.Caused by Blown Fuse in Drywell Floor Drain Flow Transmitter Power Supply.Fuse Replaced
HNP-12-130, Transmittal of Technical Specifications Bases
HNP-15-046, Transmittal of Technical Specifications Bases
05000289/LER-1990-003-01, :on 900227,isolation of Turbine Bypass Valves Due to Main Steam Valve Closure.Caused by Personnel Error. Personnel Will Review Event in Order to Emphasize Need to Follow Proper Administration
SNRC-1770, Application for Amend to License NPF-82,replacing Tech Spec Pages 3/4 4-1 & 3/4 4-3 of Proposed Defueled Tech Specs
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
05000324/LER-1979-088-03, /03L-0:on 791206 & 13,reactor Recirculation Pump 2B Tripped.Possibly Caused by Short Brushes on Exciter Collector Rings Causing Degraded Excitation for Generator Field Which Forced Voltage Regulator Fuses to Blow
05000325/LER-1978-096-03, /03L-0 on 781211:loss of Normal Power to Bus E-1 Caused by a 1/2 Scram & a 1/2 Group No 1 Isolation.Cause Unknown,But Suspected to Be Const Activities Associated W/ Fire Protection Mods
LR-N19-0038, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR
GO2-95-228, Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys
05000389/LER-1987-008-03, :on 871128,oil Fire Occurred at Reactor Coolant Pump (Rcp).Caused by Oil Leak from Loose Packing Gland on Instrument Isolation Valve.Leaking Valve Repaired.Visual Insp & Leak Test Conducted on 2A1 RCP Oil Pans
RC-13-0047, License Amendment Request - LAR 12-03567, Application to Revise Tech Specs to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line Item Improvement
LR-N13-0222, Core Operating Limits Report, Reload 17, Cycle 18, Revision 8
L-2009-099, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4
L-05-144, License Amendment Request Nos. 324 and 196 Re Steam Generator Tube Integrity
L-96-017, TER on Third 10-Yr Interval ISI Program Plan:Boston Edison Co,Pilgrim Nuclear Power Station
05000289/LER-2001-001-02, Re Emergency Feedwater Pump 2A Inoperable Greater than the Technical Specification Allowable Outage Time Due to an Incorrect Operability Determination
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
BSEP-87-0065, Annual Rept of Facility Changes,Tests & Experiments,1986
L-95-059, Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 2
SNRC-1554, Responds to NRC Bulletin 88-007,Suppl 1, Oscillations in Bwrs. Changes Initiated to Appropriate Station Procedures That Instruct Reactor Operators to Manually Scram Reactor Under All Operating Conditions as Specified
2CAN112004, License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP)
LR-N21-0005, Core Operating Limits Report, Reload 22, Cycle 23, Revision 20
05000325/LER-1980-038-03, /03L-0:on 800501,during Normal operation,1A Reactor Recirculation Pump Tripped on Motor Generator Set Low Oil Pressure.Caused by PCV-1739 Controlling Erratically During Radom Periods & Possible Setpoint Drift