Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18107A3151999-04-30030 April 1999
Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1
ML18106A6821998-06-24024 June 1998
Revised Charting Our Future.
ML18106A6681998-06-17017 June 1998
Charting the Future
ML18106A2571998-01-19019 January 1998
Nuclear Business Unit Future Objectives
ML18106A2131997-12-15015 December 1997
Safety Evaluation Supporting Rev to TS to Adopt Option B of 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing
ML18102B4651997-06-30030 June 1997
Evaluation of Macrohabitat Utilization by Loggerhead Sea Turtles in Delaware Estuary Using Sonic & Satellite Tracking Techniques
ML18102B3331997-02-28028 February 1997
Rev 0 to Cfcu Return Piping Inside CTMT,221F Temp Effect.
ML20133D2201996-12-0606 December 1996
Root Cause Analysis of Struthers-Dunn Operate-Reset Relay Latch Failures for Salem Generating Station
ML20133D2251996-10-30030 October 1996
Struthers-Dunn Model 255XCXP Relay Root Cause Evaluation for Salem Nuclear Generation Station
ML18102A3231996-07-0101 July 1996
Reg Guide 1.121 Assessment of Indications at Salem Unit 2
ML18102A1591996-06-0404 June 1996
Fuel Handling Accident Analysis Radiological Evaluation
ML20101M6601996-03-24024 March 1996
Supplemental Submittal in Response to NRC GL 87-02/USI A-46, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors
ML18102A1321996-03-15015 March 1996
Change 2EC-3332 to Rev 0 to Design Analysis, 125 Vdc Battery Charger Replacement
ML18102B0201996-02-28028 February 1996
Rev 0 to Evaluation of Structures for Increased Temps Due to Updated Main Steam Line Break.
ML18101B1951996-01-31031 January 1996
IPE for External Events
ML20129K1031995-07-10010 July 1995
Exam of Fasteners from Salem Nuclear Generating Station
ML18101A7481995-05-19019 May 1995
Safe Shutdown Equipment List Rept for Salem Generating Station Units 1 & 2
ML18101A7491995-04-25025 April 1995
Relay Evaluation Rept, Volumes 1 & 2, for Salem Generating Station Units 1 & 2
ML18101A7501995-04-20020 April 1995
Seismic Evaluation Rept, for Salem Generating Station
ML20134K1031995-03-24024 March 1995
Organizational Effectiveness Assessment Rept for Sngs,
ML18102B6541995-03-24024 March 1995
Organizational Effectiveness Assessment Rept for Plant, Redacted Version
ML18101A4391994-12-21021 December 1994
Fire Protection Review of Salem Reactor Coolant Pump Oil Collection Sys, Dtd 941221
ML20138H0381994-12-15015 December 1994
Engineering Assessment of Salem Bill of Matl (BOM) Validation of Pc 4 Class Codes Used on Q Boms, Final Rept
ML20134C5791994-10-23023 October 1994
Salem/Maint SC.MD-GP.SW-0001(Q) Svc Water Silt Survey, Rev 5
ML18106B0541994-01-31031 January 1994
Criticality Analysis of Salem Units 1 & 2 Fresh Fuels Racks.
ML18100A7971993-12-23023 December 1993
Simulator Four-Year Certification Rept
ML20069M2221993-10-15015 October 1993
Flux Thimble Thermocouple Ultrasonic Profilometry & Eddy Current Encircling Coil Insp of Stored Thimble Tubes Jul-Aug 1993
ML18100A6281993-09-16016 September 1993
Updated Page A4-4 of Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis, Changing Figure Numbers A5-1 & A5-2 to A4-1 & A4-2 at End of First Paragraph
ML18100A6801993-08-20020 August 1993
Engineering Evaluation of Sgs 1 & 2 Control Room Evacuation for Fire Induced MOV Hot Shorts as Discussed in NRC Info Notice 92-018
ML20045B8801993-05-21021 May 1993
Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis for Salem Nuclear Generating Station, Units 1 & 2
ML18100A3401993-04-28028 April 1993
Licensing Rept for Spent Fuel Storage Capacity Expansion Pse&G,Salem Generation Station,Units 1 & 2
ML18096B3561993-02-11011 February 1993
Cycle 8 Peaking Factor Limit Rept
ML20135A8141992-12-29029 December 1992
Control Room Overhead Annunciator Lock-Up of 921213
ML18096B1661992-11-13013 November 1992
Rev 1 to Fracture Toughness Analysis for Salem Units 1 & 2 Reactor Pressure Vessels to Protect Against Pressurized Thermal Shock Events,10CFR50.61
ML20106E1231992-10-31031 October 1992
IPE Level II Analysis Preliminary Summary
ML20138G9901992-10-0606 October 1992
Controls Equipment - Troubleshooting
ML18096B0081992-09-0202 September 1992
Analytical Data Rept, for Project 28173
ML18096A8061992-06-17017 June 1992
Rev 0 to Salem Unit 2 Response to Generic Ltr 92-01,Rev 1, Reactor Vessel Structural Integrity
ML18096A8051992-06-17017 June 1992
Rev 0 to Salem Unit 1 Response to Generic Ltr 92-01,Rev 1, Reactor Vessel Structural Integrity
ML18096A5831992-03-31031 March 1992
Rev 1 to Estimated Frequency of Loss of Off-Site Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations
ML18095A5151990-07-31031 July 1990
Vol 1 to Spring 1990 NDE of Selected Class 1 & Class 2 Components of Salem Generating Station,Unit 2
ML18095A3691990-07-26026 July 1990
Unit 1 Decommissioning Rept
ML18095A3681990-07-26026 July 1990
Unit 2 Decommissioning Rept
ML18095A3791990-07-20020 July 1990
Decommissioning Rept of Philadelphia Electric Co
ML18094B2241989-12-28028 December 1989
Simulator NRC Certification, Vols I-III
ML18094A3551989-04-30030 April 1989
Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles
ML20086U2571989-03-31031 March 1989
Estimated Frequency of Loss of Offsite Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations
ML18093B2021988-09-30030 September 1988
Special Rept on Spare CRD Mechanism Weld Refurbishments.
1999-09-30
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Category:INDIVIDUAL PLANT EXAM (OF EXTERNAL EVENTS)
MONTHYEARML18101B1951996-01-31031 January 1996
IPE for External Events
ML20106E1231992-10-31031 October 1992
IPE Level II Analysis Preliminary Summary
ML18095A6621990-12-28028 December 1990
Forwards Rept Summarizing Updates to Plant Level 1 PRA Analysis.Rept Documents Completion of Second Generic Ltr 88-20 Milestone
1996-01-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARLR-N99-0448, Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With1999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML18107A5581999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr
ML18107A5571999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr
LR-N99-0449, Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With1999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With
ML20212B7221999-09-14014 September 1999
Safety Evaluation Supporting Amends 224 & 205 to Licenses DPR-70 & DPR-75,respectively
LR-N99-0415, Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 9909131999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913
ML18107A5311999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913
LR-N99-0416, Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With1999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With
05000272/LER-1999-006-02, :on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With1999-08-26026 August 1999
- on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With
ML18107A5201999-08-12012 August 1999
Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 9) Second Interval,Second Period, First Outage (96RF)
LR-N99-0380, Monthly Operating Rept for July 1999 for Salem,Unit 2.With1999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 2.With
ML18107A4821999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr
ML18107A4811999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr
LR-N99-0379, Monthly Operating Rept for July 1999 for Salem,Unit 1.With1999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 1.With
05000311/LER-1999-008, :on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With1999-07-28028 July 1999
- on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With
ML20210B7371999-07-21021 July 1999
Safety Evaluation Supporting Amends 223 & 204 to Licenses DPR-70 & DPR-75,respectively
ML18107A4411999-07-0909 July 1999
SER Denying Licensee 980730 & 990222 Requests to Revise TS 3/4.7.6, Control Room Emergency Air Conditioning Sys, & Associated Bases to Change Acceptable Criteria for Control Room Emergency Air Conditioning System
ML18107A4441999-07-0606 July 1999
LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr
05000311/LER-1999-007, :on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With1999-07-0606 July 1999
- on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With
05000272/LER-1999-005-02, :on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With1999-07-0202 July 1999
- on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With
05000311/LER-1999-006, :on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With1999-07-0101 July 1999
- on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With
ML18107A5211999-07-0101 July 1999
Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 10) Second Interval,Second Period,Second Outage (99RF)
05000311/LER-1999-002, :on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With1999-07-0101 July 1999
- on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With
ML18107A4321999-07-0101 July 1999
LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr
ML18107A4331999-07-0101 July 1999
LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr
LR-N99-0325, Monthly Operating Rept for June 1999 for Salem,Unit 2.With1999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 2.With
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
LR-N99-0324, Monthly Operating Rept for June 1999 for Salem,Unit 1.With1999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 1.With
ML18107A4351999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr
ML18107A4341999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr
ML18107A4161999-06-23023 June 1999
Safety Evaluation Accepting Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML18107A3951999-06-17017 June 1999
LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr
05000272/LER-1999-004-02, :on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With1999-06-17017 June 1999
- on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With
05000272/LER-1999-003-02, :on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With1999-06-0909 June 1999
- on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With
05000311/LER-1999-005-01, :on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With1999-06-0202 June 1999
- on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With
ML18107A3441999-06-0101 June 1999
Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716
ML18107A3541999-06-0101 June 1999
LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr
LR-N99-0275, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With1999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With
ML18107A3721999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr
LR-N99-0278, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With1999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With
05000272/LER-1999-002-02, :on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With1999-05-12012 May 1999
- on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With
ML18107A2931999-05-12012 May 1999
LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr
05000311/LER-1999-004-01, :on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With1999-05-10010 May 1999
- on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With
ML18107A2791999-05-0404 May 1999
LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr
05000311/LER-1999-003-01, :on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With1999-05-0404 May 1999
- on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With
ML20206H2631999-05-0404 May 1999
Safety Evaluation Supporting Amend 222 to License DPR-70
05000311/LER-1999-002-01, :on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With1999-05-0303 May 1999
- on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With
ML18107A3711999-04-30030 April 1999
Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1
ML18107A3151999-04-30030 April 1999
Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1
1999-09-30
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