Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212B7221999-09-14014 September 1999 Safety Evaluation Supporting Amends 224 & 205 to Licenses DPR-70 & DPR-75,respectively 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 ML18107A3931999-06-23023 June 1999 Safety Evaluation Supporting Licensee Response to GL 95-07 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 ML18107A3751999-06-15015 June 1999 Safety Evaluation Accepting Licensee Request for Approval of Proposed Changes to Nuclear Business Unit EP for Hope Creek & Salem Generating Stations,Iaw 10CFR50.54(q) ML18107A3111999-05-21021 May 1999 SER Accepting GL-88-20,suppl 4, IPEEEs for Severe Accident Vulnerabilities, for Plant,Units 1 & 2 ML20206H2631999-05-0404 May 1999 Safety Evaluation Supporting Amend 222 to License DPR-70 ML20206B4761999-04-26026 April 1999 Safety Evaluation Supporting Amends 220 & 202 to Licenses DPR-70 & DPR-75,respectively ML18107A1791999-04-15015 April 1999 Safety Evaluation Supporting Changes to QA Program in That QA Program Continues to Meet Requirements of App B to 10CFR50 ML18107A1601999-04-0707 April 1999 Safety Evaluation Accepting Request for Exemption from Update Requirements of 10CFR50.71(e)(4) ML18106B1461999-04-0101 April 1999 SER Accepting Util Proposed Request to Use 1992 Edition of ASME Boiler & Pressure Vessel Code,Section Xi,Article, IWA-4500,for Potential Repair of Feedwater Nozzles for Salem Nuclear Generating Station,Unit 2 ML18106B0981999-03-12012 March 1999 Safety Evaluation Supporting Relief Requests to Licenses DPR-70 & DPR-82,respectively ML20199G0791999-01-0808 January 1999 Safety Evaluation Supporting Amend 197 to License DPR-75 ML20198J2951998-12-19019 December 1998 Safety Evaluation Supporting Amends 216 & 196 to Licenses DPR-70 & DPR-75,respectively ML20196J6011998-12-0202 December 1998 Safety Evaluation Supporting Amends 215 & 195 to Licenses DPR-70 & DPR-75,respectively ML18106A9361998-10-22022 October 1998 Safety Evaluation Supporting USI A-46 Program Implementation Re Licenses DPR-70 & DPR-75,respectively ML18106A8721998-09-15015 September 1998 Safety Evaluation Accepting Pse&G Request to Incorporate W WRB-2 Correlation Into Licensing Basis for Salem Nuclear Generating Station,Units 1 & 2 ML20151X2211998-09-0808 September 1998 Safety Evaluation Supporting Amends 214 & 194 to Licenses DPR-70 & DPR-75,respectively ML20237A3851998-08-0606 August 1998 Safety Evaluation Supporting Amends 213 & 193 to Licenses DPR-70 & DPR-75,respectively ML18106A7781998-07-23023 July 1998 SER Accepting QA Program Description Changes for Hope Creek & Salem Generating Stations ML20236Q4301998-07-14014 July 1998 Safety Evaluation Supporting Amends 212 & 192 to Licenses DPR-70 & DPR-75,respectively ML20236L6371998-07-0606 July 1998 Supplement to Safety Evaluation Accepting Proposed Statements Made by Pse&G to Correct 890501 Safety Evaluation Along W/Documents Re Amend 69 ML20248K8311998-06-0404 June 1998 Safety Evaluation Supporting Amend 211 to License DPR-70 ML20217D4291998-04-20020 April 1998 Safety Evaluation Supporting Amend 210 to License DPR-70 ML20217F4011998-03-24024 March 1998 Safety Evaluation Supporting Amends 209 & 191 to Licenses DPR-70 & DPR-75,respectively ML20217K8261998-03-19019 March 1998 Safety Evaluation Supporting Amend 190 to License DPR-75 ML20217A1661998-03-12012 March 1998 Safety Evaluation Supporting Amends 208 & 189 to Licenses DPR-70 & DPR-75,respectively ML20203L4021998-02-27027 February 1998 Safety Evaluation Supporting Amends 207 & 188 to Licenses DPR-70 & DPR-75,respectively ML20203B4951998-01-29029 January 1998 Safety Evaluation Supporting Amends 205 & 187 to Licenses DPR-70 & DPR-75,respectively ML20203A5681998-01-29029 January 1998 Safety Evaluation Supporting Amends 204 & 186 to Licenses DPR-70 & DPR-75,respectively ML20203B5231998-01-29029 January 1998 Safety Evaluation Supporting Amend 206 to License DPR-70 ML20198S8691998-01-0808 January 1998 Safety Evaluation Supporting Amends 203 & 185 to Licenses DPR-70 & DPR-75,respectively ML20198H3891997-12-22022 December 1997 Safety Evaluation Supporting Amend 202 to License DPR-70 ML20198J0361997-12-18018 December 1997 Safety Evaluation Supporting Proposed Merger of Atlantic Energy,Inc,& Dp&L Affecting Plants Units 1 & 2 ML20203C7221997-11-26026 November 1997 Safety Evaluation Supporting Amend 201 to License DPR-70 ML20217B2311997-09-11011 September 1997 Safety Evaluation Supporting Amends 200 & 184 to Licenses DPR-70 & DPR-75,respectively ML20216J5081997-09-10010 September 1997 Safety Evaluation Supporting Amend 183 to License DPR-75 ML18102B5001997-08-0707 August 1997 Safety Evaluation Approving Licensee Use of Proposed Alternative to ASME Code Requirement & Removal of Restriction from 950505 SE That Required Weld Repairs Be Performed Offsite on SA-351 ML18102B4961997-08-0404 August 1997 Safety Evaluation Accepting Proposed Changes to Rev 15 of Sgs QAP Submitted by Sgs on 970516 & 970606 ML20210H1721997-07-29029 July 1997 Safety Evaluation Supporting Amends 199 & 182 to Licenses DPR-70 & DPR-75,respectively ML20141H4091997-07-17017 July 1997 Safety Evaluation Supporting Amends 198 & 181 to Licenses DPR-70 & DRP-75,respectively ML20141D6541997-06-24024 June 1997 Safety Evaluation Supporting Amends 197 & 180 to Licenses DPR-70 & DPR-75,respectively ML20236X5681997-06-19019 June 1997 Safety Evaluation Supporting Amends 196 & 179 to Licenses DPR-70 & DPR-75,respectively ML20148K7381997-06-13013 June 1997 Safety Evaluation Supporting Amends 195 & 178 to Licenses DPR-70 & DPR-75,respectively ML20148K1071997-06-0404 June 1997 Safety Evaluation Supporting Amends 194 & 177 to Licenses DPR-70 & DPR-75,respectively ML20141K6101997-05-0808 May 1997 Safety Evaluation Supporting Amends 193 & 176 to Licenses DPR-70 & DPR-75,respectively ML20137E2451997-03-21021 March 1997 Safety Evaluation Supporting Amends 192 & 175 to Licenses DPR-70 & DPR-75,respectively ML18102A8801997-02-13013 February 1997 Safety Evaluation Accepting Proposed Rev to Plant Inservice Testing Program Containing Proposed Relief Requests V-24 & V-25 ML20134J9631997-02-0606 February 1997 Safety Evaluation Supporting Amends 191 & 174 to Licenses DPR-70 & DPR-75,respectively 1999-09-14
[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 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 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data 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 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 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 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
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
ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 10) Second Interval,Second Period,Second Outage (99RF) 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 ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept 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 ML18107A3931999-06-23023 June 1999 Safety Evaluation Supporting Licensee Response to GL 95-07 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 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
ML18107A3751999-06-15015 June 1999 Safety Evaluation Accepting Licensee Request for Approval of Proposed Changes to Nuclear Business Unit EP for Hope Creek & Salem Generating Stations,Iaw 10CFR50.54(q) 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 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 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 ML18107A3111999-05-21021 May 1999 SER Accepting GL-88-20,suppl 4, IPEEEs for Severe Accident Vulnerabilities, for Plant,Units 1 & 2 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
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
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
ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 LR-N99-0225, Monthly Operating Rept for Apr 1999 for Salem Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 LR-N99-0226, Monthly Operating Rept for Apr 1999 for Salem Unit 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With ML20206B4761999-04-26026 April 1999 Safety Evaluation Supporting Amends 220 & 202 to Licenses DPR-70 & DPR-75,respectively 05000311/LER-1999-001-03, :on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With1999-04-23023 April 1999
- on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With
ML18107A1791999-04-15015 April 1999 Safety Evaluation Supporting Changes to QA Program in That QA Program Continues to Meet Requirements of App B to 10CFR50 ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11 ML18107A1601999-04-0707 April 1999 Safety Evaluation Accepting Request for Exemption from Update Requirements of 10CFR50.71(e)(4) ML18106B1461999-04-0101 April 1999 SER Accepting Util Proposed Request to Use 1992 Edition of ASME Boiler & Pressure Vessel Code,Section Xi,Article, IWA-4500,for Potential Repair of Feedwater Nozzles for Salem Nuclear Generating Station,Unit 2 LR-N99-0176, Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With LR-N99-0177, Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 05000272/LER-1999-001-02, :on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with1999-03-29029 March 1999
- on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with
05000272/LER-1999-001-01, :on 990228,reactor Scram Resulted in Turbine Trip.Caused by Personnel Error.Revised Lesson Plans to Explicitly Demonstrate Manner in Which Valve Functions. with1999-03-29029 March 1999
- on 990228,reactor Scram Resulted in Turbine Trip.Caused by Personnel Error.Revised Lesson Plans to Explicitly Demonstrate Manner in Which Valve Functions. with
1999-09-30
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