Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212H0711999-09-21021 September 1999 Safety Evaluation Supporting Amend 123 to License NPF-57 ML20212C1251999-09-17017 September 1999 Safety Evaluation Supporting Amend 122 to License NPF-57 ML20212B7221999-09-14014 September 1999 Safety Evaluation Supporting Amends 224 & 205 to Licenses DPR-70 & DPR-75,respectively ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) 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 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 ML18107A3931999-06-23023 June 1999 Safety Evaluation Supporting Licensee Response to GL 95-07 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 ML20206Q4731999-05-14014 May 1999 SER Accepting Response to GL 97-05, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant 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 ML20206C8481999-04-22022 April 1999 SER Authorizing Pse&G Proposed Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B Pursuant to 10CFR50.55a(a)(3)(i) ML20205R8721999-04-19019 April 1999 Safety Evaluation Supporting Amend 120 to License NPF-57 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 ML20205P7701999-04-14014 April 1999 Safety Evaluation Supporting Amend 119 to License NPF-57 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 ML20205G6051999-03-19019 March 1999 SER Accepting Relief Request Re Acme Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components,Section Xi,Div 1 ML20205F8911999-03-18018 March 1999 Safety Evaluation Authorizing Licensee Requests for Second 10-year Interval for Pumps & Valves IST Program ML18106B0981999-03-12012 March 1999 Safety Evaluation Supporting Relief Requests to Licenses DPR-70 & DPR-82,respectively ML20205G3781999-03-0909 March 1999 Safety Evaluation Supporting Amend 117 to License NPF-57 ML20203F8861999-02-10010 February 1999 Safety Evaluation Supporting Amend 115 to License NPF-57 ML20203F7061999-02-0909 February 1999 Safety Evaluation Supporting Amend 114 to License NPF-57 ML20203C7791999-02-0404 February 1999 Safety Evaluation Supporting Amend 113 to License NPF-57 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 ML20154B6691998-10-0101 October 1998 Safety Evaluation Supporting Amend 112 to License NPF-57 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 ML20247L1661998-05-0808 May 1998 Safety Evaluation Supporting Amend 111 to License NPF-57 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 ML20203B5231998-01-29029 January 1998 Safety Evaluation Supporting Amend 206 to License DPR-70 ML20203A5681998-01-29029 January 1998 Safety Evaluation Supporting Amends 204 & 186 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 ML20198S8691998-01-0808 January 1998 Safety Evaluation Supporting Amends 203 & 185 to Licenses DPR-70 & DPR-75,respectively 1999-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000354/LER-1999-011, :on 990919,unplanned Inoperability of HPCI Sys Occurred Due to Failure of Trip Unit Associated with HPCI Turbine Exhaust Pressure Transmitter.Failed Trip Unit Was Replaced & Procedures Were Revised.With1999-10-19019 October 1999
- on 990919,unplanned Inoperability of HPCI Sys Occurred Due to Failure of Trip Unit Associated with HPCI Turbine Exhaust Pressure Transmitter.Failed Trip Unit Was Replaced & Procedures Were Revised.With
ML20217F1501999-10-12012 October 1999 Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With LR-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 05000354/LER-1999-010, :on 990831,automatic Isolation Signal Received. Caused by Steam Flashing That Resulted in Spurious Steam Line Pressure Signals.Isolation Signal Was re-set & warm-up of RCIC Steam Lines Was Completed.With1999-09-29029 September 1999
- on 990831,automatic Isolation Signal Received. Caused by Steam Flashing That Resulted in Spurious Steam Line Pressure Signals.Isolation Signal Was re-set & warm-up of RCIC Steam Lines Was Completed.With
ML20212H0711999-09-21021 September 1999 Safety Evaluation Supporting Amend 123 to License NPF-57 ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG 05000354/LER-1999-009, :on 990820,license Condition Violation Re Min FW Temp Limits Were Noted.Caused by Lightning Strike. Recovered & Restored Plant Sys Affected by Electrical Transient1999-09-20020 September 1999
- on 990820,license Condition Violation Re Min FW Temp Limits Were Noted.Caused by Lightning Strike. Recovered & Restored Plant Sys Affected by Electrical Transient
ML20212C1251999-09-17017 September 1999 Safety Evaluation Supporting Amend 122 to License NPF-57 05000354/LER-1999-008-01, :on 990817,CR Was Notified That Control Equipment Mezzanine (CEM) Floor Drain Discovered in Open Position.Caused by Failure to Include CEM Floor Drain Valve in Tagging Control Sys.Valve Was Closed.With1999-09-16016 September 1999
- on 990817,CR Was Notified That Control Equipment Mezzanine (CEM) Floor Drain Discovered in Open Position.Caused by Failure to Include CEM Floor Drain Valve in Tagging Control Sys.Valve Was Closed.With
ML20212B7221999-09-14014 September 1999 Safety Evaluation Supporting Amends 224 & 205 to Licenses DPR-70 & DPR-75,respectively ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 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 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 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
ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence 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 ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,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
ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: Ipeees, Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20210B7371999-07-21021 July 1999 Safety Evaluation Supporting Amends 223 & 204 to Licenses DPR-70 & DPR-75,respectively 05000354/LER-1999-007-01, :on 990614,license Condition Violation - Class 1E Battery Charging Operation Was Noted.Caused by Inadequate Procedure Development.Procedures Revised & Personnel Held Accountable for Inappropriate Actions1999-07-14014 July 1999
- on 990614,license Condition Violation - Class 1E Battery Charging Operation Was Noted.Caused by Inadequate Procedure Development.Procedures Revised & Personnel Held Accountable for Inappropriate Actions
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
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
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
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 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 ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.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) 05000354/LER-1999-006-01, :on 990518,unexpected Actuation of B Channel PCIS Occurred.Caused by Personnel Error.Addl Training Will Be Provided to Operations Personnel to Preclude Addl Unexpected ESF Actuations1999-06-15015 June 1999
- on 990518,unexpected Actuation of B Channel PCIS Occurred.Caused by Personnel Error.Addl Training Will Be Provided to Operations Personnel to Preclude Addl Unexpected ESF Actuations
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-N99-0275, 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 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 ML20196A1511999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Hope Creek Generating Station,Unit 1.With 1999-09-08
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