Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML18152B3831999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section XI Requirements for Containment Insp ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206C0151999-04-22022 April 1999 Safety Evaluation Supporting Amends 219 & 200 to Licenses NPF-4 & NPF-7,respectively ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20207H4451999-03-0202 March 1999 Safety Evaluation Supporting Amends 218 & 199 to Licenses NPF-4 & NPF-7,respectively ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20155H0351998-10-30030 October 1998 Safety Evaluation Supporting Amends 215 & 196 to Licenses NPF-4 & NPF-7,respectively ML20237E1871998-08-26026 August 1998 Safety Evaluation Supporting Amends 214 & 195 to Licenses NPF-4 & NPF-7,respectively ML20236X3811998-08-0303 August 1998 Safety Evaluation Supporting Amends 213 & 194 to Licenses NPF-4 & NPF-7,respectively ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20249C1521998-06-23023 June 1998 Safety Evaluation Supporting Amends 212 & 193 to Licenses NPF-4 & NPF-7,respectively ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20217E7001998-04-22022 April 1998 Safety Evaluation Supporting Amends 211 & 192 to Licenses NPF-4 & NPF-7,respectively ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20216G8741998-04-16016 April 1998 Safety Evaluation Supporting Amends 210 & 191 to Licenses NPF-4 & NPF-7,respectively ML20216F1251998-04-14014 April 1998 Safety Evaluation Supporting Amends 209 & 190 to Licenses NPF-4 & NPF-7,respectively ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198H5541997-12-29029 December 1997 SER Accepting Request for Approval of ASME Case N-498,rev 1, as an Alternative to Required Hydrostatic Pressure Test for Plant,Unit 2 ML20197K1541997-12-18018 December 1997 SER Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping for North Anna Power Station,Per Util 970919 Submittal ML20203C4191997-12-0404 December 1997 Safety Evaluation Supporting Amends 207 & 188 to Licenses NPF-4 & NPF-7,respectively ML20202B8751997-11-24024 November 1997 Safety Evaluation Denying Licensee Request for Exemption from Section III.G.2.f of App R to 10CFR50.Staff Concluded That Use of Combustible Radiant Energy Heat Shields Inside Containment at Surry & North Anna Unacceptable ML20199L0501997-11-24024 November 1997 SER Accepting Inservice Insp Program Relief Request NDE-32 ML20199E4971997-11-14014 November 1997 Safety Evaluation Authorizing Proposed Alternative of Licensee Relief Requests NDE-35 & NDE-37,for Plant,Units 1 & 2 During Second 10 Yr Interval ML20217E2411997-09-24024 September 1997 SER Accepting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping,Virginia Electric & Power Co,North Anna Power Station,Unit 1 ML20217E1871997-09-24024 September 1997 SER Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping,Virginia Electric & Power Co,North Anna Power Station,Units 1 & 2 ML20217E0701997-09-24024 September 1997 Safety Evaluation Granting Licensee ASME Section XI Relief Request NDE-33 at Plant,Unit 1 ML20149L2001997-07-29029 July 1997 SER Granting Requests for Relief NDE-33,34 & 35 Re ISI Program,Per 10CFR50.55a(g)(6)(i) ML20149F1321997-07-17017 July 1997 Safety Evaluation Supporting Amends 205 & 186 to Licenses NPF-4 & NPF-7,respectively ML20148H1971997-06-0404 June 1997 Safety Evaluation Granting Licensee Relief Request NDE-31 Related to Inservice Insp Program ML20140H8961997-05-0909 May 1997 Safety Evaluation Supporting Amends 204 & 185 to Licenses NPF-4 & NPF-7,respectively ML20140F4811997-04-30030 April 1997 Safety Evaluation Accepting Licensee 951207 Proposed Alternative in Request for Relief SPT-16 Re Second 10-yr Interval Inservice Insp Program for Unit 2 ML20133Q0661997-01-17017 January 1997 Safety Evaluation Supporting Amends 203 & 184 to Licenses NPF-4 & NPF-7,respectively ML20133G1561997-01-10010 January 1997 Safety Evaluation Accepting Second 10-year Relief Requests for Relief Numbers NDE-27,NDE-28 & NDE-29 ML20133G1911997-01-10010 January 1997 Safety Evaluation Accepting Second 10-year Interval Inservice Insp Plan Relief Request NDE-30 ML20138G1931996-10-16016 October 1996 SER Accepting Second 10-year Interval Inservice Insp Plan Request for Relief SPT-14,rev 1 Virginia Electric & Power Co North Anna Power Station,Unit 2 ML20128P1701996-10-10010 October 1996 Safety Evaluation Supporting Second 10-year Interval Inservice Insp Program Plan Requests for Relief NDE-23 Through NDE-30 for Plant Unit 2 ML20128F5981996-10-0101 October 1996 Safety Evaluation Authorizing Licensee Proposed Alternative to Examine Terminal End Welds on Lower Regenerative Heat Exchanger sub-vessels,per 10CFR50.55a(a)(3)(ii) ML20116B2361996-07-24024 July 1996 Safety Evaluation Supporting Amends 202 & 183 to Licenses NPF-4 & NPF-7,respectively ML20117K4221996-06-0505 June 1996 Safety Evaluation Supporting Amends 201 & 182 to Licenses NPF-4 & NPF-7,respectively ML20101L6861996-04-0101 April 1996 Safety Evaluation Supporting Amends 200 & 181 to Licenses NPF-4 & NPF-7,respectively ML20100L0031996-02-27027 February 1996 Safety Evaluation Supporting Amends 198 & 179 to Licenses NPF-4 & NPF-7,respectively ML20097D2491996-02-0808 February 1996 Safety Evaluation Supporting Amends 195 & 176 to Licenses NPF-4 & NPF-7,respectively 1999-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000339/LER-1999-002-03, :on 990922,containment Liner Through Wall Defect Was Noted.Caused by Corrosion.Pressure Test Was Performed.With1999-10-21021 October 1999
- on 990922,containment Liner Through Wall Defect Was Noted.Caused by Corrosion.Pressure Test Was Performed.With
ML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su 05000339/LER-1999-001-03, :on 990915,failure to Lock Open Loop SV Breakers as Intended by TSs Was Noted.Caused by Failure to Update Operating Procedures.Procedure ARs Were Initiated & Approved for Maint Procedure 1/2-MOP-5.92.With1999-10-12012 October 1999
- on 990915,failure to Lock Open Loop SV Breakers as Intended by TSs Was Noted.Caused by Failure to Update Operating Procedures.Procedure ARs Were Initiated & Approved for Maint Procedure 1/2-MOP-5.92.With
ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With 05000338/LER-1999-006-01, :on 990904,potential for Safegurads Exhaust Flow to Bypass Charcoal Filter,Was Discovered.Caused by Degraded Damper.Plant Issue Rept Submitted for B Train of Savs Flow Rate.With1999-09-28028 September 1999
- on 990904,potential for Safegurads Exhaust Flow to Bypass Charcoal Filter,Was Discovered.Caused by Degraded Damper.Plant Issue Rept Submitted for B Train of Savs Flow Rate.With
05000338/LER-1999-002, :on 990213,unsecured Isolation Valve,Was Discovered.Caused by Valve Configuration.Unsecured Bit Manual Bypass Isolation Valve Was Verified Closed & Chain & Lock Secured Valve Tee Handle.With1999-09-17017 September 1999
- on 990213,unsecured Isolation Valve,Was Discovered.Caused by Valve Configuration.Unsecured Bit Manual Bypass Isolation Valve Was Verified Closed & Chain & Lock Secured Valve Tee Handle.With
ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML18152B3831999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section XI Requirements for Containment Insp ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with 05000338/LER-1999-004, :on 990413,position Switch for Suction Supply Dampers to CR Emergency Fan Was Discovered Out of Position. Cause Could Not Be Determined.Station Entered Action Statement for TS 3.7.7.1.With1999-05-11011 May 1999
- on 990413,position Switch for Suction Supply Dampers to CR Emergency Fan Was Discovered Out of Position. Cause Could Not Be Determined.Station Entered Action Statement for TS 3.7.7.1.With
ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With 05000338/LER-1999-003, :on 990331,potential Loss of HHSI Pumps, Occurred Due to Postulated Main CR Fire.Caused by Incomplete Understanding of Time Sensitivity of Actions Required to Avoid Potential Loss.Procedure Revised.With1999-04-27027 April 1999
- on 990331,potential Loss of HHSI Pumps, Occurred Due to Postulated Main CR Fire.Caused by Incomplete Understanding of Time Sensitivity of Actions Required to Avoid Potential Loss.Procedure Revised.With
ML20206C0151999-04-22022 April 1999 Safety Evaluation Supporting Amends 219 & 200 to Licenses NPF-4 & NPF-7,respectively ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With 05000338/LER-1999-002, :on 990213,isolation Valve Was Unsecured. Caused by Valve Configuration.Unsecured Valve Verified to Be Closed & Chain & Lock Placed in Manner That Would Secure Valve Tee Handle.With1999-03-11011 March 1999
- on 990213,isolation Valve Was Unsecured. Caused by Valve Configuration.Unsecured Valve Verified to Be Closed & Chain & Lock Placed in Manner That Would Secure Valve Tee Handle.With
ML20207H4451999-03-0202 March 1999 Safety Evaluation Supporting Amends 218 & 199 to Licenses NPF-4 & NPF-7,respectively ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year 05000338/LER-1999-001-01, :on 990106,RCS Leak Rate Missed Surveillance Was Noted.Caused by Computer Malfunction.Computer Malfunction Affecting VCT & Pzr Level Inputs Was Corrected. with1999-01-22022 January 1999
- on 990106,RCS Leak Rate Missed Surveillance Was Noted.Caused by Computer Malfunction.Computer Malfunction Affecting VCT & Pzr Level Inputs Was Corrected. with
ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With 05000338/LER-1998-007-01, :on 981015,3B Casing Cooling Pump Failed to Develop Discharge Pressure & Recirculation.Caused by Air Binding.Subject Pump Was Vented of Air,Started & Tested Satisfactorily.With1998-11-12012 November 1998
- on 981015,3B Casing Cooling Pump Failed to Develop Discharge Pressure & Recirculation.Caused by Air Binding.Subject Pump Was Vented of Air,Started & Tested Satisfactorily.With
ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20155H0351998-10-30030 October 1998 Safety Evaluation Supporting Amends 215 & 196 to Licenses NPF-4 & NPF-7,respectively ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns 05000338/LER-1998-005-01, :on 980921,safety Valve Setpoints Were Noted Out of Tolerance.Caused by Setpoint Variance.Valves Were Disassembled,Inspected,Repaired as necessary,re-assembled & Tested Satisfactory.With1998-10-0707 October 1998
- on 980921,safety Valve Setpoints Were Noted Out of Tolerance.Caused by Setpoint Variance.Valves Were Disassembled,Inspected,Repaired as necessary,re-assembled & Tested Satisfactory.With
05000338/LER-1998-006-01, :on 980922,ESFA Occurred.Caused by Human Error. Safety Injection Signal Was Reset & Equipment Was Restored to Normal1998-10-0707 October 1998
- on 980922,ESFA Occurred.Caused by Human Error. Safety Injection Signal Was Reset & Equipment Was Restored to Normal
05000339/LER-1998-004-02, :on 980917,reactor Trip Was Noted.Caused by Lightning Strike.Operations Emergency Procedure 2-E-0, RT or SI Was Entered1998-10-0606 October 1998
- on 980917,reactor Trip Was Noted.Caused by Lightning Strike.Operations Emergency Procedure 2-E-0, RT or SI Was Entered
05000339/LER-1998-003-01, :on 980424,multiple Failures Occurred During Functional Testing of RCS Large Bore Snubbers.Cause Unknown. Large Bore Snubbers Replaced.With1998-10-0505 October 1998
- on 980424,multiple Failures Occurred During Functional Testing of RCS Large Bore Snubbers.Cause Unknown. Large Bore Snubbers Replaced.With
ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With 05000338/LER-1998-004-01, :on 980902,motor Operated Valve Surveillance Was Missed.Caused by Personnel Error.Station Entered 24 H Action of TS 4.0.3 & Station Deviation Rept Was Initiated to Document Condition.With1998-09-22022 September 1998
- on 980902,motor Operated Valve Surveillance Was Missed.Caused by Personnel Error.Station Entered 24 H Action of TS 4.0.3 & Station Deviation Rept Was Initiated to Document Condition.With
05000338/LER-1998-003, :on 980804,service Water Supports Surveillance Was Missed.Caused by Personnel Error.Component Supports Were Examined & Found to Be Acceptable.With1998-09-17017 September 1998
- on 980804,service Water Supports Surveillance Was Missed.Caused by Personnel Error.Component Supports Were Examined & Found to Be Acceptable.With
ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section 1999-09-08
[Table view] |