Letter Sequence Approval |
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Results
Other: 05000346/LER-1980-090, Forwards LER 80-090/03L-0, 05000346/LER-1980-090-03, /03L-0:on 801205,during Surveillance Testing, Setpoint for Borated Water Storage Tank Low Level Bistables BA312 & BA309 Found Out of Tolerance.Caused by Component Failure.Bistables Recalibr, 05000346/LER-1983-019-03, /03L-0:on 830421,steam & Feedwater Rupture Control Sys Channel 3 Tripped.Caused by Failed +15-volt Dc Power Supply.On 830427,Channel 3 Tripped.Power Supply Returned to Vendor.Failed Supplies Replaced, 05000346/LER-1986-008, :on 860108,while in Mode 5,full Safety Features Actuation Sys (Sfas) Actuation Experienced.Caused by Lack of Adherence to Procedures by Personnel.Incident Reviewed W/Personnel, ML19340E991, ML19341B813, ML20002C776, ML20010J123, ML20069E493, ML20141N821, ML20265E231, ML20265E237, ML20265E241, ML20265E246, ML20265E251
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MONTHYEARML20002C7761980-12-24024 December 1980 Informs That Engineered Safety Features Actuation Sys Does Not Conform to IEEE Std 279.1971 & Constitutes Potential Failure Mode.Recommends Short Term Corrective Actions Project stage: Other 05000346/LER-1980-090, Forwards LER 80-090/03L-01981-01-0202 January 1981 Forwards LER 80-090/03L-0 Project stage: Other 05000346/LER-1980-090-03, /03L-0:on 801205,during Surveillance Testing, Setpoint for Borated Water Storage Tank Low Level Bistables BA312 & BA309 Found Out of Tolerance.Caused by Component Failure.Bistables Recalibr1981-01-0202 January 1981 /03L-0:on 801205,during Surveillance Testing, Setpoint for Borated Water Storage Tank Low Level Bistables BA312 & BA309 Found Out of Tolerance.Caused by Component Failure.Bistables Recalibr Project stage: Other ML19340E9911981-01-0909 January 1981 Forwards marked-up Electrical Drawings as Update to 810105 Request to Deautomate Incident Level 5 of Safety Features Actuation Sys.Procedure Mod Details,License Amend Request & Safety Evaluation Will Follow.W/O Encl Project stage: Other ML20002D1341981-01-15015 January 1981 Proposed Tech Specs Sections 3 & 4,to Permit Deautomation of Valve Shifts Caused by Incident Level 5 of Safety Features Actuation Sys.Draft Emergency & Sys Operating Procedures & Functional Description Encl Project stage: Draft Other ML20002D1291981-01-15015 January 1981 Application to Amend License NPF-3,changing Tech Specs to Permit Deautomation of Valve Shifts Caused by Incident Level 5 of Safety Features Actuation Sys Project stage: Request ML19341B8131981-02-24024 February 1981 Revised Tech Spec Section 4.5.2.d.2 & Tables 3.3-3,3.3-5 & 4.3-2 Changing Surveillance Requirements Per Amend 36 to License NPF-3 Project stage: Other ML19341B8051981-02-24024 February 1981 Forwards Application to Amend License NPF-3 Changing Tech Specs to Provide Consistency in Terminology W/Plant Design & to Ensure Adequate Surveillance Requirements Project stage: Request ML19341B8111981-02-24024 February 1981 Application for Amend to License NPF-3 Changing Tech Spec Section 4.5.2.d.2 & Tables 3.3-3,3.3-5 & 4-3.2 Project stage: Request ML20010J1231981-09-15015 September 1981 Forwards Response to NRC Re 801205 Inadvertent Safety Features Actuation Sys Actuation Project stage: Other ML20069E4931983-03-11011 March 1983 Forwards Response to Re Safety Features Actuation Sys Shared Power Supply Returns.Permanent Grounding of Power Supply Commons to Instrument Ground Will Be Provided to Resolve Channel Independence Issue Project stage: Other 05000346/LER-1983-019-03, /03L-0:on 830421,steam & Feedwater Rupture Control Sys Channel 3 Tripped.Caused by Failed +15-volt Dc Power Supply.On 830427,Channel 3 Tripped.Power Supply Returned to Vendor.Failed Supplies Replaced1983-05-20020 May 1983 /03L-0:on 830421,steam & Feedwater Rupture Control Sys Channel 3 Tripped.Caused by Failed +15-volt Dc Power Supply.On 830427,Channel 3 Tripped.Power Supply Returned to Vendor.Failed Supplies Replaced Project stage: Other ML20265E2311985-11-0101 November 1985 Schematic Diagram:Davis Besse Safety Features Actuation System. Sheet 2 of 5.Drawing Consists of Four Aperture Cards Project stage: Other ML20265E2371985-11-0101 November 1985 Schematic Diagram:Davis Besse Safety Features Actuation System. Sheet 1 of 5.Drawing Consists of Three Aperture Cards Project stage: Other ML20265E2411985-11-0101 November 1985 Schematic Diagram:Davis Besse Safety Features Actuation System. Sheet 3 of 5.Drawing Consists of Four Aperture Cards Project stage: Other ML20265E2461985-11-0101 November 1985 Schematic Diagram:Davis Besse Safety Features Actuation System. Sheet 4 of 5.Drawing Consists of Three Aperture Cards Project stage: Other ML20265E2511985-11-0101 November 1985 Schematic Diagram:Davis-Besse Safety Features Actuation System. Sheet 5 of 5.Drawing Consists of Five Aperture Cards Project stage: Other ML20138Q5501985-12-17017 December 1985 Summary of 851126 Meeting W/Util,Beta & Consolidated Controls Corp in Bethesda,Md Re Proposed Changes to Safety Features Actuation Sys.Viewgraphs & List of Attendees Encl Project stage: Meeting 05000346/LER-1986-008, :on 860108,while in Mode 5,full Safety Features Actuation Sys (Sfas) Actuation Experienced.Caused by Lack of Adherence to Procedures by Personnel.Incident Reviewed W/Personnel1986-02-0606 February 1986
- on 860108,while in Mode 5,full Safety Features Actuation Sys (Sfas) Actuation Experienced.Caused by Lack of Adherence to Procedures by Personnel.Incident Reviewed W/Personnel
Project stage: Other ML20141N8211986-03-11011 March 1986 Confirms 860307 Submittal of Drawings 7749-E-30-5-6, Analog Module Assembly & 7749-E-30-19-7, Bistable 2 & Forwards Addl Copies,Per NRC Response to Re Safety Features Actuation Sys Project stage: Other ML20203N7921986-04-17017 April 1986 Forwards Safety Evaluation Accepting Proposed Mods to Safety Features Actuation Sys as Result of 801205 Actuation, Pending Successful Completion of post-mod Tests Project stage: Approval ML20203N9141986-04-17017 April 1986 Safety Evaluation Accepting Proposed Mods to Safety Actuation Sys Re Shared Power Supply Returns as Result of 801205 Actuation Project stage: Approval 1983-03-11
[Table View] |
Safety Evaluation Accepting Proposed Mods to Safety Actuation Sys Re Shared Power Supply Returns as Result of 801205 ActuationML20203N914 |
Person / Time |
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Site: |
Davis Besse |
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Issue date: |
04/17/1986 |
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From: |
NRC |
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To: |
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Shared Package |
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ML20203N793 |
List: |
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References |
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TAC-43253, NUDOCS 8605060209 |
Download: ML20203N914 (10) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20212H9961999-06-22022 June 1999 Safety Evaluation Supporting Amend 233 to License NPF-3 ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20207G6661999-06-0808 June 1999 Safety Evaluation Supporting Amend 232 to License NPF-3 ML20206U7371999-05-19019 May 1999 Safety Evaluation Supporting Amend 231 to License NPF-3 ML20206U2441999-02-0909 February 1999 Safety Evaluation Supporting Amend 229 to License NPF-3 ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20198K7671998-12-21021 December 1998 Safety Evaluation Supporting Amend 228 to License NPF-3 ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 ML20236M9411998-07-0707 July 1998 Safety Evaluation Supporting Amend 225 to License NPF-3 ML20236K4321998-06-30030 June 1998 Safety Evaluation Supporting Amend 224 to License NPF-03 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 ML20249A7551998-06-11011 June 1998 Safety Evaluation Supporting Amend 223 to License NPF-3 ML20249A7661998-06-11011 June 1998 Safety Evaluation Supporting Amend 222 to License NPF-3 ML20216B9401998-04-15015 April 1998 Safety Evaluation Supporting Amend 221 to License NPF-3 ML20216B8381998-04-14014 April 1998 Safety Evaluation Supporting Amend 220 to License NPF-3 ML20202C6131998-02-0303 February 1998 Safety Evaluation Supporting Amend 219 to License NPF-3 ML20199J9511998-01-30030 January 1998 SER Related to Exemption from Section Iii.O of App R,To 10CFR50,for Davis-Besse Nuclear Power Station,Unit 1 ML20198R4771998-01-13013 January 1998 SER Approving Second 10-year Interval Inservice Inspection Program Plan Requests for Relief for Davis-Besse Nuclear Power Station,Unit 1 ML20203B2141997-12-0202 December 1997 Safety Evaluation Supporting Amend 218 to License NPF-3 ML20203C1401997-12-0202 December 1997 Safety Evaluation Supporting Amend 217 to License NPF-3 ML20203C2701997-12-0202 December 1997 Safety Evaluation Supporting Amend 216 to License NPF-3 ML20137G5721997-03-24024 March 1997 Safety Evaluation Supporting Amend 215 to License NPF-3 ML20138L0491997-02-11011 February 1997 Safety Evaluation Supporting Amend 214 to License NPF-3 ML20138L0661997-02-10010 February 1997 Safety Evaluation Supporting Amend 213 to License NPF-3 ML20134J7781996-11-0808 November 1996 Safety Evaluation Supporting Amend 212 to License NPF-3 ML20128L3001996-10-0202 October 1996 SER Supporting Dbnp IPE Process of Identifying Most Likely Severe Accidents & Severe Accident Vulnerabilities ML20107K3131996-04-23023 April 1996 Safety Evaluation Supporting Amend 211 to License NPF-7 ML20107J6371996-04-19019 April 1996 Safety Evaluation Supporting Amend 201 to License NPF-3 ML20101Q5951996-03-29029 March 1996 Safety Evaluation Supporting Amend 209 to License NPF-3 ML20100L0561996-02-27027 February 1996 Safety Evaluation Supporting Amend 207 to License NPF-3 ML20095E3571995-12-0808 December 1995 Safety Evaluation Supporting Amend 204 to License NPF-3 ML20095E3271995-12-0808 December 1995 Safety Evaluation Supporting Amend 203 to License NPF-3 ML20094M4031995-11-17017 November 1995 Safety Evaluation Supporting Amend 202 to License NPF-3 ML20094L4821995-11-14014 November 1995 Safety Evaluation Supporting Amend 201 to License NPF-3 ML20092A1721995-09-0505 September 1995 Safety Evaluation Supporting Amend 200 to License NPF-3 ML20086M1321995-07-20020 July 1995 Safety Evaluation Supporting Amend 199 to License NPF-3 ML20083K5641995-05-0303 May 1995 Safety Evaluation Supporting Amend 198 to License NPF-3 ML20081J2341995-03-22022 March 1995 Safety Evaluation Supporting Amend 197 to License NPF-3 ML20081H1031995-03-21021 March 1995 Safety Evaluation Supporting Amend 196 to License NPF-3 ML20080L9501995-02-27027 February 1995 Safety Evaluation Supporting Amend 195 to License NPF-3 ML20078C1531995-01-17017 January 1995 Safety Evaluation Supporting Amend 194 to License NPF-3 ML20076J3031994-10-18018 October 1994 Safety Evaluation Supporting Amend 193 to License NPF-3 ML20076G9421994-10-0707 October 1994 SER Supporting Amend 192 to License NPF-3 ML20071N4211994-07-27027 July 1994 Safety Evaluation Supporting Amend 190 to License NPF-3 ML20070K9001994-07-22022 July 1994 Safety Evaluation Supporting Amend 189 to License NPF-3 ML20070C7971994-06-28028 June 1994 Safety Evaluation Supporting Amend 188 to License NPF-3 Unit 1 ML20065C7791994-03-28028 March 1994 Safety Evaluation Supporting Amend 185 to License NPF-3 1999-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & PNPP QA Program ML20217D5441999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With 05000346/LER-1998-011, :on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle1999-09-0303 September 1999
- on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle
ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1999-003, :on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With1999-08-26026 August 1999
- on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With
ML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20210Q8541999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20209E6231999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-013, :on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With1999-06-24024 June 1999
- on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With
ML20212H9961999-06-22022 June 1999 Safety Evaluation Supporting Amend 233 to License NPF-3 ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20207G6661999-06-0808 June 1999 Safety Evaluation Supporting Amend 232 to License NPF-3 ML20195F4871999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20206U7371999-05-19019 May 1999 Safety Evaluation Supporting Amend 231 to License NPF-3 ML20207F4351999-05-0404 May 1999 Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504 ML20206M6341999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Davis-Besse Nuclear Station,Unit 1.With ML20205M2931999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Davis-Besse Nuclear Power Station.With 05000346/LER-1999-002, :on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With1999-03-0505 March 1999
- on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With
ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206U2441999-02-0909 February 1999 Safety Evaluation Supporting Amend 229 to License NPF-3 ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20198K7671998-12-21021 December 1998 Safety Evaluation Supporting Amend 228 to License NPF-3 ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-012, :on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With1998-11-17017 November 1998
- on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With
05000346/LER-1998-011, :on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With1998-11-13013 November 1998
- on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With
05000346/LER-1998-009, :on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With1998-11-13013 November 1998
- on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With
ML20195D0001998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process 05000346/LER-1998-010, :on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with1998-10-26026 October 1998
- on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with
05000346/LER-1998-008, :on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With1998-10-0101 October 1998
- on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With
ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-007, :on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With1998-09-22022 September 1998
- on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With
ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With 05000346/LER-1998-006, :on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources1998-08-21021 August 1998
- on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources
ML20237E3171998-08-21021 August 1998 ISI Summary Rept of Eleventh Refueling Outage Activities for Davis-Besse Nuclear Power Station ML20237B1681998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236U5011998-07-23023 July 1998 Special Rept:On 980624,Unit 1 Site Damaged by Tornado & High Winds.Alert Declared by DBNPS Staff,Dbnps Emergency Response Facilities Activiated & Special Insp Team Deployed to Site by Nrc,As Result of Event ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 05000346/LER-1998-004, :on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired1998-07-13013 July 1998
- on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired
05000346/LER-1998-005, :on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations1998-07-11011 July 1998
- on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations
ML20236M9411998-07-0707 July 1998 Safety Evaluation Supporting Amend 225 to License NPF-3 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K4321998-06-30030 June 1998 Safety Evaluation Supporting Amend 224 to License NPF-03 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 1999-09-30
[Table view] |
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SAFETY EVALUATION - DAVIS-BESSE ELECTRICAL INDEPENDENCE BETWEEN REDUNDANT SAFETY FEATURES ACTUATION SYSTEM INSTRUMENT AND LOGIC CHANNELS INTRODUCTION AND BACKGROUND Following an inadvertent safety features actuation system (SFAS) actuation at Davis-Besse on December 5, 1980, it was discovered that hardwired electrical connections exist between circuitry associated with redundant SFAS instrument and logic channels 1 and 3.
Specifically, the power supply returns (floating commons) for the 15 Vdc and +24 Vdc supplies within the SFAS cabinets for channels 1 and 3 were electrically connected. Similar connections existed between SFAS channels 2 and 4.
The Davis-Besse SFAS uses a 2-out-of-4 "deenergize-to-actuate" logic for the actuation of engineered safety features equipment. Each of four instrument / sensing channels (for each monitored SFAS parameter) provides inputs to each of four logic channels. Each logic channel provides an output when any two or more of its inputs are in a tripped condi-tion. The outputs of logic channels 1 and 3 are combined to form SFAS actuation channel I which initiates SFAS equipment in train 1.
Similarly, SFAS logic channels 2 and 4 are combined to form SFAS actuation channel 2 which initiates equipment in train 2.
Both logic channels associated with an actuation channel must be tripped in order to cause an SFAS actuation. Prior to the SFAS actua-tion on December 5, 1980, a short circuit within a +15 Vdc power supply associated with SFAS instrument channel I resulted in 120 Vac on the shared (floating) return between channels 1 and 3.
This caused bistable setpoints within both channels to deviate from their normal values, in some cases exceeding Technical Specification limits. This condition existed for several f
days prior to the SFAS actuation.
The staff's review of the interconnections between redundant SFAS channels i
raised the following concerns:
- 1) An electrical fault on a shared power supply return could potentially cause a spurious SFAS actuation and 2) an undetected Nk S
-2 fault (the shared. power supply returns are not continuously monitored for fault conditions) coupled with a single failure within a channel unaffected by the fault could potentially prevent a SFAS actuation when needed. The licensee instituted monthly surveillance testing to determine the presence of extraneous voltage on the SFAS comons. However, the staff does not consider this fre-quency sufficient to identify and correct fault conditions prior to adversely affecting components within redundant SFAS channels. The staff concluded that the Davis-Besse SFAS design does not comply with the requirements of Section 4.6 (Channel Independence) of IEEE Standard 279-1971.
In order to resolve the staff's concerns regarding the comon ties between redundant SFAS sensing and logic channels, the licensee proposed to permanently connect the floating comons to the instrument ground. The SFAS was function-ally tested successfully in this configuration. With the floating commons connected to the instrument ground, the effects of power supply failures similar to that which occurred prior to the inadvertent SFAS actuation on December 5,1980 would be limited to a single SFAS instrument or logic channel.
The licensee, however, cautioned that grounding the commons would result in significant potential hazards relating to system reliability, that ground faults or stray voltages occurring subsequent to grounding could potentially damage an instrument channel, and concluded that this configuration poses a greater potential for SFAS damage and is considered highly undesirable.
The staff's review of the licensee's proposal concluded that although permanent grounding of the shared floating comons may resolve SFAS channel independence concerns, additional information supporting SFAS connections to the instrument ground system was required since the Davis-Besse plant has had a history of problems regarding the instrument ground system and its relationship to the station ground system. The specific concern was that inadvertent ties exist between these systeins at other than the designed comon tie point. Given an electrical fault, loop fault current could produce an induced voltage in systems connected to the instrument ground, potentially affecting system opera-bility. The licensee submitted an analysis which demonstrated that safety systems would perform as intended given the worst case station electrical fault i
l
condition with the inadvertent ties present between the instrument and station ground systems. The staff's review of the analysis concluded that the installed instrument-station ground system was acceptable based on the understanding that there were no inadvertent ties between the SFAS instrument ground (i.e., the floating returns) and the station ground, and therefore, that faults could not be postulated that would adversely affect the engineered safety features of the facility. Therefore, the staff requested the licensee to provide additional information demonstrating that connecting the floating power supply returns (SFAS instrument grounds) to the instrument ground system was an acceptable approach to resolving the SFAS channel separation concern, and that the operability of the SFAS will be assured following such a modification.
Subsequent to the staff's request, the licensee requested a meeting with the staff to discuss alternate methods available to resolve the issue. Options considared by the licensee included 1) continuous monitoring of the 115 Vdc and +24 Vic SFAS power supply commons for electrical fault conditions,
- 2) connecting the power supply cornmons to the instrument ground system as dis-cussed above, 3) physically removing all interconnections between redundant SFAS channels, thus separating the power supply returns, and 4) separating the sensor / instrument channel power supplies from the logic / actuation power supplies, and removing the connections between redundant instrument channel power supplies. The licensee has decided to implement option 4.
EVALUATION Two figures are provided at the end of this report to aid in the understanding of the material in this section.
Figure 1 shows the Davis-Besse SFAS logic configuration ar'd the boundary between instrument / sensor channels and logic /
actuation channels.
Figure 2 shows the SFAS power supply configuration before and after the modifications. Both of these figures reflect the general Davis-Besse SFAS design, but have been greatly simplified and should not be used to infer design deta-lls.
l
e..
The Davis-Besse SFAS design uses 15 Vdc and +24 Vdc power supplies. The -15 Vdc supplies provide power to sensor / instrument channel components only. The
+24 Vdc supplies provide power to logic / actuation channel components only.
The +15 Vdc supplies provide power to both the instrument and logic portions of the SFAS. The SFAS de power supply design uses a floating ground system, i.e., the power supply returns (commons) are isolated from the SFAS cabinet structure which is connected to'the instrument-station ground system. The floating returns for SFAS instrument channel #1, logic channel #1, instrument channel #3, and logic channel #3 are electrically connected (hardwired).
Similar connections exist between SFAS channels 2 and 4.
These connections between redundant SFAS channels led to the channel independence and single failure concerns identified by the staff. The floating return configuration was selected by design to reduce the number of contacts (and thus the amount of field run wiring) from SFAS relays and control switches needed to actuate SFAS equipment, and to reduce the potential for degradation of SFAS performance given a fault voltage existing between the SFAS de commor, and the SFAS cabinet structure.
To provide electrical independence between redundant SFAS instrument channels, four new +15 Vdc supplies will be used to provide power to instrument channel components. New power supplies wiil be added to SFAS cabinets 2 and 4, and existing +15 Vdc supplies which are currently spares will be used in SFAS cabinets 1 and 3 (these supplies were originally provided for automatic test circuitry which is no longer used). These supplies will provide power to instrument channel components only (amplifiers, current isolation converters, bistable modules, etc., and associated test and calibration circuits). The existing SFAS +15 Vdc supplies that were previously used for both instrument and logic channel components will now be used to provide power to SFAS logic /
actuation channel components only. The four instrument channel +15 Vdc supplies will be electrically independent from each other, and each supply will be electrically separated from its corresponding +15 Vdc logic channel power supply. Thus, each SFAS instrument channel will have its own dedicated +15 Vdc and -15 Vdc power supplies. These supplies will share the same floating ground (designated as the " sensor common").
The sensor commons of redundant SFAS l
i instrument channels are not connected, thus maintaining channel independence.
Each SFAS logic / actuation channel will have its own dedicated +15 Vdc and
+24 Vdc power supplies which share a separate floating ground (designated as the " logic common"). The sensor common and logic common within each SFAS cabinet are not connected, thus maintaining electrical separation between the sensor and logic portions of the SFAS. All connections which previously tied the sensor and logic commons together and redundant instrument channel supply commons together have been eliminated.
The above modifications can be accomplished by circuit modifications within the four SFAS. The electrical separation of redundant sensor commons will assure that the effects of SFAS power supply failures similar to that which occurred prior to the inadvertent actuation on December 5, 1980 will be limited to a single SFAS instrument channel (i.e., multiple / redundant channels will not be affected).
In addition, since the floating power supply return configuration has been retained, the above modifications will not make the SFAS more vulnerable to spurious trips or equipment damage from electrical faults, and connections between the SFAS and the instrument-station ground system have been avoided.
It should be noted that following the SFAS modifications, the logic commons for SFAS logic / actuation channels 1 and 3 will remain electrically connected as will the logic commons for channels 2 and 4.
SFAS logic channels 1 and 3 are combined to actuate SFAS equipment in train 1 (powered from division 1). Both channels 1 and 3 must trip to cause actuation. SFAS logic channels 2 and 4 operate in a similar fashion to actuate equipment in train 2 (powered from division 2). Because the logic / actuation channels associated with a given i
train of SFAS equipment are not electrically indeperdent, an electrical fault condition associated with a shared logic common could be postulated to disable both logic / actuation channels and therefore, to disable the safety functions of one train of SFAS equipment. However, this situation is not considered more limiting than other failure modes (e.g., loss of divisional power), where SFAS equipment in the redundant train is relied on to accomplish required safety functions. Furthermore, since the two logic / actuation channels associated with
a given SFAS train are arranged in a 2-out-of-2 (logical "AND") configuration (i.e., both channels must trip to cause equipment actuation), a single failure of either logic / actuation channel will preclude the SFAS safety functions of a single train. However, four electrically independent logic / actuation channels are not required to comply with NRC regulations. A four channel design in which dependent logic channels are combined to form two electrically independent actuation channels, such a the Davis-Besse design, is acceptable if properly implemented. Therefore, the electrical connections between redundant logic commons are consic'ered acceptable provided that adequate isolation exists between the seruor and logic portions of each SFAS channel (such that faults within the logic portion can not affect instrument / sensor channel performance),
and that faults within the logic portion of the SFAS are detectable.
There are two types of interfaces which occur between the instrument / sensor portions and the logic / actuation portions of the Davis-Besse SFAS. The first and most frequently used interface occurs at the bistable module outputs. Each bistable for each SFAS monitored parameter (containment radiation, containment pressure, reactor coolant pressure, and borated water storage tank level) provides four isolated outputs, one output to each SFAS logic channel. Thus, even the output signal to the associated logic channel is isolated.
Isolation is provided by opto-electronic devices housed in the bistable modules. The second interface occurs at the reactor coolant pressure bistable modules used to generate block permissivos that allow manual bypass of the reactor coolant low pressure trip functions. Here, relay coil-to-contact isolation is used between the logic channel (+24 Vdc relay side) and the instrument channel
(+15Vdccciitactside). The staff cor.cludes that the isolation provided between the sensors channels and logic channels is acceptable to maintain sen-sor channel independence. All other instrument channel circuits (e.g.,
indicators, annunciator outputs, computer outputs, etc.) are isolated using relay coil-to-contact isolation or current-to-current converters. The licensee has stated that the physical separation between redundant SFAS sensor and actuation channels, reviewed and approved during plant licensing, has not been compromised as a result of the SFAS modifications discussed above.
The licensee has proposed testing following implementation of the modifications to demonstrate that instrument / sensor channel portions of the SFAS have been effectively isolated from the logic / actuation portions of the SFAS. Specifi-cally, the resistance between the sensor comon and the logic comon for each SFAS channel will be measured to verify electrical separation.
In addition, the resistance between the sensor comon and the SFAS cabinet structure, and the logic comon and the SFAS cabinet structure for each SFAS cabinet will be measured to verify isolation of the SFAS from the instrument-station ground system. The acceptance criteria for these tests will be a resistance of greater than 10 megohms. The staff concludes that these tests and the accep-tance criteria are acceptable to demonstrate adequate isolation. However, the staff recomends that a similar resistance test be perfomed between redundant SFAS sensor comons to verify that all connections between redundant sensor channels have been eliminated.
If the only connections between redundant SFAS sensor channels in the original design were due to the shared de commons by sensor and logic channels and the subsequent sharing of logic comons in the actuation circuits for SFAS equipment, then this test will reaffirm the effec-tiveness of the modifications to provide isolation between sensor channels (i.e.,
this test will verify that no direct connections exist between redundant sensor channels). The licensee has comitted to perform the routine monthly SFAS surveillance tests following the modifications to verify the functional per-formance of SFAS sensor and logic circuits.
Surveillance test procedure ST 5031.03, " Containment Pressure to SFAS Calibra-tion," requires monthly testing for ac voltage potential between each SFAS logic comon and the station ground. This test is used to detect power supply or other failures similar to that which occurred prior to the inadvertent SFAS i
actuation on December 5, 1980. Following the SFAS modifications, this testing will continue, and will be extended to include the SFAS sensor comons (i.e.,
testing for ac voltage potential between each SFAS sensor common and the station ground will also be performed monthly). The continued monthly testing of the SFAS logic comons is necessary because an electrical fault on one of the floating logic comons may not be easily /quickly detected. The staff has
determined that the monthly surveillance frequency is the minimum acceptable for detecting faults which may have occurred, and taking appropriate correc-tive actions to ensure that the SFAS is not degraded below an acceptable level.
CONCLUSION Based on the review of information provided by the licensee in letter #1229 dated December 16, 1985, and an audit review of the field change procedure, including revised electrical schematic / elementary diagrams of the SFAS, the staff concludes that the modifications proposed by the licensee are sufficient to resolve staff concerns regarding independence between redundant SFAS instru-ment channels and to bring the Davis-Besse SFAS design into conformance with Section 4.6 (Channel Independence) of IEEE Standard 279-1971, " Criteria for Protection Systems for Nuclear Power Generating Stations." Therefore, the staff concludes that the proposed modifications to the Davis-Besse SFAS are acceptable pending successful completion of the post-modification tests discussed in the above evaluation. The acceptability of the modifications is based in part on continued monthly testing of the SFAS instrument and logic commons to detect for degraded voltage conditions.
In addition, the licensee should perform resistance tests between redundant SFAS sensor commons to verify that all connections between redundant sensor channels have been removed, and the results of these tests should be submitted for staff review.
IRVIS-BESSE SAETY WATURES ACTlRTION SYSTEM (SFAS)
LOGICDIAGRAM m
~
SENSOR 3
SENSOR SENSOR SENSOR i
CHANNEL CHANNEL CHANNEL CHANNEL
~
INSTRIENT/ SENSOR
- 1
- 3
- 2 M
OW1EL 3
(INCLLDES BISTABLES, 3
8 AW LIFIERS, AND SIGNALCONDITIONING)
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i
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LOGIC LOGIC LOGIC l
LOGIC LOGIC PORTION CHANNEL #1 C'lANNELll3 CHANNEL /I2 CHANNEL $
LOGIC /ACILRTION l
0%W_l_
i l
ACTUATION poarion 2-OUT-OF-2 2-OUT-OF-2 ACTtRTION ACTtMTION LOGIC LOGIC 1
l U
U 1
1 ELECTRICAL SEPARATION SFAS I
SFAS BOUNDAF'.' EXISTING EQUIPMENT l
EQUIPMENT PRIOR TO MODIFICATION TRAIN 1 TRAIN 2 e........................
ADDITIONAL ELECTRICAL l
SEPARATION PROVIDED AFTER MODIFICATION FIGURE 1
IMVIS-ESSE SAFELY EATlFES ACTlMTION SYSTEM (SFAS)
SENSOR AND LOGIC OWiEL POWER SLPPLY BLOCK DIAGRAM (CHANNELS 1 AND 3 ARE SHOWNJ C m NNELS 2 AND 4 ARE SIMILAR)
SFAS CABINET # 1 SFAS CABINET # 3 SFAS CABINET # 1 SFAS CABINET # 3 i
118 VAC, 60 HZ POWER 118 VAC, 60 HZ POWER 118VAC,60HZPOWER 118 VAC, 60 HZ POWER FOR SFAS chaff 4EL # 1 FOR SFAS CHANNEL # 3 FOR SFAS CHAT #4EL # 1 FOR SFAS CHANNEL # 3 i
r - - - - - -
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PS PS I
PS PS I
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8 SENSOR I
SENSOR i
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SENSOR
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'_ _ CHAT #4EL
'_ _ _ chaff 4EL
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i LOGIC AND i LOGIC AND i LOGIC AND,
i LOGIC AND i iACTUATION 1 ACTtMTION i i ACTUATION,
i ACTUATION I
8 i CHAT #4E I
' CHANNE 8
L_____L
' _ CHANNEL 1_ CHANNEL t _ _ _ _ _L
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l I
I BEEE WDIFICATION AFTER M DIFICATION FIGURE 2 THE HEAVY LINE REPRESENTS THE PS
= POWER SUPPLY - ONLY ONE IS SHOWNJ AS FLOATIfG SFAS P0bER SUPPLY RETLRNS MANY AS THREE OR FOLR MAY BE PROVIDED}}