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MONTHYEARML20207N5761982-03-13013 March 1982 Maint Procedure MP 1405.05, 480-Volt Type Ak Reactor Trip Breaker Maint & Testing Project stage: Other ML20078R6281983-11-0707 November 1983 Forwards Response to Generic Ltr 83-28 Re Required Actions Based on Generic Implications of Salem ATWS Events.Joint Response W/Inpo & Nutac Will Be Submitted by 840731 Project stage: Other ML20100F5321985-03-29029 March 1985 Provides Addl Info in Response to 850130 Request Re Items 4.2.1 & 4.2.2 of Generic Ltr 83-28 Concerning Salem ATWS Events.Reactor Trip Breaker Maint Performed Per Maint Procedure MP 1405.5 Project stage: Other ML20100D9851985-03-29029 March 1985 Notifies of Installation of New Phone Sys,Effective 850401 Project stage: Request ML20137R1611985-11-12012 November 1985 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Preventive Maint & Trending of Parameters Project stage: Approval ML20137R1371985-11-12012 November 1985 Advises of Completion of Review of 831107 & 850329 Responses to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Preventive Maint & Trending of Parameters.Responses Acceptable Project stage: Approval 1983-11-07
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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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UNITED STATES p
NUCLEAR REGULATORY COMMISSION g
,j WASHINGTON, D. C. 20555 m
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1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RESPONSE TO GENERIC LETTER 83-28, ITEMS 4.2.1 AND 4.2.2 TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 DOCKET'NO. 50-346
1.0 INTRODUCTION AND BACKGROUND
Subsequent to the anticipated transient without scram (ATWS) events at the Salem Nuclear Power Plant, the Comission reviewed intermediate term actions to be taken by the licensees. The actions taken were developed on the basis of infomation contained in NUREG-1000. " Generic implications of ATWS Events at the Salem Nuclear Power Plant." On July 8,1983, Generic Letter (GL) 83-28 was issued by the NRC. The letter identified NRC positions developed from review of the Salem ATWS events. These positions were related to reactor trip system reliability and The Toledo Edison Company (the licensee) general management capability.
responded to GL 83-28 by letters dated November 7, 1983 (Serial No. 1000) and March 29, 1985 (Serial No. 1130).
The specific GL 83-28 items covered by this Safety Evaluation are Section 4.2.1 (Reactor Trip System Reliability - Preventive Maintenance) and Section 4.2.2 (Reactor Trip System Reliability -
Trending of Parameters) 2.0 DISCUSSION AND EVALUATION 2.1 Reactor Trip System Reliability (Preventive Maintenancel, Iten 4.2.1 2.1.1 Licensee Response The Generic Letter stated:
Licensees and applicants shall describe their preventive maintenance and surveillance program to ensure reliable reactor trip breaker operation. The program shall include a planned program of periodic maintenance, including lubrication, housekeeping, and other items recommended by the equipment
- supplier, r512050440 851112 DR ADOCK 050 6
. _ _ _ -.~
I r I
i
- The licensee stated in the November 7, 1983 response:
Maintenance Procedure MP 1405.05 (480V Type AK Circuit Breaker Maintenance and Testing) was written to provide instructions for the cleaning, inspecting, and testing of GE 480V circuit breakers. The CRD trip breakers have been incorporated into the Preventive Maintenance Program in which 4
Maintenance Procedure MP 1405.05 is performed every refueling cycle or as 1
- necessary to ensure the design performance of the, breakers. As per Maintenance Procedure MP 1405.05, Surveillance Test ST 5030.20 (CR0 Trip Breaker Response Time Test) is performed to test the response time of contact opening after de-energization of CRD trip breaker undervoltage coil as L
. required by Surveillance Test ST 5030.14 (RPS Overall Response Time Calculation). The Surveillance Test ST 5030.14 requires Surveillance Test ST j
5030.20 to be performed any time corrective or preventive maintenance is i
perfomed that could affect the response time.
e 2.1.2 Evaluation Criteria 1
The primary criteria for an acceptable periodic maintenance program are contained in Maintenance Instruction GEI-50299E!*, Power Circuit Breakers, i
Types AK-2/2A-15, AK-2/3/2A-25, AKU-2/3/2A/3A-25," and Service Advice L
175-9.35 and 175-9.20, by General Electric. The NRC staff, has reviewed these items and endorsed the maintenance program they describe. 'The criteria i
I include those items in the General Electric Instructions and advisories that relate to the safety function of the breaker, supplemented by those measurements which must be taken to accumulate data for trending. Those items identified for maintenance that should be included in the licensee's RTB maintenance program are:
1
+
1.
Verification of breaker cleanliness and insulation structure; all foreign materials, such as paint, dust, or oil, should be removed to prevent electrical breakdown between points of different potential; l
2.
Verification of breaker physical condition, including wiring insulation and temination, all retaining rings, pole bases, are quencher.
s' stationary and movable contacts, and tightness of nuts and bolts; l
3.
Verification of proper manual operation of the breaker, including. checks for excessive friction, trip bar freedom, latch engagement, o mechanism alignment and freedom, and undervoltage trip (UTV) perating device l
armature freedom; j
4.
Verification of the optimum freedom of the armature as specified in General Electric Service Advise 175-9.35, item #S1; l
5.
Verification of proper trip latch engagement as specified in Service Advice 175-9.35 Item #S2; 6.
Verification of undervoltage pick-up setting, as specified in Service Advice 175-9.35, item #S3, and dropout voltage; i
[
1
. 7.
Verification that the trip torque required on the trip shaft is less than 1.5 pound-inches, as specified in Service Advice 175-9.35, Item
- S4; "Before" and "After" maintenance torque values should be recorded; 8.
Verification of positive tripping by checking the adjustment between the UVT device and trip paddle as specified in Service Advice 175-9.3S, Item
- S5; 9.
Verfification of proper trip response time as specified in Service Advice 175-9.3S Item #S6;
- 10. Shunt Trip Attachment (STA) operation verification;
- 11. Examination and cleaning of breaker enclosure;
- 12. Functional test of the breaker prior to returning it to service.
A 12 month interval for preventative maintenance is justifiable based on the GE recommendation that maintenance be performed at least annually, with a hostile environment or severe load condition warranting more frequent maintenance.
The licensee responded in the March 29, 1985 letter that the Davis-Besse preventive maintenance program for RTB's contains all of the elements listed earlier. Further the licensee stated that:
The Davis-Besse Maintenance Department is assigned to collect the data from these parameters on a six month interval, per MP 1405.05.
Data from these parameters is given to the B&W Owners Group Availability Group for trending and anlaysis for the duration of the Reliability Monitoring Program.
Upon completion of the Reliability Monitoring Program, an analysis will be performed to evaluate the interval for performing periodic maintenance.
If the analysis indicates a period greater than 12 months is warranted, TED will perform breaker periodic maintenance using the 12 month interval recommended i
by General Electric, the breaker manufactuer, and B&W, the breaker supplier.
If analysis indicates a period less than 12 months is warranted, we will then determine the appropriate conservative interval for perfoming this maintenance.
Based on the above statements, as well as conversations with the licensee representatives, the staff concludes that preventive maintenance will be performed at intervals not exceeding 12 months, and is therefore, acceptable.
1 2.2 Reactor Trip System Reliability (Trending of Parameters), Item 4.2.2 l
. 2.1.1 Licensee Response The Generic Letter stated that:
Licensees and applicants shall describe their preventative maintenance and surveillance program to ensure reliable reactor trip breaker operation.
the program shall include trending of parameters affecting operation and measured during testing to forecast degradation of operability.
In the responses of November 7, 1983 and March 29, 1985, the licensee stated that Toledo Edison is a member of the B&W Owners Group Reliability Monitoring Program. A presentation of the conceptual program had been previously presented to the staff. Additional information about the scope and detail of the program were presented.
2.2.2 Evaluation Criteria The parameters measured during the maintenance program noted above which are applicable for trending are undervoltage trip attachment dropout voltage, trip torque, and breaker repsonse time for undervoltage trip. The staff position is that the above three parameters in addition to the breaker insulation resistance are acceptable and recomended trending parameters to forecast breaker operation degradation or failure.
If subsequent experience indicates that any of these parameters is not useful as a tool to anticipate failures or degradation, the licensee may, with justificatton and NRC approval, elect to remove that parameter from those to be tracked.
The licensee measures trip torque, breaker response time, undervoltage trip pickup and dropout voltage and insulation resistance. the licensee is a participant in the B&W Owners Group Reliability Monitoring Program, which is 4
attempting to identify the most effective parameters to forecast breaker degradation or fa'. lure. The licensee is providing these data, except for insulation resistance, to the B&W Owners Group Availability Group, which will perform trend analysis. The licensee has identified how often data will be collected and how the information derived from the analysis will be used to affect periodic maintenance. The staff finds the licensee position to be acceptable.
3.0 CONCLUSION
S Based on a review of the licensee responses, the staff finds the licensee positions on items 4.2.1 and 4.2.2 of Generic Letter 83-28 to be acceptable.
Dated: November 12, 1985 The following NRC personnel contributed to this Safety Evaluation:
N.
Romney, G. Dick
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