Letter Sequence Approval |
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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 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 ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant 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 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 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 ML20128L3001996-10-0202 October 1996 SER Supporting Dbnp IPE Process of Identifying Most Likely Severe Accidents & Severe Accident Vulnerabilities ML20058M9591993-09-28028 September 1993 SE Accepting Licensee Response to GL 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' ML20057A3791993-08-20020 August 1993 SE Concluding That Second 10-yr Interval Inservice Insp Program Plan for Plant Has Unacceptable Exam Sample as Discussed in Encl Inel TER ML20056G4301993-08-18018 August 1993 Safety Evaluation Re Inservice Testing Program Requests for Relief.Licensee Made Changes to Subj Program to Include Exercising & fail-safe Testing of Auxiliary Feedwater Valves AF-6451 & AF-6452,in Response to TER Anomaly 8 ML20056B2721990-08-20020 August 1990 Safety Evaluation Granting Relief from ASME Code Repair Requirements for ASME Code 3 Piping ML20248D8271989-09-29029 September 1989 Safety Evaluation Accepting Util 890228 & 0630 Submittals Presenting Proposed Designs to Comply w/10CFR50.62 ATWS Rule Requirements ML20247E6901989-09-0505 September 1989 Safety Evaluation of Audit of Facility Design for Resolution of IE Bulletin 79-27 Re Loss of non-Class IE Instrumentation & Control Power Sys Bus During Operation.Preventive Maint & Testing Program Should Be Developed for Bus Power Sources ML20247J8731989-05-18018 May 1989 Safety Evaluation Supporting Amend 133 to License NPF-3 NUREG-0660, Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 21989-05-0303 May 1989 Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 2 ML20196D9601988-12-0808 December 1988 Safety Evaluation Re Util Response Concerning Auxiliary Feedwater Sys Reliability Study.Util Should Ensure That Sys Mods Do Not Result in Net Reduction in Sys Reliability ML20207K7911988-10-0404 October 1988 Safety Evaluation Supporting Operation in Cycle 6 W/O Removing Flaws in Cracked HPI Nozzle ML20148D0391988-01-19019 January 1988 SER Accepting Util 831209 Response to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip reliability-on-line Testing.Unit Designed to Permit on-line Functional Testing of Diverse Trip Features of Reactor Trip Breakers ML20147C2631988-01-12012 January 1988 Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification of Reactor Trip Sys Components ML20149F9621988-01-11011 January 1988 SER Accepting License Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for safety- Related Components ML20236U6531987-11-27027 November 1987 Safety Evaluation Re Effects of Errors in Util Analysis of Small Break Loca.Use of Incorrect Values in Analysis Results in Incomplete Compliance w/10CFR50,App K.Plant Poses No Risk to Public Health Due to Meeting 10CFR50.46 Requirements ML20236T3871987-11-25025 November 1987 SER Re Conformance to Reg Guide 1.97 Concerning post-accident Monitoring Instrumentation.Design Acceptable ML20211G8641987-02-11011 February 1987 Safety Evaluation Supporting Licensee Responses to Generic Ltr 83-28,Item 3.2.3, Post-Maint Testing & All Other Safety-Related Components ML20207Q6711987-01-0909 January 1987 Safety Evaluation Supporting Util Re Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML20212C9231986-08-0404 August 1986 Sser Supporting Util Reanalyses of 74 Masonry Walls ML20212G6021986-08-0404 August 1986 Safety Evaluation Accepting Util Response to NRC Request for Addl Info Re Question 29 Concerning Training for Infrequent, Critical & Difficult Tasks ML20212R3421986-06-10010 June 1986 SER Re Progress Made by Licensee in Area of Plant Maint.New Maint Organization Functioning W/No Major Weaknesses.Region III Will Continue to Monitor Maint at Plant to Assure Continued Control & Progress ML20206F3041986-05-27027 May 1986 Safety Evaluation Accepting Util Review Re Cold Pressurization of Secondary Side of Steam Generator During Testing on 850906 ML20203N9141986-04-17017 April 1986 Safety Evaluation Accepting Proposed Mods to Safety Actuation Sys Re Shared Power Supply Returns as Result of 801205 Actuation NUREG-0103, Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing1986-03-0606 March 1986 Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing ML20137J6891986-01-0808 January 1986 Safety Evaluation Supporting Util Identification of Root Causes for Spurious 850609 Steam & Feedwater Line Rupture Control Sys Low Level Actuation,Closure of MSIVs & Actions Taken to Prevent Recurrence.Plant Restart Acceptable ML20137J7031986-01-0808 January 1986 SER Supporting Util Identification of Root Causes for Source Range Nuclear Instrumentation Channels Inoperability During 850609 Steam & Feedwater Line Rupture Control Sys Low Level Actuation & Corrective Actions Taken.Plant Restart Approved ML20136B7841985-12-24024 December 1985 SER Re Util Development of Systematic & Thorough Troubleshooting Plans to Investigate 850609 Incident Leaving Redundant source-range Nuclear Instrumentation Channels Inoperable.Restart & Power Operation Now Acceptable 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 ML20138P0681985-10-30030 October 1985 Safety Evaluation Accepting Licensee 831107 & 850709 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,4.1 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability (vendor-related Mods & Sys Functional Test Description) ML20138P6391985-10-30030 October 1985 SER Re Proposed Mods to Maint Program.Licensee Should Identify Actions to Be Completed Prior to or After Restart. Region Should Actively Monitor Licensee Progress ML20133Q0441985-10-24024 October 1985 Safety Evaluation Supporting Util 831107 Response to Generic Ltr 83-28,Item 3.1.3 Re post-maint Testing (Reactor Trip Sys Components).Eg&G Technical Evaluation Rept Encl ML20062E0871982-07-29029 July 1982 Safety Evaluation Supporting Licensee Request for Relief from ASME Boiler & Pressure Vessel Code Section XI Hydrostatic Test (Insp) Requirements ML20214J2801979-12-20020 December 1979 Safety Evaluation Re Preliminary Design for Upgrading Present control-grade Anticipatory Reactor Trip Sys for Loss of Main Feedwater & Turbine Trip to safety-grade ML20125B1331968-12-16016 December 1968 Safety Evaluation Re Piqua Nuclear Power Facility Retirement.T Hamrick to J Schlesinger Encl 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 ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.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 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 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 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 ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 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 ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.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 ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With 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 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 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 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A4121998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20196B5221998-05-23023 May 1998 10CFR50.59 Summary Rept of Facility Changes,Tests & Experiments Dbnps,Unit 1 for 960602-980523 ML20236E7581998-05-19019 May 1998 Rev 0 to Davis-Besse Unit 1 Cycle 12 Colr ML20236N7501998-04-30030 April 1998 Rev 2 to Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit ML20247F6721998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Davis-Bess Nuclear Power Station,Unit 1 ML20249A4141998-04-30030 April 1998 Revised Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20217P8041998-04-0707 April 1998 11RFO OTSG ECT Insp Scope ML20216B4041998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20216C5131998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20202D3721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20199G6321998-01-26026 January 1998 Rev 1 to Davis-Besse Unit 1,Cycle 11,COLR 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 ML20198K7931997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20217K6401997-12-31031 December 1997 1997 Annual Rept First Energy ML20203A3931997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Davis-Besse Nuclear Power Plant,Unit 1 ML20198S5371997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Davis-Besse Nuclear Power Station ML20217H7701997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20216H3261997-08-31031 August 1997 Monthly Operating Rept for August 1997 for DBNPS ML20217K0241997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Davis Besse Nuclear Power Station,Unit 1 1999-09-30
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j#*% ' 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)responded general management to GL 83-28 by capability.
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 6 DR ADOCK 050
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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 4
have been incorporated into the Preventive Maintenance Program in which 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 '
i these items and endorsed the maintenance program they describe. 'The criteria '
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. I 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) device perating 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
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- 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 4
participant in the B&W Owners Group Reliability Monitoring Program, which is 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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