Letter Sequence Approval |
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MONTHYEARML20127D8071985-05-0909 May 1985 Forwards Request for Addl Info Re Response to Generic Ltr 83-28,Items 4.1,4.2.1 & 4.2.2.Response Requested within 60 Days of Ltr Receipt Project stage: RAI ML20129J4011985-07-17017 July 1985 Forwards Response to NRC 850509 Request for Addl Info Re Generic Ltr 83-28,Items 4.1,4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability,Periodic Maint Program & Trending of Reactor Trip Breakers,Respectively Project stage: Request ML20211P9321986-07-21021 July 1986 Safety Evaluation Supporting Util Preventive Maint Program for Reactor Trip Breakers in Response to Generic Ltr 83-28 Items 4.1,4.2.1 & 4.2.2 Project stage: Approval ML20211P9191986-07-21021 July 1986 Forwards SER Re Preventive Maint Program for Reactor Trip Breakers in Response to Generic Ltr 83-28 Items 4.1,4.2.1 & 4.2.2.Program Acceptable Project stage: Approval 1985-07-17
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 ML20195D5261999-06-0202 June 1999 Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI ML20195H9801998-11-17017 November 1998 Safety Evaluation Supporting Proposed Changes to WCGS Radiological Emergency Response Plan ML20216J7791998-04-15015 April 1998 SER Approving Requests for Relief I1R-46 Through I1R-49 & I2R-21 Submitted by Licensee on 970523.Relief for Exam Category B-A,Item B1.12,RPV Shell Welds Deferred Until Licensee Satisfies Regulations for Augmented Rv Exam ML20216C2641998-04-0606 April 1998 SER Accepting Addl Info Re GL 92-08, Thermo- Lag 330-1 Fire Barriers, for Plant ML20217H3491998-03-31031 March 1998 SER Accepting Operational Quality Assurance Program Description Change for Wolf Creek Generating Station ML20217H7241998-03-30030 March 1998 SER Accepting Proposed Change to Operational Quality Assurance Program for Plant ML20202B9791997-11-26026 November 1997 Safety Evaluation Accepting Relief Requests 2VR-7 VR-8 from ASME Boiler & Pressure Vessel Code,Section XI Requirements for Inservice Testing Program ML20198Q2821997-10-24024 October 1997 Safety Evaluation Granting Relief for Second 10-yr Interval ISI Program Plan & Associated Requests for Plant ML20217J7071997-10-0909 October 1997 Safety Evaluation Accepting Second 10-yr ISI Interval Relief Request I2R-22 ML20141D0501997-06-23023 June 1997 Safety Evaluation Supporting Requests for Relief to Use ASME Code Case N-508-1 for Plant ML20147C1561997-01-31031 January 1997 Safety Evaluation Accepting Licensee Structural Integrity & Operability ML20247N1811989-09-20020 September 1989 Safety Evaluation Supporting Plant Inservice Testing Program & Request for Relief ML20236C7501989-03-0909 March 1989 SER Supporting Util 880801 Request for Relief from ASME Code Pump & Valve Inservice Testing Program Requirements for Bearing Temp for Safety Injection Pumps ML20153E6921988-09-0101 September 1988 Safety Evaluation Accepting Licensee Program for Equipment Classification & Vendor Interface ML20151H1411988-07-19019 July 1988 Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 4.3 Re Reactor Trip Breaker Automatic Shunt Trip ML20151G5121988-07-15015 July 1988 Safety Evaluation Supporting Amend 17 to License NPF-42 ML20195K0801988-06-17017 June 1988 Safety Evaluation Supporting Amend 16 to License NPF-42 ML20155G1041988-06-0101 June 1988 Safety Evaluation Re Diesel Generator Circuit Breaker Manual Close Capability.Final Design Acceptable ML20153F8471988-05-0202 May 1988 Safety Evaluation Granting Util Relief from Section XI of ASME Code Re Replacement of Parts on Two Code Classed Components ML20147D9631988-02-25025 February 1988 Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90 ML20148J7351988-01-15015 January 1988 SER of First 10-yr Inservice Testing Program Plan & Requests for Relief from Requirements Concluding That Program as Modified by SER Provides Reasonable Assurance of Operational Readiness of safety-related Pumps & Valves ML20237D7591987-12-16016 December 1987 Safety Evaluation Concluding That Util Proposed ATWS Design in Compliance w/10CFR50.62 & Acceptable,Subj to Final Resolution of Tech Spec Issue & Completion of Certain Human Factors Engineering Reviews ML20236R3241987-11-12012 November 1987 Safety Evaluation Supporting Util Submittal of Rev 2 to First 10-yr Interval Inservice Insp Program Plan ML20205Q7131987-04-0101 April 1987 Safety Evaluation Re Util 861001 Submittal of Analysis of Large Break LOCA in Response to License Condition 2.C.(12). Analysis Acceptable & License Condition 2.C.(12) Satisfied ML20211P1991986-12-15015 December 1986 Safety Evaluation Supporting Util 860123 Response to PTS Rule.Matl Properties & Fast Neutron Fluence Calculations Acceptable Until End of Current License.Reevaluation of Rt (PTS) Required by 10CFR50.61 ML20214W8821986-12-0202 December 1986 Safety Evaluation Supporting Util 850524,1104 & 861105 Submittals Re Process Used to Identify Deviations from Emergency Response Guidelines.Justification Provided for Identifying Deviations Acceptable ML20215K9841986-10-22022 October 1986 SER Supporting Util 831115 & 860812 Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing Requirements for safety-related Components,Based on Plans to Address Diesel Generator Testing Concerns ML20236N9221986-10-0707 October 1986 SER Accepting Util 840229 & 860529 Responses to Generic Ltr 83-28,Items 3.1.1 & 3.1.2 Re post-maint Testing of Reactor Trip Sys Components ML20215D8321986-10-0707 October 1986 SER Re Util 840229 & 860529 Responses to Generic Ltr 83-28, Items 3.2.1 & 3.2.2 Re post-maint Testing of safety-related components.Post-maint Testing Program Acceptable ML20215D6221986-10-0707 October 1986 SER Re Licensee Response to Generic Ltr 83-28,Item 4.5.1, Reactor Trip Sys Reliability (Sys Functional Testing). Reactor Trip Sys Functional Testing Acceptable ML20203G5361986-07-24024 July 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 1.2 Re post-trip Review Data & Info Capability ML20211P9321986-07-21021 July 1986 Safety Evaluation Supporting Util Preventive Maint Program for Reactor Trip Breakers in Response to Generic Ltr 83-28 Items 4.1,4.2.1 & 4.2.2 ML20134F5061985-08-16016 August 1985 Safety Evaluation Supporting Util 850522 Description of Mods to Low Temp Overpressure Protection Sys of Rcs.Requirements of License Condition 2.C.(13) Met ML20134F5191985-08-16016 August 1985 Safety Evaluation Supporting Rev 12 to Facility Site Addendum Re Removal of 345 Kv Offsite Transmission Line to West Gardner Switching Station from Design ML20128Q8371985-07-0303 July 1985 SER Supporting Deletion of Pseudo Rod Cluster Control Assembly Drop Test at 50% Power.No Useful Info Would Be Gained from Performance of Test ML20128C8321985-06-26026 June 1985 SER Supporting Licensee Programs Re Generic Ltr 83-28,Item 1.1, Post-Trip Review 1999-09-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1521999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Wolf Creek Generating Station.With ML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 ML20212A0251999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Wolf Creek Generating Station.With ML20217P6451999-08-30030 August 1999 Requests Commission Approval to Publish Encl Pr,Rg & SRP & to Issue Encl Ltr to Parties of Wolf Creek Transfer Proceeding Re Disposition of Existing Antitrust License Conditions in Event OL Transfer Approved ML20210R5741999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Wolf Creek Generating Station ML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept ML20210R5921999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20209H0821999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20195D5261999-06-0202 June 1999 Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI ML20210R5871999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1021999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1071999-04-30030 April 1999 Revised MOR for Apr 1999 for Wolf Creek Generating Station ML20206P8261999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Wcgs.With ML20196L3401999-04-30030 April 1999 Rev 1 to WCGS Cycle 11 Colr ML20210R5841999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Wolf Creek Generating Station ML20205Q0761999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Wolf Creek Generating Station.With ML20207K5991999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Wolf Creek Generating Station.With ML20207K9761998-12-31031 December 1998 Annual SER 14,for Period 980101-1231, for WCGS ML20199E6531998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Wolf Creek Generating Station.With ML20195C0011998-12-31031 December 1998 Ks City Power & Light Co 1998 Annual Rept & Financial Statements as of 981231 & 1997 for Ks Electric Power Cooperative,Inc ML20195B9901998-12-31031 December 1998 Western Resources Annual Rept for 1998 ML20198D7321998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Wolf Creek Generating Station.With ML20195H9801998-11-17017 November 1998 Safety Evaluation Supporting Proposed Changes to WCGS Radiological Emergency Response Plan ML20195E7591998-11-10010 November 1998 WCNOC Proposed PASS Function Reduction ML20195D1791998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Wolf Creek Generating Station.With ML20154L4591998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Wolf Creek Generating Station.With ML20153G2771998-09-30030 September 1998 Rev 1 to WCAP-15079, Wolf Creek Heatup & Cooldown Limit Curves for Normal Operation ML20153G2851998-09-30030 September 1998 Rev 1 to WCAP-15080, Evaluation of Pressurized Thermal Shock for Wolf Creek ML20153G2691998-09-30030 September 1998 Rev 1 to WCAP-15078, Analysis of Capsule V from Wolf Creek Nuclear Operating Corp Wolf Creek Reactor Vessel Radiation Surveillance Program ML20153G7301998-09-23023 September 1998 Special Rept 98-003:on 980814,station Entered TS 3.3.3.6, Action Statment a Due to Inoperability of RVLIS B Train. Cause Has Not Yet Been Identified.Work Order 98-202813-000 Has Been Generated ML20151W1491998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Wcgs.With ML20237B7381998-08-14014 August 1998 Special Rept 98-001:on 980615,oxygen Analyzer on Wgs Was Declared Inoperable.Wgs Oxygen Analyzer OARC-1119A Was Indicating 0 Ppm on 980814 & Fluctuated Between 200 & 900 Ppm on 980615.Completed Work Order & Declared Wgs Operable ML20237B0841998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Wolf Creek Generating Station ML20236P3441998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Wolf Creek Generating Station ML20236P3481998-05-31031 May 1998 Corrected Page of MOR for May 1998 for Wolf Creek Generating Station ML20249A0171998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Wolf Creek Generating Station ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20247H0901998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Wolf Creek Generating Station ML20216J7791998-04-15015 April 1998 SER Approving Requests for Relief I1R-46 Through I1R-49 & I2R-21 Submitted by Licensee on 970523.Relief for Exam Category B-A,Item B1.12,RPV Shell Welds Deferred Until Licensee Satisfies Regulations for Augmented Rv Exam ML20216C2641998-04-0606 April 1998 SER Accepting Addl Info Re GL 92-08, Thermo- Lag 330-1 Fire Barriers, for Plant ML20216F6101998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Wolf Creek Generating Station ML20217H3491998-03-31031 March 1998 SER Accepting Operational Quality Assurance Program Description Change for Wolf Creek Generating Station ML20217H7241998-03-30030 March 1998 SER Accepting Proposed Change to Operational Quality Assurance Program for Plant ML20216G1971998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Wolf Creek Nuclear Operating Corp ML20202H0721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Wolf Creek Generating Station ML20217G4311997-12-31031 December 1997 Western Resources 1997 Annual Rept & Financial Statements for Years Ended 971231 & 1996 for Ks Electric Power Cooperative,Inc ML20203H0151997-12-31031 December 1997 Annual Operating Rept 13 for Jan-Dec 1997 ML20217G3711997-12-31031 December 1997 Kansas City Power & Light Co 1997 Annual Rept ML20216D7771997-12-31031 December 1997 Annual SER 12 for Jan-Dec 1997, for Wolf Creek Generating Station 1999-09-30
[Table view] |
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SAFETY EVALUATION REPORT T
WOLF CREEK GENERATING STATION REACTOR TRIP SYSTEM RELIABILITY ITEMS 4.1, 4.2.1 AND 4.2.2 0F GENERIC LETTER 83-28
- 1.
Introduction:
On July 8, 1983, the Nuclear Regulatory Comission (NRC) issued Generic Letter (G'
- 1-28. This letter addressed intermediate-term actions to be taken bl .... sees and applicants aimed at assuring that a comprehensive program or preventive maintenance and surveillance testing is implemented for the reactor trip breakers (RTBs) in pressurized water reactors. In particular, Item 4.1 of the letter required licensees and applicants to verify that all venoor recommended reactor trip breaker modifications have been implemented.
Item 4 2 required them to submit a description of their preventive maintenance and surveillance program to ensure reliable reactor trip breaker operation.
The description of the submitted program was to include the following:
GL, Item 4.1 Review of all vendor-recommended reactor trip breaker modifications to verify that either: each modification has, in fact, been implemented, or a written evaluation of the technical reasons for not implementing a modification exists.
GL, Item 4.2.1 A planned program of periodic maintenance, including lubrication, housekeeping, and other items recommen.ded by,the equipment supplier.
GL, Item 4.2.2 Trending of parameters affecting operation and measured during testing to forecast degradation of operation.
2 e6072%$gg g .
PDR P ,
E i
i Kansas Gas and Electric Company, the licensee for Wolf Creek, responded to the Generic Letter on November 15, 1983, February 29, 1984 and July 17, 1985. This report presents an evaluation of the adequacy of the licensee's responses and of his preventive maintenance and surveillance 2
programs for RTBs.
r i 2. Evaluation Criteria j
2.1 Periodic Maintenance Program l
The primary source for periodic maintenance program criteria is Westing-house Maintenance Program Manual for DS-416 Reactor Trip Circuit Breakers,
! Rev. O. This document was prepared for the Westinghouse Owners Group and is the breaker manufacturer's recommended maintenance program for the DS-416 breaker. It provides specific direction with regard to schedule, inspection l and testing, cleaning, lubrication, corrective maintenance and record keeping, j The document was reviewed to identify those items that contribute to breaker trip reliability consistent with the generic letter. Those items identified for maintenance at six month intervals (or when 500 breaker operations have
- been counted, whichever comes first) that should be included in the i licensee's RTB maintenance program are
}
- 1. General inspection to include checking of breaker's cleanliness, all bolts and nuts, pole bases, arc chutes, insulating link, wiring and auxiliary switches; j 2. Retaining rings inspection, including those on the undervoltage trip attachment (UVTA);
- 3. Arcing and main contacts inspection as specified by the Westing- ,
house Maintenance Manual; i
i s
-,-r---, n,.,-..n .- - ,-- - --, ,. ~ ~ . - - - - , , , , , - - , - , - . - - , - , - - . , -n.- , , . . - -
- 4. UVTA check as specified by the Westinghouse Maintenance Manual, including replacement of UVTA if dropout voltage is greater than 60% or less than 30% of rated UVTA coil voltage;
- 5. Shunt Trip Attachment (STA) check as specified by the Westinghouse Maintenance Manual;
- 6. Lubrication as specified by the Westinghouse Maintenance Manual; I 7. Functional check of the breaker's operation prior to returning it to service.
The licensee's RTB periodic maintenance should also include, on a refueling interval basis:
- 1. Pre-cleaning insulation resistance measurement and recording;
- 2. RTB dusting and cleaning;
- 3. Post-cleaning insulation resistance measurement and recording, as specified by the Westinghouse Maintenance Manual;
- 4. Inspection of main and secondary disconnecting contacts, bolt tightness, secondary wiring, mechanical parts, cell switches, instruments, relays and other panei mounted devices;
- 5. UVTA trip force and breaker load check as specified by the Westing-house Maintenance Manual; f
4
- 6. Measurement and recording of RTB response time for the undervoltage trip;
- 7. Functional test of the breaker prior to returning to service as specified by the Westinghouse Maintenance Manual.
2.2 Trending of Parameters Generic Letter Item 4.2.2 specifies that the licensee's preventative l maintenance and surveillance program is to include trending of parameters affecting operation to forecast degradation of operation. The parameters measured during the maintenance program described above which are applicable for trending are undervoltage trip attachment dropout voltage, trip force, response time for undervoltage trip and breaker insulation resistance. The staff position is that the above parameters are acceptable 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 justification and NRC approval, elect to remove that parameter from those to be tracked.
- 3. Evaluation:
3.1 Evaluation of the Licensea's Position on Item 4.1 The licensee has confirmed that all vendor-recommended modifications have been completed. The staff finds the licensee position on Item 4.1 to be acceptable.
f
- i. .
t 3.2 Evaluation of the Licensee's~ Position on Item 4.2.1 i The licensee has confirmed that its periodic maintenance program will 7 include those items listed in Section 2.1 of this SER at the specified
! frequency. However, after several inspection periods, and if experience 3
warrants, the licensee plans to perfom all preventative maintenance during each refueling outage or after 500 RTR operations, whichever occurs first.
, The staff finds the licensee position on Item 4.2.1 to be acceptable.
Acceptance of the licensee's extended maintenance interval is based on the vendor recomendation that maintenance on RTBs located in mild environments ,
i should be perfomed at refueling intervals. The vendor recomendation that o* 'ocated in harsh environments or experiencing severe load conditions be l maintained more frequently is not applicable to these RTBs because of their location in a mild environment and reduced service duty at Wolf Creek (less than 200 RTB cycles annually).
k I
3.3 Evaluation of the Licensee's Position on Item 4.2.2 1
The licensee has stated that Wolf Creek will perform trend analysis on UVTA dropout voltage and breaker response time, and will record trip force and breaker insulation resistance. The applicant has identified the organization which will perform trend analysis, how often it will be
- perfomed and how the information derived from the analysis will be used to I affect periodic maintenance. The staff finds the licensee position on Item 4.2.2 to be acceptable.
i
' 4.
Conclusions:
i Based on a review of the licensee responses, the staff finds the licensee's position on Items 4.1, 4.2.1 and 4.2.2 of Generic Letter 83-28 to be I acceptable.
i l
g Mr. Glenn L. Koester Kansas Gas and Electric Company Wolf Creek Generating Station Unit No. 1 CC*
Mr. Nicholas A. Petrick Executive Director, SNUPPS Mr. Gary L. Haden. Director 5 Choke Cherry Road Research & Energy Analysis Rockville, Maryland 20850 Kansas Corporation Commission 4th Floor - State Office Building Topeka, Kansas Jay Silberg, Esq. 66612-1571 Shaw, Pittman, Potts & Trowbridge 1800 M Street, NW Regional Administrator, Region IV Washington, D.C. 20036 U.S. Nuclear Regulatory Comission Office of Executive Director for Operations Mr. Donald T. McPhee Vice President - Production 611 Ryan Plaza Drive, Suite 1000 Kansas City Power & Light Company Arlington, Texas 76011 1330 Baltimore Avenue Kansas City, Missouri 64141 Mr. Allan Mee Project Coordinator Chris R. Rogers, P.E. Kansas Electric Power Cooperative,Inc.
Manager Electric Department P. O. Box 4877 Public Service Comission Gage Center Station P. O. Box 360 Topeka, Kansas 66604 Jefferson City, Missouri 65102 Resident Inspector / Wolf Creek NPS Regional Administrator, Region III c/o U.S. Nuclear Regulatory Comission
' U.S. Nuclear Regulatory Commission P. O. Box 311 799 Roosevelt Road Burlington, Kansas 66893 Glen Ellyn, Illinois 60137 Mr. Brian Moline Brian P. Cassidy Regional Counsel Chief Legal Counsel Kansas Corporation Comission Region I Emergency, Management Agency Federal 4th Floor - State Office Building i t
J. W. McCormack P0CH Topeka, Kansas 66612-1571 Boston, Massachusetts 02109
- Senior Resident Inspector / Wolf Creek NPS y Mr. Robert Elliot, Chief Engineer c/o U.S. Nuclear Regulatory Comission Utilities Division P. O. Box 311 Kansas Corporation Comission Burlington, Kansas 66839 4th Floor - State Office Building Topeka, Kansas 66612-1571 Mr. Gerald Allen Public Health Physicist "
Bureau of Air Quality & Radiation Control Division of Environment Kansas Department of llealth and Environment Forbes Field Building 321 a Topeka, Kansas 66620 ,
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