|
---|
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] |
Text
._____ _ ___-
'p %q 7 # k UNITED STATES
[
5'
'g NUCLEAR REGULATORY COMMISSION
, WASHINGTON, D. C. 20656
- 1 9.....l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
_ GENERIC LETTER 83-28, ITEM 2.1 (PART 1) -
EQUIPMENT CLAS$1FICAT10N - RTS COMPONENTS GENERIC LETTER 83-28, ITEM 2.1_(PART 2) -
VENDOR INTERFACE PROGRAM - RTS COMPONENTS KANSAS GAS & ELECTRIC _ COMPANY KANSAS CITY POWER AND LIGHT COMPANY KANSAS ELECTRIC POWER COOPERATIVE. INC.
WOLF CREEK GEhERATING STATION DOCKET NO._5_0-482
1.0 INTRODUCTION
On February 25. 1983, both of the scram circuit breaker, at Unit 1 of the
- Salem Nuclear Power Plan failed to open upon an automatic reactor trip signal from the reactor protection system. This incident was terminated manually by the operator about 30 seconds after the initiation of the automatic trip signal. The failure of the circui? breakers was determined to be related to the sticking of the undervoltage trip attachment. Prior to this ir.cident, on February 22. 1983, at Unit 1 of the Salem Nuclear Power Plant, an automatic trip signal was generated based on steam generator low-low level during plant start-up. In this case, the reactor was tripped manually by the operator almost coincidentally with the automatic trip. '
Following these incidents, on February 28. 1983, the NRC Executive Director for Operations (EDO). directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant. The results of the staff's inquiry into the generic implications of the Salem unit incidents are reported in NUREG-1000. "Generic Implications of the ATWS Events at the Salem Nuclear Power Plant." As a result of this investigatio I. the Comission (NRC) requested (by Generic letter 83-29 dated July 8. 1983 ) all licensees of opersting reactors, applicants for an operating license, and holders of construction pennits to respond t,o generic issues raised by the analyses of these two ATWS events.
This report is an evaluation of the responses submitted by the Wolf Creek Nuclear Operating for Item 2.1 (Part ) Company,(Part and 2) of Generic letter 83-28the licensee for the Wolf treek G The actual documents reviewed as part of this evt.luation are listed in the references et the end of the report. ,
8809060370 0G0901 DR ADOCK 050 2
)
4 0
Item 2.1 (Part 1) requires the licensee to confim that all reactor trip system components are identified, classified and treated as safety-related as indicated in the following statement:
Licensees and applicants shall confirm that all components whose functioning is required to trip the reactor are identified as safety-related on documents, procedures, and infomation handling systems used in the plant to control safety-related activities, including maintenance, work orders, and parts replacement.
Item 2.1 (Part 2) requires the licensee to confim that an interface has been established with the NSSS or with the vendors of each of the components of the Reactor Trip System which includes:
periodic comunication between the licensee / applicant and the NSSS or the vendors of each of the components of the Reactor Trip System, and a system of positive feedback which confims receipt by the licensee / applicant of transmittals of vendor technical infomation.
2.5 EVALUATION Item _2.1(Part1)
The licensee for the Wolf Creek Generating Station, Unit I responded to the requirements of item 2.1 (Part 2) with a submittal dated February 29, 1984'.
The Itcensee stated in this ';ubmittal that Westinghouse is the NSSS for the j Wo1f Creek Generating Station, Unit I and that the RTS is included as part of L the Westinghouse interface program established for this plant. The response
- also confims that this interface program includes both periodic comunication between Westinghouse and the licensee and positive feedback from the licensee in the fem of signed receipts for technical information transmitted by Westinghouse.
l Item 2.1 (Part 2)
The licensee for the Wolf Creek Generating Station responded to the 1
requirementsofitem2.1(Part1)githsubmittalsdatedNovember 15, 19833 ,
February 29, 1984 and May 29, 1987 . The initial submittal stated that the Itcensee was developing a list identifying all of the safe.ty-related components that are required to function to trip the reactor and confirmed that this list would be used to verify that these components were identified as safety related in documents, procedures, and infomation handling systems.
The February 29, 1984 response stated that the program would be completed by fuel load. The May 29, 1987 response stated that the program had been implemented and that the Q-list approval process had been changed to provide that the Nuclear Plant Engineering Division now has the responsibility for approving all changes, additions, and revision to the Q-List.
~
3.0 CONCLUSION
Item 2.1 (Part 1)
Based on our review, we find the licensee's statements confinn that a program exists for identifying, classifying and treating components that are required for performance of the reactor trip function as safety related. This program meets the requirements of Item 2.1 (Part 1) of Generic Letter 83-28, and is therefore acceptable.
Item 2.1 (Part 2)
Based on our review of these responses, we find the licensee's staterrents confirm that a vendor interface program exists with the NSSS vendor for cottponents that are required for performance of the reactor trip function.
This program meets the requirerrents of Item 2.1 (Part 2) of Generic letter i 83-28, and is therefore acceptable. ,
I
4.0 REFERENCES
- 1. NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, .
Applicants for Operating License, and Holders of Construction Permits, ;
"Required Actions Based on Generic Implications of Salem ATWS Events j t
(Generic letter 83-28)," July 8, 1983 ,
- 2. Letter, Kansas Gas & Electric Company (G. L. Koester) to NRC (H. R. Denton, February 29, 1984
- 3. Letter Kansas Gas a Electric Company (G. L. Koester) to NRC (H. R. Denton),
November 15, 1983, l i
4 4 Letter Wolf Creek Nuclear Operating Corporation (B. D. Withers) to NRC, May 29, 1987.
f Dated: September 1,1988 Principal Contributors: P. O'Connor, D. Lather l
I