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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept ML20195E7591998-11-10010 November 1998 WCNOC Proposed PASS Function Reduction 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 ML20202F6881997-09-29029 September 1997 Evaluation of Underground Essential Svc Water Pipeline Leak ML20133F8451997-01-0808 January 1997 WCGS Quadrennial Simulator Certification Rept ML20117J0491996-05-0808 May 1996 At&T Round Cell Nuclear Util User'S Council Charter ML20100R4291996-02-28028 February 1996 Incident Investigation Team Rept, Plant Shutdown Due to Circulating Water & Essential Svc Water Intake Icing ML20100Q2031995-12-31031 December 1995 Annual SER 11 for Jan-Dec 1995 ML20091K4121995-08-22022 August 1995 Nonproprietary SE of Cycle 9 Core Reload Analysis for Wolf Creek ML20086R3281995-07-31031 July 1995 Human Interactions Evaluation Failure to Isolate Incorrect Valve Alignment During Shutdown ML20086A6531995-05-0303 May 1995 Pyrolysis Gas Chromatography Analysis of 5 Thermo-Lag Fire Barrier Samples ML20081D5481995-02-28028 February 1995 RCS Draindown Evaluation Summary Rept ML20126M1071992-12-31031 December 1992 Power Rerate Rept for Wolf Creek Generating Station ML20126B0901992-12-14014 December 1992 WCGS Simulator Certificate Data ML20116A8591992-10-31031 October 1992 Safety Evaluation & Cycle 7 TS Change Rept for Wolf Creek Generating Station ML20029A7391991-02-0606 February 1991 Economic Impact Study of Proposed KPL/KG-E Merger. ML20247F1321989-03-23023 March 1989 Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment ML20154K7881988-09-19019 September 1988 1988 Radiological Emergency Preparedness Exercise Objectives ML20195H4191988-01-14014 January 1988 Final Rept on NRC IE Bulletin 85-003 ML20147E8251987-12-31031 December 1987 Spent Fuel Storage Rack Criticality Analyses for Wolf Creek Generating Station ML20147E8361987-12-31031 December 1987 New Fuel Storage Rack Criticality Analysis for Wolf Creek Generating Station ML20237H3101987-07-16016 July 1987 Emergency Preparedness 1987 Field Exercise Scenario ML20215J0511987-06-19019 June 1987 Safety Evaluation Supporting Proposed Rev to Tech Spec 3/4.10.4 Re Reactor Coolant Loops to Replace Refs in Reactor Protection Sys P-7 Permissive w/P-10 Permissive ML20207R6911986-12-31031 December 1986 Annual Summary of Safety Evaluations Rept 2 for Jan-Dec 1986 ML20137L6381986-01-23023 January 1986 Reactor Vessel Ref Temp for Pressurized Thermal Shock ML20140A3741986-01-17017 January 1986 Final Rept of Independent Review of Environ Qualification Programs to NUREG-0588 ML20141H6201985-12-31031 December 1985 Nonproprietary Steam Generator Single-Tube Rupture Analysis for Snupps Plants Callaway & Wolf Creek ML20116E8171985-04-24024 April 1985 Final Rept:Task Analysis & Verification of Snupps Control Room ML20113A4961985-01-19019 January 1985 Rev 1 to Evaluation of Aws Field Welding on Structural & Miscellaneous Steel at Wolf Creek Generating Station, Final Rept ML20126H6031985-01-11011 January 1985 Const Self Assessment Corrective Action Evaluation ML20129D3921984-12-31031 December 1984 FSAR Commitment Compliance Study Results Rept ML20198B8321984-12-27027 December 1984 Evaluation of Aws Field Welding on Structural & Miscellaneous Steel at Wolf Creek Generating Station, Final Rept.Related Info Encl ML20133C9131984-12-27027 December 1984 Final Rept on Evaluation of Aws Field Welding on Structural & Miscellaneous Steel at Wolf Creek Generating Station. Related Documentation Encl ML20101K2821984-12-21021 December 1984 Draft Interim Justification Position for Seismic & Environ Qualification of In-Core Thermocouples,Connectors,Adaptors & Ref Junction Box (ESE-43 & ESE-44) ML20096D4721984-08-31031 August 1984 Rev 2 to Plant Recovery Core Damage Assessment Methodology ML20108B7031984-07-20020 July 1984 Monthly Progress Rept for June 1984 ML20093A3911984-06-30030 June 1984 Rev 1 to Detailed Control Room Design Review Summary Rept for Snupps, in Response to Generic Ltr 82-33,(NUREG-0737, Suppl 1) ML20086L0211984-02-0202 February 1984 Detailed Control Room Design Review Summary Rept for Snupps, in Response to Generic Ltr 82-33,NUREG-0737, Suppl 1 ML20079Q3961984-01-27027 January 1984 Rev 1 to Rept on Control of Heavy Loads ML20079G5061984-01-13013 January 1984 Rev 1 to SAR for Safety Parameter Display Sys ML20086M9611983-12-31031 December 1983 Evaluation of Containment Coating Acceptance Tests ML20079G3841983-12-31031 December 1983 Purge Valve Operability Rept,Snupps Project ML20082H9731983-11-28028 November 1983 Interim Rept on Water Seepage at Station 58 of Wolf Creek Generating Station Main Dam. W/One Oversize Figure. Aperture Card Is Available in PDR ML20071E6841983-03-10010 March 1983 Rept of Independent Review of Environ Qualification Programs to NUREG-0588 ML20064G5891982-12-31031 December 1982 Pressurizer Safety & Relief Line Piping & Support Evaluation,Callaway Unit 1 & Wolf Creek Unit ML20062E8581982-07-23023 July 1982 Seismic Evaluation of Wolf Creek Generating Station Structures Using Livermore Spectrum,Evaluation of Piping Sys & Supports ML20062K1771982-07-0101 July 1982 Essential Svc Water Sys Pump Restraint Embed Rept ML20054L4931982-06-15015 June 1982 Pressurizer & Safety Relief Line Piping & Support Evaluation & Action Plan, Interim Rept ML20052D8661982-04-30030 April 1982 to Seismic Evaluation of Wolf Creek Generating Station Structures Using Lll Spectrum. 1999-07-29
[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
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i ATTAclDiENT I SAFETY EVALUATION l
l 8706240304 070619 PDR ADOCK 050004G2 PDR P
SAFETY EVALUATION This application for amendment revises Wolf Creek Generating Station (WCGS), ,
Unit No. 1, Technical Specification 3/4.10.4, Reactor Coolant Loops, I replacing references to the Reactor Protection System P-7 permissive with the P-10 permissive.
Background
Technical Specification 3/4.10.4, Reactor Coolant Loops, is a special test exception which allows requirements to be suspended provided certain criteria are met. One of the requirements which may be suspended is Technical Specification 3.4.1.1 during the performance of startup and PHYSICS TESTS in MODE 1 or 2 provided:
- 1) The THERMAL POWER does not exceed the P-7 Interlock Setpoint, and
- 2) The Reactor Trip Setpoints are on the OPERABLE Intermediate and Power Range channels are set less than or equal to 25% of RATED THERMAL POWER.
The proposed technical specification revision would replace the P-7 Interlock Setpoint with the P-10 Interlock Setpoint where P-7 is listed in Technical Specification 3/4.10.4 Limiting Condition for Operation and Surveillance Requirements.
Interlock P-7 is a Reactor Protection System permissive that unblocks certain Reactor Trips when going above 10 percent power. P-7 is derived from a bistable circuit that is fed from P-10 and P-13. Either P-10 or P-13 will trip the P-7 bistable. The presence of P-10 allows a manual block of the power range (low setpoint) reactor trip, the intermediate range reactor trip, and intermediate rod stops. P-10 is also used as a back-up to block the source range reactor trip. The P-13 permissive provides a signal when the turbine is greater than 10 percent power. The permissive is generated when one-of-two turbine impulse pressure channels indicates greater than 10 percent power.
Technical Specifications presently require both the P-10 and P-13 permissives to be OPERABLE whenever this specification is being used for low power physics testing. This amendment request would require only the P-10 permissive to be OPERABLE. This change would reduce the amount of surveillence testing required prior to entering this technical speci fica tion .
Evaluation The P-7 permissive is derived from a bistable circuit indicating greater than ten percent power as measured by either first stage turbine pressure or nuclear-power range level. The turbine power input is supplied by P-13 and the nuclear power range input is supplied permissive P-10. Permissive P-7 defeats the automatic block of the following:
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. Attachm:nt I to ET 87-0219 Page 2 of 3 June 19, 1987
- 1) Pressurizer low pressure trip
- 2) Pressurizer high level trip
- 3) Reactor Coolant Pump undervoltage and underfrequency trips
- 4) Reactor coolant low flow trip in more than one loop The F-10 permissive is used to bypass the intermediate range high flux and power range low setpoint trips during an approach to power. It also serves as a backup for P-6 by automatically blocking out the source range high voltage and provides one of the two inputs to P-7. P-10 is derived from a bistable circuit indicating greater than ten percent power as measured by the' power range nuclear instruments. In order to block the intermediate range high flux power range low setpoint trips, the reactor must be above ten percent nuclear power.
The P-13 permissive provides a signal when the turbine is greater than 10 percent power. The permissive is generated when one-of-two turbine impulse pressure channels indicates greater than ten percent power. The P-13 permissive is the other one of the two inputs to P-7 Low power physics testing involves tests run on the reactor following a refueling outage. During this testing the turbine is left on the turning gear and not 'used. Therefore, the P-13 signal is always at zero.
Consequently, P-10 is the only signal to P-7 while the plant is performing this Technical Specification. By completing the surveillance requirements for P-10 P-7 is ensured of being functional. Performing the surveillance requirments for P-13 for this Technical Specification requirement when it is not used for an input to P-7 is unnecessary.
The proposed change does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Safety Analys11 Report. This amendment will only eliminate surveillance requirements fc. P-13 while operating under this l Technical Specification. Since P-13 will not input into P-7 with the turbine left on the turning gear and not used, performing these surveillance .
requirements does not affect the reliability of the circuit which will trip the P-7 bistable.
The proposed change does not create the possibility of an accident or .
malfunction of a different type than any evaluated previously in the Safety Analysis Report. No additional plant equipment is being added nor will any l existing plant equipment be operated in a manner inconsistent with existing requirements. The proposed amendment does not change any setpoints related ,
l to nuclear safety. i The proposed change does not affect the margin of safety as defined in the
! basis for any technical specification. This amendment only eliminates the need to perform the surveillance requirements for P-13 while the plant is
, operating under this Technical Speci fica tion. The setpoints remain I
unchanged.
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, Attachstnt I to ET 87-0219 Page 3 of 3
.Juna'19,'1987
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Conclusion' Based on the' above discussion and the considerations presented in Attachment II, ; the ' proposed revision to Technical: . Specification - 3/4.10.4 .does not.
increase the probability of occurrence.or. the consequences of an accident or malfunction'of ~ equipment.important to safety 'previously evaluated in the g
Safety Analysis;' Report;- or create the possibility for an~ accident or malfunction of a different type than any previously evaluated in~ the Safety Analysis. Report; or reduce the margin of safety. as defined in the basis for -
any Technical Specification. Therefore, the proposed revision does not adversely affect' or . endanger. the health and safety of the general public or ,
involve- a significant safety hazard. ;
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i ATTACHMENT II f
SIGNIFICANT HAZARDS CONSIDERATION i
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'* - 'SIGNIFICANT HAZARDS CONSIDERATION This application for amendment revises Wolf Creek Generating Station, Unit No ~1,. Technical Specification 3/4.10.4, Reactor Coolant Loops, replacing
. references to the . Reactor Protection System P-7 permissive with the P-10 permissive.
- 1. The proposed change does not involve a significant increase in the-probability or consequences of an accident previously . evaluated.
The proposed amendment would only eliminate . surveillance.
requirements for P-13 which have no effect on plant operation while using this . Technical Specification. With the turbine off line, P-13 does not provide an input into P-7. This leaves P-10 as the only input which can trip the P-7 bistable.
- 2. The proposed change does not create the possibility of a new or 6ifferent. kind of accident from any previously evaluated. . There are no new failure modes or mechanisms associatedL with the proposed changes. No. additional plant equipment is . being ladded nor will any existing plant equipment be operated in a manner inconsistent with existing requirements. . The proposed change-does-not change any.setpoints related to nuclear safety.
- 3. The. proposed change does not involve a significant reduction in a '
margin of safety. The proposed amendment does not affect ' any -
technical specification margin of safety. This amendment only eliminates the need to perform the surveillance. requirements for P-13 while the plant is operating under this Technical Specification. The proposed change does not alter the manner in which safety limits and limiting safety system setpoints are determined.
Based on the above discussions and those presented in Attachment I,_ it has been determined that the requested Technical. Specification revision does not.
involve a significant increase in the probability or consequences of an accident or other adverse condition over previous evaluations; or create the possibility.of a new or different kind of accident or condition over
-previous evaluations; or involve a significant reduction in a margin of sa fety. There fore , the requested license amendment does not involve a significant hazards consideration.
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