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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K8411999-09-0202 September 1999 Proposed Tech Specs Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band ML20210J1431999-07-29029 July 1999 Proposed Tech Specs Changes to ITSs ML20209D3651999-07-0808 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising Allowable Value for CTS Table 3.3-4,functional Unit 8.a.,4 Kv Undervoltage - Loss of Voltage & Functional Unit 8.b.,4 Kv Undervoltage - Grid Degraded Voltage ML20209C2081999-06-30030 June 1999 Proposed Tech Specs Re Temporary Change to CTS Without Action to Reduce Power ML20195G0331999-06-11011 June 1999 Proposed Tech Specs Pages,Revising TS 3.7.1.6 & Bases by Modifying LCO to Require Four ARVs to Be Operable, Eliminating Use of Required in Action Statements & Adding New Action for Three or More ARVs Inoperable ML20195F7961999-06-10010 June 1999 Proposed Tech Specs,Revising Z,S & Allowable Value Terms for Current TS Table 3.3-4,functional Unit 7.b,automatic Switchover to Containment Sump (RWST Level - Low-Low) ML20206Q9041999-05-11011 May 1999 Proposed Tech Specs 3/4.7.5, Ultimate Heat Sink, Proposing Addl Required Zcaion for Restoring Ultimate Heat Sink to Operable Status within Completion Time of 8 H ML20196K7321999-03-26026 March 1999 Proposed Tech Specs Converting to Improved Tech Specs ML20205A2111999-03-25025 March 1999 Markups of Current & Improved TS Re TS Conversion Application ML20207J2021999-03-0505 March 1999 Proposed Tech Specs Re Conversion to ITS Section 1,0,3.1, 3.2,3.3,3.4,3.6,3.7,3.8,3.9,4.0 & 5.0 ML20199G7281999-01-15015 January 1999 Proposed Tech Specs SR 4.7.3b Deleting During SD Requirement & Reflect Appropriate Plant Conditions in Associated 3/4.7.3 Bases ML20199F4511999-01-12012 January 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising TS 3/4.7.5 by Adding New Action Statement Requiring Verification of Operability of Two RHR Trains,Or Initiation of Power Reduction with Only One RHR Train Operable ML20198P1211998-12-29029 December 1998 Proposed Tech Specs to Incorporate Revised Heatup & Cooldown Limit Curves & Revised Cold Overpressure Mitigation Sys (COMS) PORV ML20207J9621998-12-18018 December 1998 Rev 1 to TRM for Wolf Creek Generating Station,Unit 1 ML20197H6701998-12-0808 December 1998 Proposed Corrected Tech Spec Page 4.0-2 Increasing Spent Fuel Storage Capacity ML20196G6161998-12-0202 December 1998 Proposed Tech Specs Section 3.3, Instrumentation ML20196B4901998-11-24024 November 1998 Proposed Tech Specs Pages & follow-up Items Re Proposed Conversion to TS Section 1.0,3.4,3.5 & 3.6,per 980828 RAI ML20195E7671998-11-10010 November 1998 Rev 0 to EPP 01-2.4, Core Damage Assessment Guidance ML20155H6121998-11-0606 November 1998 Proposed Tech Specs Bases 3/4.7.1.2 Re Afws ML20155H6841998-11-0606 November 1998 Proposed Tech Specs Pages,Revising TS Bases Section 3/4.4.4, Relief Valves ML20154S5911998-10-23023 October 1998 Proposed Tech Specs Sections 3.1, Reactivity Control Sys, 3.2, Power Distribution Sys, 3.4, RCS, 3.5, ECCS & 5.0, Administrative Controls ML20154S5721998-10-23023 October 1998 Proposed Tech Specs Section 3.5.1,increasing AOT in Action B. to 24 Hours in Lieu of Current AOT of One Hour ML20154R9321998-10-20020 October 1998 Proposed Tech Specs 3/4.3,changing ESFAS Functional Units 6.f,8.a & 8.b ML20153H0431998-09-24024 September 1998 Proposed Tech Specs Pages Re RAI on Application for Amend to License NPF-42,incorporating Changes to TS Sections 3.4 & 5.0 ML20236Y2771998-08-0505 August 1998 Proposed Tech Specs Sections 3.1,3.2,3.5,3.9 & 4.0 Converting to Improved Std Tech Specs ML20236R4781998-07-17017 July 1998 Proposed Tech Specs 3/4.7.5 Revising UHS by Adding Temporary New Action Statement ML20236G8321998-06-30030 June 1998 Proposed Tech Specs Re Section 3.6, Containment Sys ML20247F8611998-05-0808 May 1998 Proposed Tech Specs 3/4.3.2,Table 3.3-3,revising Functional Unit 7.b.,RWST Level low-low Coincident W/Safety Injection, by Adding New Action Statement ML20216J8291998-03-20020 March 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity & Increasing Max Nominal Fuel Enrichment to 5.0 W/O (Nominal Weight Percent) U-235 ML20202D1251998-02-0404 February 1998 Proposed Tech Specs 3/4.2.4 Re Quadrant Power Tilt Ratio ML20202C4561998-02-0404 February 1998 Proposed Tech Specs 3/4.3 Re Changes to ESFAS Functional Units 6.f,8.a & 8.b ML20199H3551998-01-28028 January 1998 Proposed Tech Specs 6.3 & 6.12,reflecting Position Change within Organization ML20198P5001998-01-15015 January 1998 Proposed Tech Specs Replacement Pages Clarifying Bases in 970-902 LAR Re Auxiliary Feedwater Sys ML20198Q9411997-11-0606 November 1997 Proposed Tech Specs Bases Section 3/4.8.1,3/4.8.2 & 3/4.8.3 for Installation of Spare Battery Chargers ML20217K2181997-10-17017 October 1997 Proposed Tech Specs 4.5.2b,revising Surveillance Requirement to Vent ECCS Pump Casings ML20217B6161997-09-19019 September 1997 Proposed Tech Specs Bases Section B3/4.9.2,adding Info Re Role of Source of Power Supplied to One Source Range Neutron Flux Monitor in Determining Operability of Monitor in Mode 6 ML20216F7311997-09-0606 September 1997 Proposed Tech Specs,Alleviating Need for Enforcement Discretion Granted by NRC on 970905 ML20216F6911997-09-0505 September 1997 Proposed Tech Specs,Requesting NRC Exercise Discretion Re Compliance W/Srs 4.8.1.1.2.g.2)c)2,4.8.1.1.2.g.3)d) & 4.8.1.1.2.g.4)d) ML20216D1551997-09-0202 September 1997 Proposed Tech Specs,Adding Requirements for Essential Svc Water Flowpaths to turbine-driven AFW Pump ML20196J4071997-07-29029 July 1997 Proposed Tech Specs Revising Wording of Action Statement 5a to TS Table 3.3-1, Reactor Trip Sys Instrumentation ML20141G7721997-07-0303 July 1997 Proposed Tech Specs Section 5.3.1 Incorporating Addl Info Into TS 6.9.1.9, Colr ML20151T0151997-05-15015 May 1997 Proposed Tech Specs Re Response to Request for Addl Info on Conversion to Improved Tech Specs ML20198J6551997-05-15015 May 1997 Proposed Tech Specs Re Response to RAI on Proposed Conversion to Ists,Section 3.8, Electrical Power Sys ML20154Q2441997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20195J8241997-05-15015 May 1997 Proposed Tech Specs Re Rev to Increase Spent Fuel Pool Storage Capacity ML20138F3371997-04-30030 April 1997 Rev 0 to Offsite Dose Calculation Manual ML20138B9121997-04-23023 April 1997 Proposed Tech Specs,Revising TS 3/4.9.4 Containment Bldg Penetrations & Associated Bases Section to Allow Selected Containment Isolation Valves to Be Opened Under Administrative Controls During Periods of Core Alterations ML20137X3371997-04-15015 April 1997 Proposed Tech Specs 6.8.5.d Re Reactor Coolant Pump Flywheel Insp Program ML20147F8241997-03-21021 March 1997 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insp Program ML20137C2031997-03-19019 March 1997 Proposed Tech Specs Bases Pp Reflecting Corrections to Ref Made on Those Pp 1999-09-02
[Table view] Category:TEST REPORT
MONTHYEARML20069K0561994-06-0909 June 1994 Startup Rept for Wolf Creek Generating Station Power Rerate & T Hot Increase ML20067C0131994-02-18018 February 1994 Startup Rept for Wolf Creek Generating Station Power Rerate & T Hot Reduction ML20094F4571992-02-17017 February 1992 Reactor Containment Bldg Integrated Leak Rate Test for Wolf Creek Generating Station ML20236L5001987-08-31031 August 1987 Analysis of Capsule U from Wolf Creek Nuclear Operating Corp Wolf Creek Reactor Vessel Radiation Surveillance Program ML20137T6031985-11-27027 November 1985 Startup Rept for Cycle 1 ML20117E0041984-12-31031 December 1984 Primary Reactor Containment Integrated Leakage Rate Test, Final Rept ML20080B2691984-02-29029 February 1984 Diesel Generator Rocker Arm Lube Oil Temp Test Rept - SER Confirmatory Item 26 for Callaway & Item B.26 for Wolf Creek ML20073P9831983-03-31031 March 1983 Containment Recirculation Sump Hydraulic Performance, Snupps ML20062M0401981-07-30030 July 1981 Inservice Testing Program Wolf Creek Generating Station ML19324A0501979-09-24024 September 1979 WR Waugh Basemat Concrete Testing Program. 1994-06-09
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Aftachment to ET 94-0053 Page 1 of 2 STARTUP REPORT FOR WOLF CREEK GENERATING STATION POWER RERATE AND Tavg INCREASE d INTRODUCTION This report describes the testing that supported the increase in heactor Coolant System (RCS) full power average temperature (Tavg)from 581.2 F to 586.5 *F, and an associated incraase in reactor thermal output from 3480 to 3565 MWt, at the Wolf Creek Generating Station (WCGS). This report is a supplement to the Startup Report submitted on February 18, 1994 (letter ET 94-0020, from F. T. Rhodes, WCNOC to NRC) and is submitted as required by Sections 6.9.1.1, 6 . 9.1. 2, and 6.9.1.3 of the WCGS Technical j Specifications. The previous report, submitted under letter ET 94-0020, I indicated that the generator output breakers had been modified due to revised amperage requirements. Although this had been identified as a pre-outage (the sixth refueling outage) task, subsequent analysis indicated that this modification would not be required, and was not performed.
I The license amendment request for approval to operate with limiting safety j system settings relating to the RCS average temperature increase was !
submitted on February 7, 1994 (letter NA 94-0018, from R. C. Hagan, WCNOC to NRC). This submittal contained evaluations demonstrating that the Nuclear Steam Supply System and Balance of Plant systems had been reviewed and found capable of meeting all applicable safety design bases and power generation bases as defined in the Updated Safety Analysis Report, at the uprated conditions. This submittal was subsequently approved and issued by the NRC on March 3, 1994, as Amendment No. 72 to the WCGS Operating License.
This report represents the results of implementation of Amendment No. 72 to the WCGS Operating License. The primary goal of the T avg inu ease program was to obtain an increase in electrical output.
Reactor thermal output presented in this report is based on feedwater flow that, due to venturi fouling, was indicating about 1.4 % higher than actual.
IMPLEMENTATION OF THE POWER RERATE Changes were made to the WCGS Technical Specifications concerning Tavg j limitr, Axial Flux Difference limits, Over-Power and .Over-Temperature .iT trip setpoints, and instrument accuracy and response times.
An engineering calculation was performed to determine the minimum allowable RCS flow indication (less than 0.5% adjustment) for the density change due to increase in design Tcold from 549.3 F to 554.8 F. No change was made to the low flow trip setpoints because there was sufficient conservatism in the present setpoint to accommodate the flow change due to coolant density decrease in the cold leg of the RCS (a density decrease results in a conservative change in the indication from the prior calculation based on 549.3 F for Tcold)-
Flux maps were taken before rerate implementation to verify core parameters were within acceptable limits, and compared to 3565 MWt rated power to predict post-rerate acceptability. Results showed sufficient margin existed to allow escalation to the Rated Thermal Power level (3565 MWt) 0406150234 940609 ,,,
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Attachment to ET 94-0053 Page 2 of 2 Daseline data and component rescaling for the T avg increase was commenced on March 7, 1994, and final data ai the new T avq nd necessary component rescaling was completed on March 17, 1994. Proce~ dure and software changes were prepared prior to implementation of the T avg increase and issued as directed by the implementing procedure. Implementation was conducted under temporary procedure, TP-EN-159, " Power Uprate and Tavg Increase."
Rescaling of components was accomplished at approximately 3480 MWt. This was done prior to commencement of power increase to the design uprate power l value of 3565 MWt. P; ant calorimetric data was taken and Power Range Nuclear Instrumentation (NI's) adjusted whenever changes were made which could affect accu 8dcy of the NI's. Major component and tra nsmitter rescaling and recalibration, along with power ascension to 35C5 M 4t , were completed on March 10, 1994. Turbine Control Valves were 95 's open at the power level of 3565 MWt. Rescaling and recalibration of selected l components that were determined to be outside the desired tolerance limits, l were completed at the full power level.
l The power uprate and Tavg increase resulted ir. electrical output of about 1221 Mde at the Rated Tnermal Power level, an increase of about 29 MWe.
TESTING Testing included collecting baseline and full power data for the following components: vibrations for the turbine generator, feedwater pumps, condensate pumps, and reactor coolant pumps (RCP) ; walk downs and inspection of pipe hangers for predetermined feedwater, condensate, and steam lines; trending using the plant computer for predetermined primary and secondary component parameters; and biological shield surveys at the l maximue achieved power level. The results of the testing showed the plant I operated at the new increased T avg, within expected ranges, and there was no noticeable increase in vibration or component degradation at Rated Thermal Power.
Balance of Plant data was taken for condensate, feedwater, main steam, and reheat steam systems. The values for this data remained within expected levels at Rated Tnermal Power. The generator and associated components were monitored during the uprate and component values remained at acceptable levels. Pipe hanger inspections on feedwater and steam lines showed no adverse pipe movements as a result of changes in flows and temperatures. The biological shield survey at Rated Thermal Power based on feedwater flow calorimetric chowed no change in containment radiation levels at the monitored points. '
Flux maps were again taken at the maximum achieved power level to verify core parameters were within acceptable limits. Results showed acceptable margins existed for F q and Fah, and the core to be performing within acceptable design limits.
Initial full power AT's were extrapolated from measured values at I approximately 3480 MWt and compared with expected full power AT's following 1 l
implementation. The differences were small enough to maintain initial calibration until after implementation. Final values for AT's were determined at Rated Thermal Power, and the necessary adjustments I implemented.
i Turbine Impulse pressure and Tref were rescaled to Rated Thermal Power with '
Tavg equal to Tref where current values were greater than one-half of allowable tolerances of the current scaling.
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