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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20212F8831999-09-21021 September 1999 Application for Amend to License NPF-42,proposing to Modify Effective Full Implementation Date for Amend 120 from 991231 to 000630 ML20209D3561999-07-0808 July 1999 Application for Amend to License NPF-42 to Revise 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.Se & Nshc,Encl ML20209C2001999-06-30030 June 1999 Application for Amend to License NPF-42 for Temporary Change to CTS Without Action to Reduce Power ML20195G0211999-06-11011 June 1999 Application for Amend to License NPF-42,revising TS 3.7.1.6 & Associated Bases.Proposed Change Would Modify LCO to Require Four ARVs to Be Operable;Eliminate Use of Required in Action Statements;Add New Action for Three or More ARVs ML20195F7801999-06-10010 June 1999 Application for Amend to License NPF-42,proposing to Revise 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) ML20207L0401999-03-0505 March 1999 Suppl 1 to 970515 Application for Amend to License NPF-42 Incorporating Changes to WCGS TSs & Adding License Conditions to Address Surveillance Requirements.Suppl Submits Mods Submitted to NRC During Review Process ML20199G7211999-01-15015 January 1999 Application for Request of Partial Issuance of Amend to License NPF-42,proposing TS SR Be Revised to Delete During SD Requirement & Reflect Appropriate Plant Conditions in Associated 3/4.7.3 Bases ML20199F4411999-01-12012 January 1999 Application for Amend to License NPF-42,to Revise 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 ML20198P1161998-12-29029 December 1998 Application for Amend to License NPF-42,revising Tech Specs to Incorporate Revised RCS Heatup & Cooldown Limit Curves & Revised Cold Overpressure Mitigation Sys (COMS) PORV Setpoint Limit Curve ML20195E5421998-11-10010 November 1998 Suppl Application for Amend to License NPF-42,transferring Control of Kg&E & Kansas Power & Light Possessory Ownership Interests to Westar Energy,Inc ML20155C4481998-10-26026 October 1998 Application for Amend to License NPF-42,transferring Kansas Gas & Electric Co & Kansas City Power & Light Co Interest in Operating Subject License for WCGS & Reflecting Transfer of Ownership ML20154S5651998-10-23023 October 1998 Application for Amend to License NPF-42,revising TS 3.5.1 by Increasing AOT in Action B. to 24 Hours in Lieu of Current AOT of One Hour ML20236R4711998-07-17017 July 1998 Application for Emergency Amend to License NPF-42 Revising TS 3/4.7.5, UHS, by Adding New Action Statement ML20247F8551998-05-0808 May 1998 Application for Amend to License NPF-42,revising TS 3/4.3.2, Table 3.3-3,ESF Actuation Sys Instrumentation ML20216J8151998-03-20020 March 1998 Application for Amend to License NPF-42,increasing Spent Fuel Storage Capacity & Max Nominal Fuel Enrichment to 5.0 W/O (Nominal Weight Percent) U-235.Proprietary & non-proprietary Holtec Repts,Encl.Proprietary Encl Withheld ML20202D1171998-02-0404 February 1998 Application for Amend to License NPF-42,revising TS 3/4.2.4, Quadrant Power Tilt Ratio & Associated Bases, to Clarify Required Actions for Limiting LCO & Other Change Consistents W/Ts Conversion Application Previously Submitted ML20202C4501998-02-0404 February 1998 Application for Amend to License NPF-42,revising Tech Specs 3/4.3, Changes to ESFAS Functional Units 6.f,8.a & 8.b ML20199H3431998-01-28028 January 1998 Application for Amend to License NPF-42,revising TS 6.3 & 6.12 to Reflect Position Change within Organization ML20198Q4321997-11-0606 November 1997 Application for Amend to License NPF-42,revising TS Sections 3/4.8.1,3/4.8.2 & 3/4.8.3 Re Installation of Spare Battery Chargers ML20217K2121997-10-17017 October 1997 Application for Amend to License NPF-42,revising TS Surveillance Requirements 4.5.2b & Associated Bases Re Requirement to Vent ECCS Pump Casings ML20216F7121997-09-0606 September 1997 Application for Amend to License NPF-42,alleviating Need for Enforcement Discretion Granted by NRC on 970905 ML20216D1471997-09-0202 September 1997 Application for Amend to License NPF-42,adding Requirements for Essential Svc Water Flowpaths to Turbine-Driven Auxiliary Feedwater Pump ML20196J3991997-07-29029 July 1997 Application for Amend to License NPF-42,revising Wording of Action Statement 5a to TS Table 3.3-1, Reactor Trip Sys Instrumentation ML20141G7641997-07-0303 July 1997 Application for Amend to License NPF-42,incorporating Addl Info Into TS 6.9.1.9, Colr ML20141F4361997-05-15015 May 1997 Application for Amend to License NPF-42,requesting Approval of Full Conversion of TS from Current to Set Based Upon Improved Std Ts,Per NUREG-1431 ML20138B9011997-04-23023 April 1997 Application for Amend to License NPF-42,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 Core Alterations ML20137X3211997-04-15015 April 1997 Suppl to Application for Amend to License NPF-42,requesting TS 6.8.5.b, Reactor Coolant Pump Flywheel Insp Program ML20147F8121997-03-21021 March 1997 Application for Amend to License NPF-42,revising Tech Specs 6.8.5b Re Reactor Coolant Pump Flywheel Insp Program to Provide Exception to Exam Requirements in Reg Guide 1.14,Rev 1, Reactor Coolant Pump Flywheel Integrity ML20137B9311997-03-18018 March 1997 Application for Amend to License NPF-42,revising TS Section 5.3.1,fuel Assemblies to Allow Use of Alternate Zr Based Fuel Cladding Matl ZIRLO ML20137B8971997-03-18018 March 1997 Application for Amend to License NPF-42,revising TS SR 4.5.2.c to Clarify When Containment Entry Visual Insp Is Required ML20134Q0701997-02-17017 February 1997 Application for Amend to License NPF-42,revising TS 1.7, Containment Integrity, TS 3/4.6.1, Containment Integrity & TS 3/4.6.3, Containment Isolation Valves ML20132G9821996-12-20020 December 1996 Application for Amend to License NPF-42,requesting Rev to Bases for TS 3.8.1.1 Re Electrical Power Systems - AC Sources ML20135D8411996-12-0303 December 1996 Application for Amend to License NPF-42,requesting Rev to TS 6.8.5b Re Reactor Coolant Pump Insp Program ML20135D9781996-12-0303 December 1996 Application for Amend to License NPF-42,changing TS Table 3.3-3 to Correct Ref to Applicable Action Statement for Item 7.b,RWST Level - Low-Low Coincident W/Safety Injection ML20112A5471996-05-16016 May 1996 Application for Amend to License NPF-42,revising Tech Spec Surveillance Requirements 4.7.6.e.4 to Reflect Proposed Design Change to Output Rating of Charcoal Filter Adsorber Unit Heater in Pressurization Sys Portion CREVS ML20108C8191996-05-0101 May 1996 Application for Amend to License NPF-42,revising TS Section 6.0 to Reflect Position Title Changes within WCNOC Organization ML20101B0201996-03-0808 March 1996 Application for Amend to License NFP-42,revising TS Figure 2.1-1, Reactor Core Safety Limit - Four Loops in Operation, Table 2.2-1, RTS Instrumentation Setpoints, & Table 3.2-1, DNB Parameters ML20097D3281996-02-0808 February 1996 Application for Amend to License NPF-42,revising TS 3/4.6.1.1, Containment Integrity, TS 6.8.4i, Containment Air Locks & Adding TS 6.8.4i, Containment Leakage Rate Testing Program ML20097D3081996-02-0808 February 1996 Application for Amend to License NPF-42,revising TS 3.9.4 Re Containment Bldg Penetrations ML20099L7061995-12-20020 December 1995 Application for Amend to License NPF-42,revising TSs 3/4.6.1.1 & 3/4.6.1.3 to Incorporate Option B of 10CFR50,App J ML20095F8711995-12-13013 December 1995 Application for Amend to License NPF-42,revising TS Surveillance Requirement 4.1.3.1.3 to Delete Requirement for Performing Control Rod Drop Surveillance Test W/Tavg Greater than 551 F.Proprietary SE Encl.Se Withheld ML20095F0071995-12-13013 December 1995 Application for Amend to License NPF-42,revising Minimum & Maximum Flow Requirements for Centrifugal Charging & SI Pumps Specified in TS SR 4.5.2.h ML20095F9371995-12-13013 December 1995 Application for Amend to License NPF-42,revising TSs 3/4.8.2.1,3/4.8.2.2,3/4.8.3.1 & 3/4.8.3.2 Re Electrical Power Sys Dc Sources & Onsite Power Distribution ML20094P0591995-11-22022 November 1995 Application for Amend to License NPF-42,revising TS 3/4.3.1 to Reflect Deletion of Boron Dilution Mitigation Sys ML20094P0691995-11-22022 November 1995 Application for Amend to License NPF-42,revising TS 3.9.4 & Bases Section to Allow Containment Personnel Airlock Doors to Be Open During Core Alterations & Movement of Irradiated Fuel in Containment & TS 4.9.4 ML20094B3661995-10-24024 October 1995 Application for Amend to License NPF-42,revising TS SR 4.7.6.c,d & E to Reflect Proposed Design Change to Output Rating of Charcoal Filter Adsorber Unit Heater in Pressurization Sys of CR Emergency Ventilation Sys ML20093K6491995-10-18018 October 1995 Application for Amend to License NPF-42,replacing Current Fuel Oil Vol Requirement in EDG Day Tank in TS 3.8.1.1.b.1 & 3.8.1.2.b.1 W/ Fuel Oil Level Requirement ML20092J4071995-09-15015 September 1995 Application for Amend to License NPF-42,revising TS 3/4.8.1, Electrical Power Sys - AC Sources & Associated Bases, Proposing That Guidance of RG 1.9,Rev 3,GL 93-05 & 94-01 Be Adopted ML20092F5831995-09-14014 September 1995 Application for Amend to License NPF-42,revising TS 3/4.5.5, ECCS - RWST to Increase AOT of RWST for Adjustment of Boron Concentration from One H to Eight H ML20091K7851995-08-22022 August 1995 Application for Amend to License NPF-42,revising TS to Relocate Instrumentation Response Time Limits 1999-09-21
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217D9751999-10-12012 October 1999 Amend 128 to License NPF-42,increasing Allowable Values for Engineered Safety Features Actuation Sys loss-of-power 4 Kv Undervoltage Trips in Table 3.3-4 & in SR 3.3.5.3 ML20212F8831999-09-21021 September 1999 Application for Amend to License NPF-42,proposing to Modify Effective Full Implementation Date for Amend 120 from 991231 to 000630 ML20210T0271999-08-12012 August 1999 Amend 127 to License NPF-42,revising TS 3.7.1.6,SG Atmospheric Relief Valves & Associated Bases to Require Four Atmospheric Relief Valves to Be Operable ML20210T0001999-08-0909 August 1999 Amend 126 to License NPF-42,revising TS Table 3.3-4, Functional Unit 7,b.,Automatic Switchover to Containment Sump to Reflect Results of Calculations Performed for Associated Instrumentation Setpoints ML20209G2771999-07-0808 July 1999 Amend 125 to License NPF-42,revising TS 3/4.7.5 by Adding New Action Statement to Be Used in Event That Plant Water Temp Exceeds 90 Degrees ML20209D3561999-07-0808 July 1999 Application for Amend to License NPF-42 to Revise 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.Se & Nshc,Encl ML20209C2001999-06-30030 June 1999 Application for Amend to License NPF-42 for Temporary Change to CTS Without Action to Reduce Power ML20195G0211999-06-11011 June 1999 Application for Amend to License NPF-42,revising TS 3.7.1.6 & Associated Bases.Proposed Change Would Modify LCO to Require Four ARVs to Be Operable;Eliminate Use of Required in Action Statements;Add New Action for Three or More ARVs ML20195F7801999-06-10010 June 1999 Application for Amend to License NPF-42,proposing to Revise 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) ML20206D4421999-04-27027 April 1999 Amend 124 to License NPF-42,revising TS 3/4.5.1, ECCS - Accumulators, by Increasing Allowed Outage Time with One Accumulator Inoperable for Reasons Other than Boron Concentration Deficiencies from 1 Hour to 24 Hours ML20205G1541999-03-31031 March 1999 Amend 123 to License NPF-42,converting CTSs for WCGS to Itss.Overall Objective of Proposed Amend Was to Rewrite, Reformat & Streamline CTS to Improve Safety & Understanding of Bases Underlying TSs ML20205B7671999-03-23023 March 1999 Amend 121 to License NPF-42,revising TS Tables 3.3-3,3.3-4 & 4.3-2 Requirements by Establishing Separate Requirements for Analog & Digital Portions of Associated Circuit ML20205B7001999-03-23023 March 1999 Amends 122 to License NPF-42,revising TS 4.7.3b, Plant Sys - Component Cooling Water Sys - Srs, by Deleting Requirement to Perform Specified Surveillances During Shutdown ML20205B8161999-03-22022 March 1999 Amend 120 to License NPF-42,revising TS to Support Mod to Plant to Increase Nominal Fuel Enrichment to 5% Percent Weight Percent U-235 ML20207L0401999-03-0505 March 1999 Suppl 1 to 970515 Application for Amend to License NPF-42 Incorporating Changes to WCGS TSs & Adding License Conditions to Address Surveillance Requirements.Suppl Submits Mods Submitted to NRC During Review Process ML20199G7211999-01-15015 January 1999 Application for Request of Partial Issuance of Amend to License NPF-42,proposing TS SR Be Revised to Delete During SD Requirement & Reflect Appropriate Plant Conditions in Associated 3/4.7.3 Bases ML20199F4411999-01-12012 January 1999 Application for Amend to License NPF-42,to Revise 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 ML20198P1161998-12-29029 December 1998 Application for Amend to License NPF-42,revising Tech Specs to Incorporate Revised RCS Heatup & Cooldown Limit Curves & Revised Cold Overpressure Mitigation Sys (COMS) PORV Setpoint Limit Curve ML20195E5421998-11-10010 November 1998 Suppl Application for Amend to License NPF-42,transferring Control of Kg&E & Kansas Power & Light Possessory Ownership Interests to Westar Energy,Inc ML20155C4481998-10-26026 October 1998 Application for Amend to License NPF-42,transferring Kansas Gas & Electric Co & Kansas City Power & Light Co Interest in Operating Subject License for WCGS & Reflecting Transfer of Ownership ML20154S5651998-10-23023 October 1998 Application for Amend to License NPF-42,revising TS 3.5.1 by Increasing AOT in Action B. to 24 Hours in Lieu of Current AOT of One Hour ML20151U0181998-08-31031 August 1998 Errata to Amend 119 to License NPF-42.Overleaf Page B 3/4 5- 2 Did Not Reflect Most Current Amend,Due to Administrative Error.Overleaf Page Also Provided to Maintain Document Completeness ML20236U8061998-07-21021 July 1998 Amend 119 to License NPF-42,adding New Action Statement to TS 3.5.1 Which Provides 72-hr AOT for One Accumulator to Be Inoperable Because Boron Concentration Did Not Meet 2300-2500 Parts Per Million Band ML20236S2071998-07-18018 July 1998 Amend 118 to License NPF-42,revising TS 3/4.7.5, Ultimate Heat Sink by Adding New Action Statement to Be Used in Event That Plant Inlet Water Temp Exceeded 90 F ML20236R4711998-07-17017 July 1998 Application for Emergency Amend to License NPF-42 Revising TS 3/4.7.5, UHS, by Adding New Action Statement ML20248D3841998-05-28028 May 1998 Amend 117 to License NPF-42,adding New Action Statement to TS 3/4.3.2,Table 3.3-3,Functional Unit 7.b., Refueling Water Storage Tank Level - Low-Low Coincident W/Safety Injection ML20247F8551998-05-0808 May 1998 Application for Amend to License NPF-42,revising TS 3/4.3.2, Table 3.3-3,ESF Actuation Sys Instrumentation ML20217K7991998-04-27027 April 1998 Amend 116 to License NPF-42,revising TS 3.2.4 & Associated Bases Re Quadrant Power Tilt Ratio ML20217J9801998-03-30030 March 1998 Amend 115 to License NPF-42,revising TS Sections 6.3 & 6.12 to Reflect Merger for Positions of Superintendent Radiation Protection & Superintendent Chemistry Into One New Position, Manager Chemistry/Radiation Protection ML20216J8151998-03-20020 March 1998 Application for Amend to License NPF-42,increasing Spent Fuel Storage Capacity & Max Nominal Fuel Enrichment to 5.0 W/O (Nominal Weight Percent) U-235.Proprietary & non-proprietary Holtec Repts,Encl.Proprietary Encl Withheld ML20203M6001998-02-27027 February 1998 Corrected Amend 101 to License NPF-42.Rev Due to Administrative Error Consisting of Omitted Sentence from TS Pp 6-18b That Should Have Been Included as Part of Amend 89 ML20202D1171998-02-0404 February 1998 Application for Amend to License NPF-42,revising TS 3/4.2.4, Quadrant Power Tilt Ratio & Associated Bases, to Clarify Required Actions for Limiting LCO & Other Change Consistents W/Ts Conversion Application Previously Submitted ML20202C4501998-02-0404 February 1998 Application for Amend to License NPF-42,revising Tech Specs 3/4.3, Changes to ESFAS Functional Units 6.f,8.a & 8.b ML20199H3431998-01-28028 January 1998 Application for Amend to License NPF-42,revising TS 6.3 & 6.12 to Reflect Position Change within Organization ML20198Q4321997-11-0606 November 1997 Application for Amend to License NPF-42,revising TS Sections 3/4.8.1,3/4.8.2 & 3/4.8.3 Re Installation of Spare Battery Chargers ML20199B1931997-11-0303 November 1997 Amend 114 to License NPF-42,revising TS 4.5.2b & Associated Bases to Eliminate Requirement to Vent Centrifugal Charging Pump Casings ML20212F5311997-10-20020 October 1997 Amend 113 to License NPF-42,revising Surveillance Requirements 4.3.1.2 & 4.3.2.2,TS 3/4.3.1 & 3/4.3.2 & Associated Bases of Sections B 3/4.3.1 & B 3/4.3.2 to Eliminate Periodic Response Time Testing Requirements ML20217K2121997-10-17017 October 1997 Application for Amend to License NPF-42,revising TS Surveillance Requirements 4.5.2b & Associated Bases Re Requirement to Vent ECCS Pump Casings ML20217G7041997-10-0707 October 1997 Amend 112 to License NPF-42,allowing Test of Certain Contacts in EDG Load Sequencer to Be Done W/Unit at Power (Mode I) & Providing Addl 24 Hrs to Time Allowed by TS 4.0.3 to Complete Testing ML20217D9161997-09-29029 September 1997 Amend 111 to License NPF-42,changing Wording of Action Statement 5a to TS Table 3.3-1, Reactor Trip Sys Instrumentation ML20217E3121997-09-22022 September 1997 Amend 110 to License NPF-42,modifying TSs 5.3.1, Fuel Assemblies, & 6.1.9.6, COLR, to Add ZIRLO as Fuel Matl & Use of Limited Zirconium Alloy Filler Rods in Place of Fuel Rods ML20216F7121997-09-0606 September 1997 Application for Amend to License NPF-42,alleviating Need for Enforcement Discretion Granted by NRC on 970905 ML20216D1471997-09-0202 September 1997 Application for Amend to License NPF-42,adding Requirements for Essential Svc Water Flowpaths to Turbine-Driven Auxiliary Feedwater Pump ML20196J3991997-07-29029 July 1997 Application for Amend to License NPF-42,revising Wording of Action Statement 5a to TS Table 3.3-1, Reactor Trip Sys Instrumentation ML20149E8631997-07-11011 July 1997 Amend 107 to License NPF-42 Revising TS to Allow Svc Air & Breathing Air Containment Penetrations to Remain Open Under Administrative Control During Periods of Core Alterations or Movement of Irradiated Fuel Inside Containment ML20141G7641997-07-0303 July 1997 Application for Amend to License NPF-42,incorporating Addl Info Into TS 6.9.1.9, Colr ML20141D9741997-06-24024 June 1997 Amend 106 to License NPF-42,revising TS 6.8.5.b to Provide Exception to Exam Requirements of RG 1.14,rev 1, RCP Flywheel Integrity, & Delays Insp of D RCP Flywheel to Fall 1997 Refueling Outage ML20148E0111997-05-28028 May 1997 Amend 105 to License NPF-42,reducing Containment Visual Insp Frequency,When Containment Integrity Is Required,From Every Entry to Once Per Day & During Final Entry ML20141F4361997-05-15015 May 1997 Application for Amend to License NPF-42,requesting Approval of Full Conversion of TS from Current to Set Based Upon Improved Std Ts,Per NUREG-1431 ML20138B9011997-04-23023 April 1997 Application for Amend to License NPF-42,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 Core Alterations 1999-09-21
[Table view] |
Text
KANSAS GAS AND ELECTRIC COMPANY THE ELECTAC COMPANY GLENN L ROESTER vect.nt srosmt. muctaan Decerber 6, 1985 Mr. Harold R. Denton, Director Office of lbclear Reactor Regulation U.S. Ibclear Regulatory Comission h'ashington, D.C.
20555 KML?EC 85-264 RE:
Docket No. STN 50-482 SUBJ: Revision to Technical Specification 3/4.6.1.6
Dear Mr. Denton:
The ptrpose of this letter is to transmit three (3) original and forty (40) conformed copies of an application for Ahendment to Facility Operating License No. NPF-42 for Wolf Creek Generating Station, Unit No. 1.
This application requests that Section 3/4.6.1.6, Containment Vessel Structural Integrity, of the Wolf Creek Generating Station
'Ibchnical Specifications be revised.
This application for amendment revises ACTION b.
and adds ACTION c.
and d.
associated with Technical Specification 3.6.1.6, and revises surveillance 4.6.1.6.1.e.l.
The AcrION Statement rewording assures acceptable design margins for the life of the plant.
The revision to the surveillance eliminates the requirement for precise verification of the percent voids present in tendon sheathing filler grease.
A conplete Safety Evaluation and Significant Hazards Consideration are provided as Attachments I and III respectively.
{$
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I 8512130362 851206 PDR ADOCK 05000482 P
PDR 201 N. Market -Wduta, Kansas - Mail Address: RO. Box 208 I Wichita, Kansas 67201 - Telephone: Area Code (316) 261-6451 L
.6.r. H.R. Denton KMLNRC 85-264 Page 2 Decenber 6, 1985 In accordance with 10 CFR 50.91, a copy of this application, with Attachments is being provided to the designated Kansas State Official.
Enclosed is a check for the $150.00 application fee required by 10 CPR 170.21.
If you have any glestions concerning this matter, please contact ne or Mr. O.L. Maynard of my staff.
Very truly yours, W
Glenn L. Koester Vice President - Nuclear G M:see Enclosure Attachments: I -Safety Evaluation II -Initial Fill Void Factors III-Significant Hazards Consideration IV -Marked Tech. Spec, pages 3/4 6-8 and 3/4 6-9 cc: P0'Connor (2) w/a JCummins w/a G ulen w/a FJohnson w/a
SmTE & KANSAS )
)
SS CITY T WICHITA )
Glenn L. Koester, of lawful age, being first duly sworn upon oath says that he is Vice President - Wclear and an Officer of Kansas Gas and Electric Conpany; that he has read the foregoing document and knows the content thereof; that he has executed that same for and on behalf of said Conpany with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By
'Glenn L. Koester Vice President - Nulcear SUBSCRIBED and sworn to before me this ([" day of M t, 1985.
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Expiration Date 1 M
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Mr. H.R. Denton Attachment I to KMIRRC 85-264 Page 1 of 3 SAFE'IY EVALUATION This anendment requests the rewording of ACTION b.
and the addition of ACTIONS c.
and d.
to Specification 3.6.1.6 and the revision of surveillance Specification 4.6.1.6.1.e.l.
The existing ACTION b.
requires that whenever any element of the tendon surveillance acceptance criteria is not satisfied, it be considered as evidence of abnormal degradation of the structural integrity of the Containment vessel requiring that the integrity be restored or that the plant be shutdown. The proposed amendment, however, would classify a failure to satisfy an element of the acceptance criteria as evidence of possible abnormal degradation and would permit an evaluation to be performed demonstrating the continued ability of the Containment Vessel Structure to perform its design function. The proposed amendment still provides pronpt action for the plant to be shutdown if the engineering evaluation does not denonstrate Containment integrity.
The addition of ACTION c. provides for timely evaluation and correction of those parameters which in thenselves do not indicate abnormal-degradation but which may allow future degradation if not corrected.
This ACTION also provides a report to the Cocmission describing the condition and action taken.
The inclusion of an exemption from the provisions of Specification 3.0.4 by adding ACTION d.
reduces the inpact on plant operation consistent with the allowable times contained in ACTION a.
and ACTION b.
The revision to 4.6.1.6.1.e.1 changes the requirement to verify the operability of the sheathing filler grease by assuring that there are no voids in excess of 5% of the net duct volume to the requirement to assure that widespread grease leakage has not occurred. The tendons at Wolf Creek were initially greased between February and Septecber,1982, by Inryco using current industry standard filling procedures.
These procedures did not require recording the amount of grease injected into each sheath nor did they require verificaton that there were less than 5% voids.
At that time, Kansas Gas and Electric was conmitted to Reg.
Gilde 1.35, Rev. 2, which deals only with voids in the trunpet area and not in the entire sheath.
Revision 4 of Westinghouse Standard Technical Specifications, from which Wolf Creek made its original submittal, makes no mention of void measurement.
The only method to accurately determine voids in the grease which "could be indicative of leakage in the tendon-duct system" is to assume the sheath was
i 4
Mr. H.R. Denton Attachment I to KMLNRC 85-264 Page 2 of 3 1
coupletely filled initially.
Attachment II shows that even under cptinum filling conditions.
volds of approximately 15% could be expected after the initial filling operation using current filling techniques.
Therefore, the requirement for verification of less than 5% voids in not meaningful for 21f Creek and should be deleted.
1 The filling technique required -to assure that the tendon sheaths are initially 100% full of filler grease involves repeated filling of the i
sheath and allowing of the grease to cool.
This can lead to gasket i
failures and leakage of the grease due to grease expansion during the sunner months.
The Elf Creek first year tendon surveillance is scheduled to be 1
performed beginning in Decenter 1985.
Uhder the current Technical Specification requirements of assuring no voids in excess of 5% of the net duct volume, it is necessary to regrease the tendons involved to i
determine the percentage of voids.
This operation is considered to be unnecessary in view of the arguments presented herein and 4= = = an unnecessary burden especially in view of the difficulty of punping grease during the winter months.
Prevention of corrosion of the tendons is assured by coating adequately the tendon wires and the anchorage cwp ents.
The material used in.
the 21f Creek post-tensioning
- system, Visconorust 2090 N,
acconplishes its corrosion protection function by the filler material's affinity to adhere to steel structures, its -ability to enulsify any moisture in the system nullifying its rusting ability, and 1
by its resistance to moisture, mild acids, and alkalis.
As long as sufficient grease has been introduced into the system to coat the wires i
and anchorages completely, corrosion protection is assured. Protection j
is also afforded by each tendon wire being individally pre-coated with Anber 1601 prior to installation.
The degree,of filling the interstitial spaces, which conprise the. net duct volume, is not i
directly related to the degree of coating which occurs and, 1
consequently, is not of significant inportance as an indicator of
. operability of the sheathing filler material.
Test data from the Callaway Plant, which has the identical containment as W lf Creek, and other plants with longer operating history have failed to show any correlation between the amount of voids and tendon strength -failures.
Results of the initial tendon surveillance at
~
- Callaway, which are discussed in Ohion Electric letters to the IRC, i
UIJmC-1172 dated Septenber 12, 1985 and UIJEC-ll73 dated September 18, i
- 1985, show that tendons requiring net refill volumes of the filler material in excess of the acceptance criteria have not shown any j
abnormal deterioration or degradation of strength. The lift-off forces L
for those tendons, as well as the other surveillance tendons, have been j
found to fall within (or above) the predicted limits. Examination and testing of the individual wires at Callaway has revealed that there is
Mr. H.R. Denton Attachment I to KMLNRC 85-264 Page 3 of 3 no eviden of corrosion and that the wire strength exceeds the mininum required ultimate strength throughout the wires.
Examination of the filler material has shown virtually no change in the physical appearance or chemical properties.
'Ibst results indicate that the amount of chlorides, sulfides, nitrates, and moisture fall far below the maxinum allowed limits as specified by the manufacturer.
Visual inspection of the different conponents of the anchorage system revealed proper coverage by the filler material with no signs of corrosion or presence of water.
In accordance with the reconnendations of Regulatory Guide 1.35, proposed Rev.
3, a visual examinati>n of the exterior surfaces of the containment will be made at the beginning of the surveillance to. detect areas of widespread cracking,
- spalling, or grease leakage.
Additionally, if the presence of significant voids in the grease coverage is detected during surveillance operations or during grease replacement, the tendons will be regreased.
Based on the above discussion, the first surveillance at Callaway, and the evaluation of results from other plants, this amendment to Technical Specification 3/4.6.1.6 will not adversely affect the structural integrity of the containment vessel nor will it endanger the health and safety of the general public.
This amendnent does not involve significant safety hazard as discussed in Attachment III.
Mr. H.R. Denton Attachment II to KMLNRC 85-264 Page 1 of 1 INITIAL FILL VOID FAC'IORS Voids in the tendon sheathing may be attributed to a nunber of additive factors:
- 1) Visconorust 2090P-4 has a coefficient of expansion which yields an expansion of about 1% per every 20 F.
Initial filling tenperatures of the filler material can average 160 F.
Cold weather conditions can cool the filler material to 40 F,
giving a contraction of 6% of the net duct volume.
- 2) Calculated voids between the wires which cor: prise the tendon bundle are aproximately 7% of the net duct volume. If during the initial filling operations the tendon bundle is cold (anbient tenperature of 65 F.) and, as the filler material is punped into the sheathing
- void, it solidifies on the surface of the tendon bundle, small voids will be left between the wires.
As the filler material gradually heats the tendon bundle during tendon surveillance, it is likely that the voids between the wires allow migration of the filler s terial into the tendon bundle.
In addition, this type of migration could also occur at other areas such as where tendons are in contact with the sheathing.
- 3) Characteristics of the initial filling method may induce air entraFaent into the filler material.
Punping operations can introduce air into filler material and may add up to as noch as 2%
of the net duct volume.
This void value could be higher for horizontal tendons due to the lower punping head used when conpared to the vertical tendons.
In
- sunmary, even under optinum filling conditions, voids of approximately 15% could be expected after the initial filling operations.
Mr. H.R. Denton Attachment III of KMLNRC 85-264 Page 1 of 2 SIGNIFICANT HAZARDS CONSIDERATION This amendment request revises AcrION b.
and adds ACTION c.
and d.
associated with Technical Specification 3.6.1.6, and revises surveillatce 4.6.1.6.1.e.l.
The ACTION statement rewording assures that there are acceptable design margins for the life of the plant while eliminating the need to shutdown the plant or maintain the plant shutdown when it can be shown by an engineering evaluation that the nonconforming parameters do not degrade containment integrity.
The revision to the surveillance eliminates the requirements for precise verification of a parameter that cannot be accurately determined and has adequate backup surveillance parameters to assure acceptable design margins are maintained throughout plant life.
The Safety Evaluation submitted with this application provides Kansas Gas and Electric's bases for concluding that the Wolf Creek Generating Station can be safely operated consistent with the revised action statement.
In evaluating the increase in probability or consequences of any previously analyzed accident, the following areas were considered:
1.
Desion Conservat4am The Containment vessel post tensioning system is a passive element designed to provide a mininum level of pre-stress of 1.2 x the design accident pressure at the end of the 40 year design life of the plant. As such, there is a wide margin of safety at the beginning of_ the plant life which decreases to a mininum value of 1.2 at 40 years.
2.
Surwillance Precuency Periodic tendon surveillances are required by Reg. Guide 1.35.
The first three surveillances occur at 1.0, 3.0 and 5.0 years after the structural integrity test, and surveillances are required every five years thereafter.
The length of the intervening period of 5 years between successive surveillances is evidence of the recognition of the extreme inprobability of the deterioration of the post tensioning system to a level where vessel integrity would be affected in this time period.
As such, there is not basis for the requirement for restoration or shutdown within the time periods given in the Technical Specification.
3.
Surveillance Results During the initial inservice tendon surveillance at the Callaway
- Plant, it was discovered that net refill volumes of sheathing filler material (grease) exceeded 5 percent of the net duct volume
~
Mr. H.R. Denton Attachment III to P:MLNRC 85-264 Pay 2 of 2 for several tendons.
These results for the affected tendons suggest that those tendon sheaths were not totally filled with
- grease, due to the initial fill void factors discussed in Attachment II and since volume control techniques were not used (or required) during initial filling.
The above incidences, involving net refill grease volumes in excess of the acceptance criteria, did not affect the strength of the Callaway tendons.
Lift-off forces for the surveilled tendons were found to lie within (or above) predicted limits indicating
- that, among other things, wire integrity was not degraded.
Examination and testing of individual wires from the tendons revealed that there was no evidence of wire corrosion and that wire strength was not degraded.
Examination of the grease itself revealed that there were no changes in the presence (at the anchorage) or physical appearance of the grease and the chemical properties were verified by laboratory analysis.
As evidenced by examination of the surveillance tendons, the detected underfill conditions did not affect the ability of the grease to provide minimum coverage for the different parts of the anchorage system.
Additionally, data gathered from other plants with more operating history than Callaway have failed to show any correlation between percent voids and lift-off force or tensile strength failures.
Based on the above discussions, this change does not involvu a significant increase in the probability or consequences of an accident previously evaluated.
The propsed change to the Specification:
will not inpact tendon integrity since tendon integrity will be assured by surveillance of remaining parameters and restoration of parameters or assurance by engineering evaluation; ~ will not affect the method and manner of plant operation; and will not affect conponents and equipment inportant to l
safe operation. Therefore, the proposed amendment does not create the possibility of a new and different accident from any previously evaluated.
The surveillances and actions requested provide assurance that any tendon degradation would be identified and corrected in a timely manner consistent with the indicators, and, therefore, this change does not involve any reduction in a margin of safety.
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