Letter Sequence Other |
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MONTHYEARML20059B0841993-12-22022 December 1993 Forwards RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, Per 10CFR50.54(f) for Plant.Requests Addl Info on Configurations & Amounts of Thermo-Lag Fire Barriers Installed in Plant & Cable Loadings Project stage: RAI ML20073R9971994-02-0909 February 1994 Forwards Response to NRC 931222 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers Project stage: Other ML20070G7081994-07-15015 July 1994 Responds to Request for Addl Info Re GL 92-08,Thermo-Lag 330-1 Fire Barriers,Issued on 941222 Project stage: Request ML20078S7891994-12-22022 December 1994 Responds to 940923 Request for Addl Info Re GL 92-08 Concerning Thermo-Lag Fire Barrier Protection Sys Project stage: Request ML20086A6481995-06-27027 June 1995 Forwards Suppl Response to NRC 941229 follow-up to RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers & Rept from Nucon Intl,Inc, Pyrolysis Gas Chromatography Analysis of 5 Thermo-Lag Fire Barrier Samples Project stage: Other ML20137C2081997-03-20020 March 1997 Ack Completion of Licensing Action of GL 92-08, Thermo-Lag 330-1 Fire Barriers, & Requests to Retain All Documentation Related for Future NRC Audits & Insp Project stage: Other 1994-02-09
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Category:CORRESPONDENCE-LETTERS
MONTHYEAR05000482/LER-1999-002, Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl 05000482/LER-1994-014, Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl1999-10-15015 October 1999 Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl ML20217F7481999-10-14014 October 1999 Informs That Based on Approval of Core Assessment Damage Guidance in WCAP-14696,rev 1 for Westinghouse Nuclear Power Plants,Licensee May Use WCAP-14696,rev 1 at Wolf Creek Generating Station ML20217F8701999-10-13013 October 1999 Provides Summary of Meeting on 991007 with Representatives of Wolf Creek Nuclear Station in Burlington,Kansas Re Status of Licensee Radiation Protection Program.List of Meeting Attendees & Licensee Presentation Encl ML20217C1721999-10-0707 October 1999 Forwards Insp Rept 50-482/99-09 on 990830-0903.No Violations Noted.Purpose of Insp to Perform Routine Operational Status Insp of Emergency Preparedness Program & to Resolve Questions Re Revised Emergency Plan ML20217A4881999-09-29029 September 1999 Forwards Changes to Plant Data Point Library,Iaw 10CFR50,App E,Section VI.3.a.ERDS Point Affected Is RDS0001 ML20216H9291999-09-29029 September 1999 Informs That Licensee Responses to GL 97-06, Degradation of Steam Generator Internals Acceptable & Did Not Identify Any New Concerns with Condition of SG Intervals at Plant ML20212G1681999-09-24024 September 1999 Notifies NRC of Change in Status of Licensed Individual at Plant,Per 10CFR50.74.RL Acree Holds License OP-42654 at Plant,But Has Been Permanently Reassigned from Position for Which Plant Has Certified Need for RO License ML20216F9591999-09-22022 September 1999 Forwards Withdrawal of Amend Request Re Ultimate Heat Sink Temp for Wolf Creek Generating Station ML20212G5641999-09-20020 September 1999 Forwards Insp Rept 50-482/99-13 on 990725-0904.Three Violations Being Treated as Noncited Violations 05000482/LER-1999-011, Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I1999-09-17017 September 1999 Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I 05000482/LER-1999-010, Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util1999-09-16016 September 1999 Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util ML20212D9381999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of WCGS on 990818.Areas of EP & Engineering Warranted Increase in NRC Action.Nrc Plan to Conduct Add Insp Beyond Core Insp Program Over Next 7 Months to Address Listed Questions 05000482/LER-1999-006, Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl1999-09-15015 September 1999 Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl ML20212C9211999-09-15015 September 1999 Forwards NRC Form 536, Operating Licensing Examination Data, in Response to NRC Administrative Ltr 99-03 ML20216F1641999-09-14014 September 1999 Forwards Insp Rept 50-482/99-12 on 990816-20.No Violation Noted.Determined That Solid Radwaste Mgt & Radioactive Matls Transportation Programs Were Properly Implemented 05000482/LER-1999-009, Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER1999-09-10010 September 1999 Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER ML20212A5651999-09-10010 September 1999 Informs of Completion of Review of & Encl Objectives for Wolf Creek Generating Station 1999 Emergency Preparedness Exercise Scheduled for 991117.Determined Exercise Objectives Appropriate to Meet EP Requirements 05000482/LER-1999-008, Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER1999-09-0303 September 1999 Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER ML20211M7151999-09-0303 September 1999 Forwards Changes to Wolf Creek Generating Station Data Point Library.Emergency Response Data Sys Points Affected Are EJL0007 & EJL0008 ML20211N0081999-09-0202 September 1999 Informs That NRC Staff Has Reviewed Submittals & Concluded Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20211K8301999-09-0202 September 1999 Forwards marked-up TS Page Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band,Per 990708 Application to Amend License NPF-42 ML20211K1941999-08-31031 August 1999 Forwards Rev 31 to WCGS Physical Security Plan,Safeguards Contingency Plan & Training & Qualification Plan,Iaw 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20211H1491999-08-26026 August 1999 Forwards Insp Rept 50-482/99-16 on 990809-13.No Violations Noted.Insp Focused on Low as Is Reasonably Achievable Program,Training Program for Contract Radiation Protection Personnel & Radiation Protection QA Program ML20211A8581999-08-18018 August 1999 Forwards Insp Rept 50-482/99-08 on 990316-0724.One Violation Being Treated as Noncited Violation ML20211G2201999-08-17017 August 1999 Forwards Exam Rept 50-482/99-301 on 990726-29.Exam Evaluated Six Applicants for SO Licenses & Three Applicants for RO Licenses ML20210U0991999-08-13013 August 1999 Forwards Insp Rept 50-482/99-11 on 990712-16.No Violations Noted.Insp Was to Review Radiological Environ Monitoring Program ML20210U9751999-08-13013 August 1999 Informs That Licensee Identified That Answer Key for One Question on 990720 Written Exam & Event Classification for on Job Performance Measure Required Mod.Description & Justification for Proposed Mod,Including Technical Ref,Encl ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210R5621999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Revised Repts for Apr,May & June 1999,correcting Number of Hours Reactor Critical,Encl ML20210P7491999-08-0909 August 1999 Ack Receipt of ,Which Transmitted Wolf Creek Radiological Emergency Response Plan 06-002,Rev 0,under Provisions of 10CFR50,App E,Section V ML20210N0061999-08-0303 August 1999 Forwards Response to NRC 990401 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Motor-Operated Gate Valves ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210H2551999-07-29029 July 1999 Provides 180-day Response to NRC Request for Info Re GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210J1371999-07-29029 July 1999 Requests NRC Approval of Methodology for Determining RCS Pressure & Temp & Overpressure Mitigation Sys PORV Limits. Attachment I Provides Proposed Changes to Improved TS ML20210F5931999-07-27027 July 1999 Forwards semi-annual Fitness for Duty Performance Data Rept for Wcnoc,Per 10CFR26.71(d).Rept Covers Period of 990101- 0630 ML20210F5881999-07-23023 July 1999 Submits Response to Administrative Ltr 99-02, Operator Reactor Licensing Action Estimates, ML20210B8191999-07-20020 July 1999 Ack Receipt of ,Which Transmitted Wolf Creek EP Implementing Procedure 06-005,Rev 1.Implementation of Changes Will Be Subj to Insp to Confirm That Changes Does Not Decrease Effectiveness of EP ML20209H5411999-07-15015 July 1999 Forwards Insp Rept 50-482/99-07 on 990614-18.No Violations Noted.Insp Focused on Radiation Program During Normal Operating Conditions ML20209H0441999-07-14014 July 1999 Forwards Response to NRC 990326 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. Summary of Util Commitments Provided in Attachment 2 ML20209H0751999-07-14014 July 1999 Forwards Monthly Operating Rept for June 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Max Dependable Capacity Has Been Updated from 1163 to 1170,as Determined by Calculations Based on Capacity Test Results of July 1998 ML20209G9871999-07-14014 July 1999 Informs of Changes Affecting Wolf Creek Security Plan,Per 10CFR50.54(p)(2).Encl Provides Description of Changes & Justification for Changes ML20209E3581999-07-12012 July 1999 Discusses Util 980925 Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Wolf Creek Generating Station ML20209E0611999-07-0808 July 1999 Forwards Addl Pages to Rev 12 of USAR & Commitment Changes, Inadvertently Omitted from 990311 Submittal ML20196K8231999-07-0606 July 1999 Submits Kansas Electric Power Cooperative,Inc Ltr Pursuant to Commission Direction in Memo & Order CLI-99-19.Addresses Disposition of Existing Antitrust Conditions Attached to License for Wolf Creek Unit 1 Re Proposed License Transfer ML20209C6031999-07-0606 July 1999 Provides Applicants View as Result of 990618 Memo & Order Directing Parties to Address Proper Disposition of Existing Antitrust License Condition Attached to OL for Facility Due to Planned Changes in Ownership of Facility.With Svc List ML20196K0501999-07-0202 July 1999 Forwards Insp Rept 50-482/99-06 on 990502-0612.Three Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20209B7131999-07-0101 July 1999 Submits Response to NRC Request for Info Re GL 98-01, Suppl 1, Y2K Readiness of Computer Sys at Npps. Response on Status of Facility Y2K Readiness Was Requested by 990701.Disclosure Encl ML20209A7461999-06-29029 June 1999 Informs of Changes in Project Mgt Staff Assigned to Wcgs. Effective 990628,J Donohew Will Assume PM Responsibilities ML20209B5151999-06-29029 June 1999 Informs That Util Completed Analyses & Modifications to Address Items Discussed in GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions 1999-09-03
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR05000482/LER-1994-014, Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl1999-10-15015 October 1999 Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl 05000482/LER-1999-002, Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl ML20217A4881999-09-29029 September 1999 Forwards Changes to Plant Data Point Library,Iaw 10CFR50,App E,Section VI.3.a.ERDS Point Affected Is RDS0001 ML20212G1681999-09-24024 September 1999 Notifies NRC of Change in Status of Licensed Individual at Plant,Per 10CFR50.74.RL Acree Holds License OP-42654 at Plant,But Has Been Permanently Reassigned from Position for Which Plant Has Certified Need for RO License 05000482/LER-1999-011, Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I1999-09-17017 September 1999 Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I 05000482/LER-1999-010, Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util1999-09-16016 September 1999 Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util 05000482/LER-1999-006, Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl1999-09-15015 September 1999 Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl ML20212C9211999-09-15015 September 1999 Forwards NRC Form 536, Operating Licensing Examination Data, in Response to NRC Administrative Ltr 99-03 05000482/LER-1999-009, Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER1999-09-10010 September 1999 Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER 05000482/LER-1999-008, Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER1999-09-0303 September 1999 Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER ML20211M7151999-09-0303 September 1999 Forwards Changes to Wolf Creek Generating Station Data Point Library.Emergency Response Data Sys Points Affected Are EJL0007 & EJL0008 ML20211K8301999-09-0202 September 1999 Forwards marked-up TS Page Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band,Per 990708 Application to Amend License NPF-42 ML20211K1941999-08-31031 August 1999 Forwards Rev 31 to WCGS Physical Security Plan,Safeguards Contingency Plan & Training & Qualification Plan,Iaw 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20210U9751999-08-13013 August 1999 Informs That Licensee Identified That Answer Key for One Question on 990720 Written Exam & Event Classification for on Job Performance Measure Required Mod.Description & Justification for Proposed Mod,Including Technical Ref,Encl ML20210R5621999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Revised Repts for Apr,May & June 1999,correcting Number of Hours Reactor Critical,Encl ML20210N0061999-08-0303 August 1999 Forwards Response to NRC 990401 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Motor-Operated Gate Valves ML20210J1371999-07-29029 July 1999 Requests NRC Approval of Methodology for Determining RCS Pressure & Temp & Overpressure Mitigation Sys PORV Limits. Attachment I Provides Proposed Changes to Improved TS ML20210H2551999-07-29029 July 1999 Provides 180-day Response to NRC Request for Info Re GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210F5931999-07-27027 July 1999 Forwards semi-annual Fitness for Duty Performance Data Rept for Wcnoc,Per 10CFR26.71(d).Rept Covers Period of 990101- 0630 ML20210F5881999-07-23023 July 1999 Submits Response to Administrative Ltr 99-02, Operator Reactor Licensing Action Estimates, ML20209G9871999-07-14014 July 1999 Informs of Changes Affecting Wolf Creek Security Plan,Per 10CFR50.54(p)(2).Encl Provides Description of Changes & Justification for Changes ML20209H0441999-07-14014 July 1999 Forwards Response to NRC 990326 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. Summary of Util Commitments Provided in Attachment 2 ML20209H0751999-07-14014 July 1999 Forwards Monthly Operating Rept for June 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Max Dependable Capacity Has Been Updated from 1163 to 1170,as Determined by Calculations Based on Capacity Test Results of July 1998 ML20209E0611999-07-0808 July 1999 Forwards Addl Pages to Rev 12 of USAR & Commitment Changes, Inadvertently Omitted from 990311 Submittal ML20209C6031999-07-0606 July 1999 Provides Applicants View as Result of 990618 Memo & Order Directing Parties to Address Proper Disposition of Existing Antitrust License Condition Attached to OL for Facility Due to Planned Changes in Ownership of Facility.With Svc List ML20196K8231999-07-0606 July 1999 Submits Kansas Electric Power Cooperative,Inc Ltr Pursuant to Commission Direction in Memo & Order CLI-99-19.Addresses Disposition of Existing Antitrust Conditions Attached to License for Wolf Creek Unit 1 Re Proposed License Transfer ML20209B7131999-07-0101 July 1999 Submits Response to NRC Request for Info Re GL 98-01, Suppl 1, Y2K Readiness of Computer Sys at Npps. Response on Status of Facility Y2K Readiness Was Requested by 990701.Disclosure Encl ML20209B5151999-06-29029 June 1999 Informs That Util Completed Analyses & Modifications to Address Items Discussed in GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20196G9681999-06-22022 June 1999 Informs NRC That BC Ryan Will Be Leaving Ks State Univ for Position with Wolf Creek Nuclear Operating Corp,Effective 990701 05000482/LER-1999-007, Forwards LER 99-007-00,re Condition in Which Wolf Creek Generating Station TS 3.3.2 Was Not Met.Commitments Made by Util Also Encl1999-06-18018 June 1999 Forwards LER 99-007-00,re Condition in Which Wolf Creek Generating Station TS 3.3.2 Was Not Met.Commitments Made by Util Also Encl ML20196A0251999-06-17017 June 1999 Requests That Written Exams for Reactor Operator & SRO for Plant Be Administered Beginning Wk of 990719 & Followed by Operating Exam During Wk of 990726 to Personnel Listed in Attachment.Proprietary Info Encl.Proprietary Info Withheld ML20195K0641999-06-15015 June 1999 Forwards MOR for May 1999 for Wolf Creek Generating Station & Corrected Page 2 of 2 of Apr 1999 Mor,Adding That Unit Entered Intomode 5 for Restart During Month of Apr & Correcting Shutdown Duration Hours from 672 to 671 ML20195G4391999-06-11011 June 1999 Provides Details for Missed Rept Re 10CFR50.46 Thirty Day Rept of ECCS Model Revs.Attachment I Provides Summary of Commitments Made in Submittal 05000482/LER-1999-005, Forwards LER 99-005-00,re Esfa.Commitments Made by Util Are Encl1999-06-11011 June 1999 Forwards LER 99-005-00,re Esfa.Commitments Made by Util Are Encl 05000482/LER-1997-027, Forwards LER 97-027-00 Re Identification of Missed Surveillance Required by TS 4.3.3.5.2.Encl 1 Identifies Actions Committed to by Util1999-06-0404 June 1999 Forwards LER 97-027-00 Re Identification of Missed Surveillance Required by TS 4.3.3.5.2.Encl 1 Identifies Actions Committed to by Util ML20195B9811999-05-26026 May 1999 Forwards 1998 Annual Repts for Ks Electric Power Cooperative Inc,Ks City Power & Light Co & Western Resources,Inc, Including Wholly Owned Subsidiary Kg&E Co ML20196L3361999-05-18018 May 1999 Forwards Rev 1 to Cycle 11 COLR for WCGS, IAW TS Section 6.9.1.9 05000482/LER-1999-004, Forwards LER 99-004-00 Re Failure to Maintain Containment Closure During Fuel Movement as Required by TS 3.9.4.c. Attachment I to Ltr Identifies Actions Committed to by Plant in Encl LER1999-05-12012 May 1999 Forwards LER 99-004-00 Re Failure to Maintain Containment Closure During Fuel Movement as Required by TS 3.9.4.c. Attachment I to Ltr Identifies Actions Committed to by Plant in Encl LER ML20206Q8141999-05-11011 May 1999 Requests NRC Work with Industry to Resolve Generic Changes to Allow Permanent Change to TSs Prior to June 2000.Encl Provides TS Limited Duration Action Statement Until 990930 05000482/LER-1999-003, Forwards LER 99-003-00,re Failure to Perform TS SR 4.9.2.c Prior to Entering Mode 6.Commitments Made by Util Are Encl1999-05-10010 May 1999 Forwards LER 99-003-00,re Failure to Perform TS SR 4.9.2.c Prior to Entering Mode 6.Commitments Made by Util Are Encl ML20206K5141999-05-0707 May 1999 Provides Info Re Number of Tubes Plugged in Each Sg,As Required by TS 4.4.5.5.ISI of SGs B & C Completed on 990424,resulting in Mechanical Plugging of One Tube in SG B & Five Tubes in SG C ML20206J0711999-05-0505 May 1999 Forwards Guarantees of Payment of Deferred Premiums for Owners of Wolf Creek Generating Station,As Required by 10CFR140.21 ML20206D9551999-04-29029 April 1999 Forwards 1999 Annual Radioactive Effluent Release Rept 22, for Reporting Period Jan-Dec 1998,per Section 6.9.1.7 of WCGS Ts.Attachment to Ltr Identifies Commitments Resulting from Correspondence ML20206C7321999-04-22022 April 1999 Provides Notification of Changes at WCGS Affecting Plant Physical Security Plan,Per 10CFR50.54(p).Changes Identified in Attachment I Will Be Incorporated Into Plan by 990831. Commitments Made by Util Are Included in Attachment II ML20206B2051999-04-20020 April 1999 Forwards Revs to RERP Implementing Procedures,Including Rev 1 to EPP 06-001, CR Operations, Rev 1 to EPP 06-002, TSC Operations, Rev 3 to EPP 06-004, Public Info Organization & Rev 1 to EPP 06-005, Emergency.. ML20205L7431999-04-0606 April 1999 Confirms 990401 Telcon with NRC Re Late Payment Notice That Util Received for Invoice RL0295-99.Licensee Understands Invoice to Be Cancelled ML20205F1601999-03-30030 March 1999 Forwards Rept Re Status of Decommissioning Funding for WCGS, Per 10CFR50.75.Kansas Gas & Electric Co Decommissioning Trust Agreement,Encl ML20205K9481999-03-26026 March 1999 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-482/98-05.Corrective Actions:Training Was Provided to Mrep Members Through Use of Contract Individual Experienced in Maint Rule Programs.Change to Commitment Date,Encl ML20196K7261999-03-26026 March 1999 Forwards Certified Copy of ITS & ITS Bases,As Committed in Licensee to Nrc.Summary of Editorial Corrections, Also Encl ML20205A1961999-03-25025 March 1999 Provides Suppl 2 to 970515 Application for Amend to License NPF-42,providing Changes to TS Based on 990310 & 19 Discussions with NRC Re Conversion to Improved TS 1999-09-03
[Table view] |
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- W$LF CREEK NUCLEAR OPERATING CORPORATION Robert C. Hagan Voe Prendent Engineenng ET 95-0061
~
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D. C. 20555
Reference:
- 1) NRC Letter dated December 29, 1994, " Follow-Up to the Request for Additional Information Regarding Generic Letter 92-08, Issued Pursuant to 10 CFR 50.54 (f) ,
Wolf Creek Generating Station (TAC NO. M85625)."
- 2) Letter WM 95-0057 dated March 29, 1995, from.
N. S. Carns, WCNOC, to the NRC.
Subject:
Docket No. 50-482: Supplemental Response to the Follow-Up to the Request for Additional Information Regarding Generic Letter 92-08 Gentlemen:
Reference 1 required a response to be submitted to the NRC, under the requirements of 10 CFR 50.54 (f) , within 90 days of receipt of the letter. ;
Reference 1 indicated an increased level of concern within the NRC with the reliability of information and data supplied by Thermal Science, Inc., that Wolf Creek Nuclear Operating Corporation (WCNOC) may -have relied on to validate the acceptability of Thermo-Lag 330-1 as a fire barrier material at Wolf Creek Generating. Station (WCGS), Consequently, the NRC requested WCNOC to provide additional information regarding Wolf Creek Thermo-Lag 330-1 e installations. Specifically, WCNOC was requested to provide the information previously requested in Section II of the NRC letter of December 22, 1993, l
" Request For Additional Information Regarding Generic Letter 92-08 (TAC No.
M85625)," after verifying the information through the use of detailed examinations, such as destructive examinations. Reference 1 also requested additional information concerning material chemical composition, test and analysis methods to be used, fire endurance / performance capabilities, and various mechanical properties associated with seismic capabilities.
WCNOC provided a preliminary response to Reference 1 on March 29, 1995 (Reference 2), in which WCNOC stated we would provide a supplemental response by June 27, 1995. A complete response could not be provided at that time since the results of the NEI chemical composition testing were not available.
Additional information has since become available, and the attachment provides WCNOC's response to the information requested in Reference 1.
I l-9507030329 950627 PDR ADOCK 05000482 P PDR l P.O. Box 411/ Burhngton, KS 66839 / Phone: (316) 364-8831 3 i An Equal opportunny Ernployer MWHCNET [ f l
l
ET 95-0061 ,
Page 2 of 2 If you have any questions concerning this matter, please ontact me at (316) 364-8831, extension 4553, or Mr. Richard D. Flannigan at extension 4500 i i
Very truly yours, s
Robert C. Hagan i RCH/j ra ,
Attachment Enclosure (NUCON International Chemical Test Report for Wolf Creek)'
cc: L. J. Callan (NRC) , w/a, w/e D. F. Kirsch (NRC) , w/a, w/e J. F. Ringwald (NRC), w/a, w/e :
J. C. Stone (NRC), w/a, w/e 6
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i o
STATE OF KANSAS ) l
) 88 ,
- COUNTY OF COFFEY )
- l. .
Robert C. Hagan, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation;. '
that he has read the foregoing document and knows the content thereof; that '
- he has executed that same for and on behalf of' said Corporation 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.
i h.
l N ryPubEc Stat 'BY - // ' "
'[M _
,Wy Appt. Empires 9 98 Robp C C.~Hagan <
Vice President -l Engineering ;
SUBSCRIBED and sworn to before me this day of M , 1995.
1 e i
oTafy Public j
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Expiration Date I
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Attachmtnt to ET 95-0061 Page 1 of 5 I
SUPPLEMENTAL RESPONSE TO THE FOLLOW-UP TO THE REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 92-08, I
THERMO-LAG 330-1 FIRE BARRIERS PURSUANT TO 10 CFR 50.54(F) i
.1. Thermo-Lag Natorials Question la.
Describe the specific tests and analyses that will be performed to verify l that the Thermo-Lag fire barrier materials that are currently installed at Wolf Creek Nuclear Generating Station, or that will be installed in the future, are representative of the materials that were used to address the technical issues associated with Thermo-Lag barriers and to construct the fire endurance and ampacity derating test specimens. The tests and analyses shall address the material properties and attributes that were determined or controlled by Thermal Science, Inc., (TSI) during the manufacturing process and the quality assurance program. The tests and i analyses shall also address the material properties and attributes that contribute to conclusions that the Thermo-Lag materials and barriers conform to NRC regulations. These include: ;
(1) chemical composition (2) material thickness (3) material weight and density (4) the presence of voids, cracks, and delaminations l
(5) fire endurance capabilities ;
(6) combustibility (7) flame spread rating (8) ampacity derating (9) mechanical properties such as tensile strength, compressive strength, sheer strength, and flexural strength.
Response
With respect to Item 1.a.(1) above, WCNOC is participating in an industry-wide effort to evaluate chemical composition as a means of addressing product consistency on a generic basis. WCNOC subtaitted five samples of Thermo-Lag 330-1 to NUCON International, Inc., for pyrolysis gas chromatography (PGC) testing in accordance with the guidance of ASTM D3452 This testing is part of the industry-wide testing _ program requested by NEI in their letter to ,
Licensee Administrative Points Of Contact dated February 3, 1995. The five WCNOC samplen were taken from a one-hour pre-formed conduit section and pre-formed panel, a three-hour pre-formed conduit section and pre-formed panel, l and from installed trowel-grade material. Prior to this, WCNOC had also submitted 152 sections of pre-formed conduit sections to NEI as part of the NEI Phase I Generic Test Program.
NEI has indicated that they will provide to t.he NRC information on product consistency, based on the results of the generic chemical composition !
testing. The results of the Pyrolysic Gas Chomatography testing for organic materials on the five WCNOC samples indicate that the WCNOC samples are consistent, in terms of chemical composition, to the baseline results tested by NEI.
Attachment to ET 95-0061 Page 2 of 5 Inorganic testing will be completed in July, 1995, through the industry test program. A total of 18 samples will be tested. Seven of the samples will be taken from the material used in the NEI fire test program. The test results from these samples will provide baseline data to compare with the remaining l eleven samples. The remaining eleven samples will be selected from a l population of approximately 160 samples provided to NUCON by the Licensees. l WCNOC does not intend to perform any additional chemical testing at this '
time, pending evaluation of the results of the industry-wide test program currently in progress.
With respect to Item 1.a . (2) , WCNOC completed Quality Receiving Reports for original Thermo-Lag materials received on-site. These reports verify that the dimensions of the materials were inspected and found to be within the range specified by TSI.
With respect to Item 1.a . (3) and 1.a . (4) , WCNOC has obtained the important barrier parametters (24 parameters specified in Reference 3) to ensure that the Thermo-Lag installed at WCGS is bounded by industry testing. No substantial voids, cracks, or delaminations that would adversely affect barrier performance were identified during walkdowns for the 24 important barrier parameters and inspections of disassembled boxed assemblies.
With respect to Items 1.a.(5), 1. a . ( 6 ) , 1.a. (7) , and 1.a.(8) above, WCNOC has received the organic chemical test results from the NEI generic test program.
WCNOC's results conclude that the Thermo-Lag materials used at WCNOC are consistent with the material used in the NEI fire endurance tests and combustibility tests. NEI will perform inorganic chemical testing in July, 1995, on 18 samples. Seven of those samples will be taken from the material used in the NEI fire tests and will be chemically tested as a baseline.
Eleven samples will be selected from the population of samples provided to NUCON for the industry chemical test program. WCNOC will review the results of this testing for application to installed Thermo-Lag.
With respect to Item 1.a . (9) , NEI discussed shaker-table testing of cable raceway barrier installations in their letter to Licensee Administrative Points of Contact dated January 17, 1995. In that letter, NEI indicated that this testing was performed with acceptable results. Based on the results of the organic chemical test, performed on WCNOC Therme Tag, it can be concluded that the results of the shaker table test are applicable to WCNOC Thermo-Lag installations. WCNOC concurs with the NEI position that, if additional testing is required, it should be performed generically.
Question 1b.
Describe the methodology that will be used to determine the sample size and demonstrate that the sample size will be large enough to ensure that the information and data obtained will be sufficient to assess the total population of in-plant Thermo-Lag barriers and the materials that will be installed in the future. In determining the sample size, consider the time of installation and manufacture of the various in-plant materials and barrier installations. Give the number and types (e.g., panels, conduit preshapes, trowel-grade material, stress skin) of samples that will be tested or analyzed.
Attachment to ET 95-0061 Page 3 of 5
Response
As noted in response to Item 1.a. (1) above, WCNOC submitted 5 samples of Thermo-Lag to Nucon International, Inc., as part of cn industry-wide testing program sponsored by NEI. NEI requested each licetaec to submit several samples from each plant. The Wolf Creek samples were taken from a one-hour pre-formed conduit panel, a three-hour pre-formed conduit panel, a one-hour pre-formed wall panel, a three-hour pre-formed wall pane.1, and a sample of installed trowel-grade material; one sample from each of the five types of Thermo-Lag 330-1 applications installed at Wolf Creek. Based on conversations with both NEI and personnel from other licensees, WCNOC believes this number of samples will be sufficient to assess the total population of in-plant fire barriers, given the relatively small amount of Thermo-Lag 330-1 installed at Wolf Creek. Based on communication with NEI, WCNOC anticipates that this testing will confirm reasonable assurance of Thermo-Lag material consistency at WCNOC and the industry. Chemical testing to ensure product consistency will be considered for any future Thermo-Lag 330-1 material obtained for upgrade or replacement of existing Thermo-Lag.
However, at this time WCNOC does not intend to perform any additional chemical testing.
Question ic.
Submit the schedule for verifying the Thermo-Lag materials.
Response
As indicated in the above responses, WCNOC is participating in an industry-wide effort to evaluate chemical composition of Thermo-Lag 330-1 as a means of addressing product consistency. As noted in Reference 1, NEI will provide to the NRC and the industry information on product consistency, based on the results of the chemical composition testing. It is NEI's position that the chemical composition data will provide Liceasees with the basis to independently confirm applicability of generic industry test data with respect to several attributes, including fire endurance capability, combustibility, flame spread, heat release and ampacity derating (assuming resolution of current questions on ampacity derating test methodologies). If the NRC agrees with the NEI position, then the schedule outlined in Reference 2 is still valid. If the chemical test data is not consistent, or if the Imc does not agree with the NEI position, then WCNOC's schedule may need to be revised.
Question 1d.
After the analyses and tests have been completed, submit a written l supplemental report that confirms that this effort has been completed and provide the results of the tests and analyses. Describe any changes to previously submitted plans or schedules that result from the tests or analyses.
Response
As indicated in Reference 1, NEI will submit a detailed report to the NRC and Licensees providing the results of the generic testing and analysis following
Attachmant to ET 95-0061
.Page 4 of 5
. completion of the testing program. At the present time only organic material I testing has been completed. Enclosed with this letter is the report from NUCON International, Inc., " Pyrolysis. Gas Chromatography Analysis of 5 !
Thermo-Lag Fire Barrier Samples," which provides the'results of this testing. l Testing for inorganic material is~ scheduled by NEI to be completed in July, l 1995. The results of this testing will be submitted to the NRC by NEI. If additional analyses and testing are required, or if the issues outlined above i are not resolved by industry testing, WCNOC will submit a revised schedule or )
plans deemed necessary to resolve the Thermo-Lag issue at WCGS. !
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- 2. Important Barrier Parameters !
Question 2a.
Describe the examinations and inspections that will be performed to obtain- ;
the important barrier parameters given in Section II of the RAI of l December 1993 for the Thermo-Lag fire barrier configurations installed at Wolf Creek Generating Station.
l Response !
1 WCNOC has obtained and verified the 24 parameters listed in the Request for :
Additional Information (RAI) for WCGS BTP CMEB 9.5-1 applications (Reference 3). This information was-obtained and/or verified through the use of general walkdowns, design drawing reviews, and review of Quality Assurance (QA) {
records of the applications. WCNOC has also performed NEI Application Guide i evaluations, comparing as-installed configurations with the tested assembly [
configurations, and is currently reviewing the results, i i
Question 2b. I i
Describe the methodology that will be a, plied to determine the number and type of representative in-plant fire barrier configurations that will be examined in detail and demonstrate that the sample size is adequate to r ensure that the information and data that will be obtained are adequate to v ascess the total population of in-plant Thermo-Lag barriers. A large !
enough sample of the total population of configurations should be examined >
to provide reasonable assurance that the materials 'and important barrier i parameters used to construct the in-plant barriers and any future barrier j installations or modifications, are representative of the barriers used to {
construct the fire endurance test specimens.
Response
WCNOC performed a detailed examination of the entire population of Thermo-Lag l applications at WCGS required to comply with BTP CMEB 9.5-1. Therefore, the j requested statistical analysis to determine the sample size is not required ,
at WCGS. l i
Question 2c. [
Submit the schedule for obtaining and verifying all of the important ,
barrier parameters. ,
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Attachment to ET 95-0061 Page 5 of 5
Response
Important barrier parameters have been obtained and NEI Application Guide evaluations are being verified in accordance with the schedule outlined in Reference 2. However, some additional issues may arise as a result of the industry effort to evaluate chemical composition as a means to address product consistency. As noted in Reference 1, NEI will provide to the NRC and the industry information on product consistency, based on the results of i the chemical composition testing. With the assumption that the chemical composition testing results are consistent, and if the NRC agrees with the NEI position that the industry data can be used as a basis for using generic j test data with respect to Items 1.a. (2) through 1. a . ( 9) , then the schedule outlined in Reference 2 is still valid. If, however, the chemical test data I is not consistent, or if the NRC does not agree with the NEI position, then l our schedule may need to be revised. l Question 2d.
After the information has been obtained and verified, submit a written supplemental report that confirms that this effort has been completed and provides the results of the examinations and inspections. Verify that the parameters of the in-plant configurations are representative of the parameters of the fire endurance test specimens. Describe any changes to previously submitted plans or schedules that result from the examinations.
Response
WCNOC is currently reviewing the NEI Application Guide evaluation report. A report reflecting WCNOC's as-built configurations will be submitted in accordance with WCNOC's schedule for resolution of the Thermo-Lag issue submitted in Reference 2, unless additional examinations and inspections are required, or if the issues outlined above are not resolved by industry testing. The schedule for resolution of the Thermo-Lag issue at Wolf Creek submitted in Reference 2 has not been changed at the present time. Should issues result from industry testing, or should additional examinations be required, WCNOC will submit a revised schedule.
LIST OF REFERENCES
- 1) NEI Letter dated February 21, 1995 to W. T. Russell, NRR, from W. H. Rasin, NEI
- 2) Letter CO 94 0013, dated July 15, 1994, from R. N. Johannes, WCNOC, to the NRC
- 3) Letter WO 94-0013, dated February 9, 1994, from O. L. Maynard, WCNOC, to the NRC f
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