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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] Category:UTILITY TO NRC
MONTHYEARML20064A6951990-09-18018 September 1990 Requests one-time Waiver to Alter Licensed Operator Requalification Training Program Cycle to Be Better Aligned W/Natl Exam Schedule ML20059E6151990-08-29029 August 1990 Forwards Semiannual fitness-for-duty Program Performance Data Rept for Jan-June 1990,per 10CFR26.71(d) ML20059E9611990-08-28028 August 1990 Reaffirms Commitment to Safe & Responsible Operation of Facility in Face of Tender Offer for Util Stock.Accepts W/O Qualification,Responsibility for Continued Safe & Reliable Operation of Plant ML20059D5281990-08-27027 August 1990 Provides Correct Ltr Number for Jul 1990 Monthly Operating Rept.Correct Ltr Number Should Be No 90-0226 ML20059C1781990-08-21021 August 1990 Forwards Proprietary TR-90-0025 W01, Core Thermal-Hydraulic Analysis Methodology for Wolf Creek Generating Station, for Review & Approval by 920101.Rept Withheld (Ref 10CFR2.790) ML20059B3691990-08-21021 August 1990 Forwards Proprietary TR-90-0024 W01, Wolf Creek Nuclear Operating Corp Rod Exchange Methodology for Startup Physics Testing, Per Discussion at 890518 Meeting.Rept Withheld (Ref 10CFR2.790) ML20058P1001990-08-10010 August 1990 Forwards Wolf Creek Generating Station Inservice Insp Rept, for Fourth Refueling Outage,Period 2,Interval 1. Nonconforming Conditions Requiring Repair/Replacement of Supports Identified During Routine Maint Activities ML20058N1421990-08-0909 August 1990 Responds to Insp Rept 50-482/90-08 Re Effectiveness of Techniques Used to Detect Erosion/Corrosion Degradation. Existing erosion-corrosion Program Effective in Identifying Wall as Nonrelevant Volumetric Anomalies ML20058L2011990-08-0101 August 1990 Forwards Inadvertently Omitted Index of Proposed Tech Spec from Re RCS ML20055J0641990-07-26026 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-482/90-24.Corrective Action:All Dose Personnel Receiving Retraining within Normal 7-wk Training Cycle Which Began on 900723 & Emergency Procedure EPP 01-7.3 Will Be Revised ML20055H2091990-07-23023 July 1990 Informs That Util Has Commenced Cash Tender Offer to Purchase Outstanding Shares of Each Class of Common & Preferred Stock of Kansas Gas & Electric Co.Util Convinced That Proposed Merger Will Have No Effect on Plant Operation ML20055G8331990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20055F6671990-07-13013 July 1990 Forwards Monthly Operating Rept for June 1990 for Wolf Creek Generating Station & Corrected Pages 1,4 & 5 to May 1990 Rept ML20055D9941990-07-0505 July 1990 Forwards Addl Info Re Seismic Design Considerations for Certain safety-related Vertical Steel Tanks,Per 890525 Request ML20055D5011990-07-0202 July 1990 Forwards Change in Status of Licensed Operators Since Transmitted,Per 10CFR50.74 ML20055D0481990-06-29029 June 1990 Responds to NRC Re Violations Noted in Insp Rept 50-482/90-17.Corrective Actions:Procedure Adm 03-600 Revised on 900430,to Ensure That Respirator User Issued Model & Size for Which Fit Tested & Trained ML20055D2111990-06-29029 June 1990 Responds to Request for Addl Info Re Violations Noted in Insp Rept 50-482/90-05.Corrective Actions:Change Made to Adm 02-005, Reactor Operators Qualifications & Responsibilities ML20058K4011990-06-28028 June 1990 Forwards Emergency Preparedness 1990 Field Exercise Scenario for Exercise Scheduled for 900829 ML20043H2851990-06-18018 June 1990 Forwards Revised LERs 85-058-01 & 90-002-00,adding Rept Dates Inadvertently Omitted from Original Submittals ML20043G7691990-06-13013 June 1990 Responds to NRC 900514 Ltr Re Violations Noted in Insp Rept 50-482/90-16.Corrective Actions:Movement of Spent Pool Bridge Toward Location FF06 Halted & Bridge Crane Returned to Location DD02 ML20043F4051990-06-11011 June 1990 Forwards Monthly Operating Rept for May 1990 & Corrected Page 2 for Apr 1990 ML20043E8211990-06-0808 June 1990 Informs of Plant Radiological Emergency Preparedness Exercise for 1990 Scheduled for 900829.Schedule Discussed W/Personnel from Region IV Emergency Preparedness,Fema,State of Ks & Coffey County ML20043E7491990-06-0808 June 1990 Forwards Rev to Figure 3.4-2 to 880620 Application for Amend Revising Tech Specs 3/4.4.9.1 & 3/4.4.9.3.Rev Corrects Editorial Error ML20043E8721990-06-0505 June 1990 Notifies NRC of Changes in Status of Operator Licenses ML20043D3271990-05-31031 May 1990 Forwards Rev 17 to Physical Security Plan,Safeguards Contingency Plan & Security Training & Qualification Plan. Rev Withheld (Ref 10CFR73.21) ML20058K1911990-05-30030 May 1990 Forwards Radiological Emergency Preparedness Exercise Objectives for 1990 ML20043B4791990-05-24024 May 1990 Documents Administrative Error in Rev to Radiological Emergency Response Plan Submitted on 900116 ML20043B4361990-05-22022 May 1990 Responds to Request for Addl Info Re Proposed Revs to Tech Specs 3/4.4.9.1 & 3/4.4.9.3 Re Pressure/Temp Limits for RCS & Overpressure Protection Sys ML20042E8691990-04-30030 April 1990 Forwards Documentation of Util Ability to Make Payment of Deferred Premiums ML20042E3021990-04-13013 April 1990 Forwards Supplemental Response to NRC 900316 Ltr Re Violations Noted in Insp Rept 50-482/90-05.Corrective Actions:Air Check Valves to Main Steam & Feedwater Isolation Valves Added to Preventive Maint Program ML20012D9911990-03-22022 March 1990 Responds to NRC 900220 Ltr Re Violations Noted in Insp Rept 50-482/90-02.Corrective Actions:Procedure CNT-660, Rigging Revised to Incorporate safety-related Manway Covers Which May Be Removed W/O Addl Safety Evaluation ML20012C9841990-03-19019 March 1990 Provides Util Response to Generic Ltr 89-19 Re Request for Action on Resolution of USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Mods Made to ESFAS Logic Design ML20012C6841990-03-15015 March 1990 Responds to NRC 900213 Ltr Re Violations Noted in Insp Rept 50-482/89-26.Corrective actions:10CFR73.71,App G Reviewed to Determine If Any Reporting Requirements Not Properly Reflected in Security & Operations Procedures ML20012A1601990-02-23023 February 1990 Forwards Semiannual Radioactive Effluent Release Rept 10 for Jul-Dec 1989 & Rev 5 to ODCM for Wolf Creek Generating Station. ML20012A5631990-02-23023 February 1990 Forwards Total Pump Study & Revises Info Previously Provided on Safety Injection Pumps & Centrifugal Charging Pumps in Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. ML20006F7151990-02-21021 February 1990 Provides Present Levels of Onsite Property Damage Insurance Being Maintained,Per 10CFR50.54(w)(2) ML20012B0781990-02-14014 February 1990 Forwards Cycle 5 Radial Peaking Factor Limit Rept,Per Tech Spec Section 6.9.1.9 ML20006D6541990-02-0808 February 1990 Forwards Amend to Physical Security Plan.Proposed Change Will Require Submittal of Fingerprint Cards to NRC in Lieu of Currently Required Criminal Records Check.Proposed Changes & Safety Evaluation Withheld ML20006E3551990-02-0707 February 1990 Responds to NRC 900103 Ltr Re Violations Noted in Insp Rept 50-482/89-30.Corrective Actions:Communications Flow Process Between Facilities & Locations of Operations Status Boards Will Be Reviewed to Identify Needed Improvements ML20006E1871990-02-0707 February 1990 Advises That Bt Kckinney,Senior Reactor Operator,No Longer Employed at Util ML20011E1041990-01-30030 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Util Developed Plan & Schedule to Accomplish Reviews,Evaluations & Insps Recommended in Part IV ML19354E8831990-01-23023 January 1990 Forwards Response to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. ML20005G7791990-01-16016 January 1990 Forwards Monthly Operating Rept for Dec 1989 for Wolf Creek & Revised Operating Data Repts for Feb-Nov 1989,reflecting Thermal Generation Using New Calorimetric Procedure That Uses Main Steam Flow Instead of Feedwater Flow ML20006A0051990-01-16016 January 1990 Forwards Rev 25 to Facility Radiological Emergency Response Plan & Revs to Radiological Emergency Response Plan Implementing Procedures.Procedures Effective 891220 ML20005H1801990-01-15015 January 1990 Forwards Amend 4 to Indemnity Agreement B-99 ML20005E8591990-01-0404 January 1990 Certifies That Util Implemented fitness-for-duty Program That Meets Requirements of 10CFR26 ML20005E1921989-12-26026 December 1989 Affirms That Util Will Meet Schedule Requirements of Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. ML20011D4801989-12-20020 December 1989 Responds to NRC 891120 Ltr Re Violations Noted in Insp Rept 50-482/89-27.Corrective Actions:Personnel Completed Detailed Review of Tech Spec Surveillance Requirements to Ensure That Each Item Properly Addressed in Surveillance Procedures ML19332F8731989-12-14014 December 1989 Requests Authorization to Use ASME Section XI Code Case N-401-1, Eddy Current Exam,Section Xi,Div 1, Per 10CFR50.55a(a)(3),since Case Not Currently Listed in Reg Guide 1.147,Rev 7 as Endorsed by NRC ML19332F9131989-12-14014 December 1989 Notifies That DM Brown No Longer Employed at Facility as Senior Reactor Operator,Per 10CFR50.74 1990-09-18
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, ob e
KANSAS GAS AND ELECTRIC COMPANY ss
, THE E'LRCTen*C COnenuNY e*
GLE N N L MOE S T( H
.'CE pa t h ila t es t O*a ma t omsg i January 12, 1979 Mr. Karl V. Seyfrit Director, Region IV Office of Inspection and Enforcement U.S. fluclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Re: Docket !!o. ST!! 50-482 Sub: 50.55(c) Report Regarding Concrete Void
Dear Mr. Seyirit:
On December 14 we reported to your Region IV Office that a concrete void was revealed when the fo rms for the sixth lif t of the Wolf Creek reactor containment building were lifted.
Subsequent to this initial report, we concurred with you that a wri tten 50.55 (e) report would be prepared for this void. Accordingly, please find attached two (2) copies of our interim report dated 1/11/79. A final report will be submitted after repairs have been co:nple t ed .
Also attached as part of the report is Mr. H.W. McCall's letter dated 1/11/79 which transmitted the final Ad !!oc Committee findings and recommendaticas to tre. These correspond to the eleven items of your letter of December 19.
We will review this report with Region IV personnel in Arlington, Texas on Saturday, January 13, 1979.
Please advise if you need additional information.
Yours very truly, dI /d j,'JL&b/)5'b[D
./,
GLK:bb Attach cc: Director, Office of Inspection & Enforcement c/o Distribution Service Branch, DDC, ADM U.S. !!uclear Regulatory Commission 79011866(
Washington, D.C. 20555 (Attach 15 copies) 20! IV. Market - Wichda, Kansas -- Ma l Address: P. O. Box 2C8 ! Wichita, Kansas 67201 - Telephone- Area Code (316) 26#1111
1/11/79 RFPORT OF CC:! CRETE VOID This interim report is made pursuant to 10CFR50.55(e) regarding a concrete void in the Wolf Creek Reactor Building.
(a) Description of the Deficiency On December 13, 1978, when the form for the sixth ring pour of the Wolf Creek heactor Containment Buildina was raised, a void beneath the equipment hatch was revealed. The void extends downward from the bottom of the equipment hatch to the top of the fifth ring pour at elevation 2043'-10" The sides of the void slope upward away from the hatch centerline. The width of the void is approximately six feet and the depth of the void extends through the thickness of the wall.
(b) Identi fication of the Firm Constructing the Facility Concrete production and placement far all Power Block Buildings at Wolf Creek is performed by Daniel International.
(c) Analysis of Safety Implications Because of the dimensions and location of the void described above, it is impossible that the void could remain unseen and thus remain unrepaired until the structure would go into service. Iloweve r, if it is postulated that the void renained undetected, it would have most probably been detected at the time of tendon tensioning (which occurs prior to opera tion) because of excessive deformations as a result of tendon load. Repair of th. void will meet all design requirements and no adverse effect to te health and safety of the pub)ic will result because of this voic (d) A Description of the Corrective Action, organization Reaponsible for the Action, Measures to , Prevent Reoccurrence The occurrence of the void has been docurented on !;onconformance Report 1Stio719C by Daniel and forwarded to the A/E, Bechtel Power Corporation, for dispositioning in the established manner. As of this date the details of how the repair will be made nave not been forwarded to the site by the A/E. When the A/E approved disposition is received, it will be reviewed with !JRC Region IV personnel prior to proceedinq with the repair work.
The repair work will be performed by Daniel.
To enhance the ef fecti veness of the Wolf Creek QA Program and especially to reduce the likelihood of additional concrete placement problems
Report of Concrete Void 1/11/79 the eleven step program as described in Mr. K.V. Seyfrit's letter to Mr. G.L. Koester dated December l'), 1978, has been undertaken. The attached report indicates the status of all eleven items and describes the findings of Daniel's Ad Hoc Committee. This report and Mr. H.W. McCall's letter of January il, 1979, also indicate the actions which hace been and are being takea as a result of the Committee's review.
To provide a further review of the QA Program as carried out by KG&E and Daniel, an independent consultant will be retained by YG&E/KCP' to make a long term investigation of the construction QA Program, its implementation and its effecti*leness. The con-sultants work will include recommending changes to correct any inadequacies which might be identi fied. It is planned to start this independent review as soon as a suitable consultant can be selected.
D ANIEL CON STRUCTION COM PANY, I NC.
DANIEL SulLDING GREENVILLE, SOUTH CAROLINA 29602 H. W. McCALL P ESIDENT Para o==* January 11, 1979 Mr. G. L. Koester Vice President Kansas Gas and Electric Company 201 North Market Street Wichita, Kansas 67201
Dear Glenn:
Confirming our discussion at the Wolf Creek site on January 9 and 10, I am pleased to transmit the Ad Hoc Committee's final ~ report on the placement and consolidation of the concrete on the Wolf Creek Project.
This report includes recommendations and actions deemed necessary to release work-hold agreement #3. D. M. McAfee has been assigned the responsibility to follow up all the recommendations and see that they are implemented.
In addition, we have enclosed a copy of the existing WP-IV-106 and QCP-IV-106 with the Applicable Draft Interim Change Pr.ocedures recommended by the Committee.
A Technical Service Representative from our Greenville-based Tech-nical Service Division will be on the site to fulfill a newly created position of Technical Superintendent-Concrete until a per-manent superintendent is assigned to the project.
The additional training of the craft in the field has been started and will be documented. A formal program for training responsible personnel in project procedural requirements shall be completed by February 19, 1979.
Subject to your review of our response and your verification of the actions called for therein we ask that you ign and release work-hold agreement #3.
incerely, cc: J. O. Arterburn L. W. McGri ff R. A. Bradshaw D. M. McAfee M. E. Clark D. T. McPhee E. W. Creel is e ?EO7 L. R. Smi th W. E. Hitt ~v' B. E. Wells
. a DANIEL INTERNATIONAL CORPO:MTION DANIEL BUILDING GR E ENVILL E. SO UTH CAROLINA 296o2 18o3)299-2500 TO: H. W. McCall DATE: January 10, 1979 FROM: Ad Hoc Committee
SUBJECT:
Placement and Consolidation of Concrete on Wolf Creek Project
REFERENCE:
- 1. Letter from H. W. McCall to Distribution, Dated December 16, 1978 same subject.
- 2. Letter from USNRC, to Kansas Gas and Electric Company, Dated December 19, 1978.
In accordance with your directive stated in reference #1 above, the Ad Hoc Committee has completed their review of safety related con-crete placement, consolidation, testing and inspection at the Wolf Creek Project.
The following are the results of the review. This report is keyed in the left hand margin to both reference #1 and #2 above. A sum-mary of recommendations is shown at the end of the report.
Reference 1 2 para.1 Immediately halt further placement of concrete in safety related structures until the following proposed reviews and corrective measures have been completed.
A Work Hold Agreement Number 3 was issued by Kansas Gas & Electric Company for safety related concrete on December 18, 1978, para,1 para.2 Completely review concrete placement and related work procedures to assure their adequacy for the placement and consolidation of concrete.
The results of the above review indicated the procedural controls for placement and censolidation of concrete are adequate and are in compli-ance with project requirements. However, to strengthen the procedural controls a change to WP-IV-106, (Concrete Pre-Placement, Placement and Post Placement) is recommended to include a section addressing pre-planning activities for difficult concrete placement.
January 10, 1978 Page Reference 1 2 para.2 para.3 Completely review quality control, inspection and testing procedures to confirm their adequacy.
The results of the above review indicate the procedural controls used by quality Control for testing and inspection of placement and consoli-dation of concrete are adequate and meet project requirements. To be consistant with the recommended change to WP-IV-106 it is recommended that QCP-IV-106 (Concrcte Pre-Placement, Placement and Post-Placement) also be revised to address the Quality Control Department's participat-ion in the preplanning effort and implementation of the plan.
Reference 1 2 para.3 para.4 Assure all persons in construction engineering, construction, and quality control are fully cognizant of these procedures, or any modifications to these procedures and that Quality Assurance verifies that the appropriate persons are trained in these procedures,
- a. The Committee's review to assure that personnel in Construction Engineering and Construction are fully cognizant of concrete place-ment and related work procedures and modifications thereto resulted in the following:
Responsible Construction Engineering and Construction per-sonnel are cognizant of concrete placement an1 consolidation procedure requirements; however, there is a lack of documen-tation attesting to procedural review or training by either Construction Engineering or Construction, A standardized program has not been implemented for orientation and training of personnel relative to procedural requirements and contents.
A standardized program has not been implemented to assure that personnel are cognizant of either new procedures or revision to existing procedures,
- b. The Committee's review to assure that personnel in Quality Control are fully cognizant of the requirements of quality control, testing and inspection procedures including modifications resulted in the following:
Quality Control personnel have a generally good working know-ledge of both the purpose and contents of QC Procedures al-though familiarity with the procedure itself was apparently limi:ed in some cases.
January 10, 1979 Page Reference (con't) 1 2 para.3 para.4 A standardized program has not been implemented for orientation and training of personnel relative to procedural requirements and contents.
A standardized program has not been implemented to assure that personnel are cognizant of either new procedures or revisions to existing procedures.
- c. The Committee's review to assure that Quality Assurance verifies that appropriate persons are trained in procedures related to place-ment and consolidation of concrete indicated that the Orientation and Training is being audited and the results of the audits were satis-factory. Audits of On-Going Training of Craf t Personnel invol' nd in safety related work have not been accomplished to date.
In conclusion, these reviews indicate that project personnel inter-viewed are generally cognizant of the procedure requirements, how-ever, to assure that responsible personnel are knowledgeable of appropriate procedural requirementa additional training should be provided to Construction supervision, Engineering and QC personnel.
Specific training of concrete placement craft personnel should be provided as specified by the Technical Superintendent-Concrete.
Reference 1 2 para.4 para.5 ~~ Review the adecuacy of the quality assurance program for verifying the satisfactary placement and consolidation of concrete to meet project requirements.
The Committee reviewed the adequacy of the quality assurance pro-gram with the following results:
The Quality Assurance Program for assuring the satisfactory place-ment and consolidation of concrete to meet project requirements is adequate. The implementation of the program is adequate and ef fect-ive with the exception of documented training of personnel. To assure that project personnel are provided adequate training to per-form their assigned functions, the Department Managers shot td specify the required class room training for personnel under their direction.
Tids training should be conducted and documented for supervisory con-struction engineering and quality control personnel. In addition special formal and informal training of craf t personnel shoald be conducted and documented as specified by the Technical Superintendent -
Concrete.
January 10, 1979 Page Reference 1 2
--- para. 6 Review the adequacy of the quality control program for verifying the satisfactory implementation of the procedures.
The Quality Control Program was reviewed by the Committee and included the checks and balances of the Quality Control Program such as Procedures, Inspection Reports, Deficiency Reports, Non-conformance Reports and Audit Reports. The results of this review indicated that the QC Program has the necessary controls for verify-ing satisfactory implementation of the procedures.
A weakness was identified with documented procedural training which is addressed above. Also, it is recognized that better preplanning would provide additional assurance of the success of difficult con-crete placements. This is addressed in the review of the specific void as follows.
Reference 1 2 para. 5 para.7 Review the specific void in the concrete under the equipment hatch in the reactor containment wall to determine probable cause and corrective action.
A review was conducted by the Committee to determine the probable cause of the void.
The pour started on north side of Equipment Hatch with adequate vibrator crews working concrete from the north side flowing con-crete under the Equipment Hatch sleeve toward the south side.
Vibrator crews were also on the south side helping to flow the concrete. The concrete Q.C. Inspector and the concrete foreman were visually observing the face of the concrete with the aid of flash lights from approxiaately 20 feet from the center line of the sleeve and was considered sealed, they authorized finishing the pour from the south side of the Equipment Hatch sleeve. The probable causes are:
- 1. Delay ir. the pour around the Equipment Hatch on the north side to havirg to replace styrofoam which had broken loose. The delay of approximately 30 minutes could have reduced the plastic-ity of the concrete face.
- 2. Lack of windows in the forms to f acilitate placement and inspection.
- 3. Due to the heavy congestion of the rebar and tendon sheathing around the Equipment Hatch sleeve it was extremely difficult for personnel to get closer than 15'-20' from the centerline of the sleeve.
- 4. The centerline of the sleeve was not visually identified to aid Quality Control and Construction personnel in determining the location of the concrete face in relation to the centerline.
January 10, 1979 Page Ref+rence 1 2 '~
para.5 para.7 5. Absence of weep holes in the forms contributed to trapping air and preventing flow of concrete.
In conclusion elimination or mitigation of these probable causes thru better preplanning would have prevented the void.
Corrective Action to reduce the possibility of voids in congested areas.
The implementation of the Committee's recommendations at the con-clusion of this report should eliminate or mitigate the occurrence of voids as well as improve the overall concrete placement and consolidation program.
Reference 1 2 para.6 para.8 Review and confirm the independence of incpection and verification organizations.
This review was conducted by the Committee and the results confirm the independence of the inspection and verification organizations.
A thorough review of the management commitments at the Wolf Creek Project which included Section 17.Bl. of the PSAR, the DIC Quality Assurance Program-Nuclear and the organization alignment and res-ponsibilities defined in Construction Procedure AP-II-01, (Site Organization and Position Description) revealed that the management system for the project provides adequate independence for the inspec-tion and verification organization.
Interviews with Quality Control supervisors and inspectors confirmed that the implementation of the management commitments in the PSAR, DIC Quality Assurance Program - Nuclear and Project Construction Procedures is satisfactory.
Personnel interviewed feel that Quality is not being sacrificed in favor of schedule or cost.
The interviews revealed that a communication gap exists within Quality Control and between Quality Control and the remainder of the project.
It is recommended that Quality Control manageaent should be included in the project planning meetings and they should conduct regular meet-ings with their subordinate supervision to discuss work forecasts and potential and real problem areas. Effcrte should be made to reaffirm all personnel in the Quality Control Department are informed of their independence and authority.
, January 10, 1979 Page Reference 1 2 para. 7 para.9 Establish a Daniel Construction Company Ad Hoc Committee cotprising David M. McAfee, Chairman, Leo R. Smith; Richard A. Bradshaw; and William E. Hitt to review, evaluate, and attest to the adequacy of the above action items prior to further placement of saf ety related concrete.
Kansas Gas and Electric Company will be represented at each Committee meeting by at least one individual from its Quality Assurance group.
The Ad Hoc Committee was formed in accordance to the above statement and this report comprises its findings and recommendations.
Reference 1 2 para.8 para.10 David M. McAf ee, Committee Chairman, is to report to Mr. H. W. McCall, President-Power Group, Daniel Construction Company, on a daily basis as to the progress being made on these actions. Mr. H. W. McCall, in turn, will keep you informed, daily, of the committee's significant findings.
D. M. McAfee did report to H. W. McCall to discuss progress and find-ings of the Committee on a daily basis. This progress was reported to G. L. Koester on a regular basis.
Reference 1 2 -
para.11 Discuss with Region IV personnel the completion status of the reviews and corrective measures identified above, along with any significant findings, prior to resumine the placement of concrete in safety re-lated structures .
A meeting is scheduled with Region IV personnel on January 13, 1979, to present this report.
RECOMMENDATIONS: 1. Implement a formal program for training responsible personnel in project procedural requirements.
- 2. Provide additional training of concrete placement and consoli-dation requirements to applicable construction and quality con-trol personnel to assure their knowledge for placing and con-solidation of concrete.
- 3. Assign Technical Superintendent-Concrete for the project to direct Ccnstruction personnel in preplanning their work.
January 10, 1979 Page RECOMMENDATIONS (con't)
- 4. Q.C. Management conduct regularly scheduled meetings with their subordinate supervision to discuss work forecasts and potential and real problem areas. Also, Q.C. Management should be required to participate in roject planning meet-ings.
- 5. Revise WP-IV-106 and QCP-IV-106 (Concrete Preplacement, Place-ment and Post Placement) to address preplanning and special written instructions for difficult concrete placement act-ivities.
- 6. A Quality Assurance audit of on going training of craf t personnel sould be conducted in the near future.
- 7. Additional special formal and informal training for craft personnel should be conducted and documented as specified by the Technical Superintendent-Concrete.
- 8. The Project Manager and the Regional Manager, Power Group should meet with Q.C. personnel to reaffirm their independence and authority.
- 9. Add to the Daniel Quarterly Quality Assurance Committee Meeting agenda an item to review the independence and authority of the Q.C. Department. This meeting is a joint meeting between the licensee and Daniel.
- 10. Submit formal requests to the Architect Engineer when required to facilitate placement of concrete.
/
D. M. McAfee