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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
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4
- ; g W@lJLF CREEK NUCLEAR OPERATING CORPORATION Otto L. Maynard President and Chief Exeo tue Officer December 23. 1997 ..
WM 97-0151 U. S. Nuclear Regu}atory Cot.. mission '
ATTN: Document Control Desk' Mail Station P1-137 Washington, D. C. 20555
Reference:
Letter dated November 25, 1997, from W. D. Johnson, NRC, to O. L. Maynard, WCNOC
Subject:
Docket No. 50-482: Response to Notice of Violations 50-482/9719-01, 9719-02, 9719-03, 9719-04, and 9719-05
- Gentlemen:
l This letter transmits Wolf Creek Nuclear Operating Corporati.cn's (WCNOC) response to Notice of Violations 50-482/9719-O', 9719-02, 9715-03, 9719-04, and 9719-05. Notice of Violation 9719-01 cites use of an operator aid without ,
the documented approval of tne Shift Supervisor. Notice of Violation 9719-02 cites examples of effecti'?eness follow-ops for corrective action documents not being performed as required by procedure. Notice of Violation 9719-03 cites an example of a maintenance worker working outside of procedural guidance which resulted in a r. inadvertent opening of an atmospheric relief valve.
Notice of Violation 9719-04 addresses a failure to reinstall an equipment hatch cover following the replacement of the associated filter cartridge.
Notice of Violation 9719-05 cites four examples of personnel failing to adhere to radiation protection procedures.
WCNOC's response to these violat.i ons is provided in the attachment. If you have - any questions regarding *his response, please cont:'t me at (316) 364- /,
8831, extension 4000, or Mr. Michael J. Angus at extension 4077 /.
Very truly yours, e!
l . fo rk f Otto I . Maynard # $0 OLM/jad Attachment l
cc:
!' W. D. Johnson (NRC), w/a E. W. Merschoff (NRC), w/a l~ J. F. Ringwald (NRC), w/a K. M. Thomas ( N RC) , w/a 9801050388 971223 lll i J
PDR g
ADOCK 05000482 pgg l0ll -
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RO. Box 411/ Burhngton, KS 66839 / Phone: (316) 364 8831 An Equal Opporunity Emp4 oyer M F HCNET l
I , Attachment to Wti 97-0151 Page 1 of 9 c
Violation 50-482/9719-01:
" Criterion V of Appendix B to 10 CFR 50 requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, and drawings apornpriate to the circumstances, and shall be accomplished in accordance with tl.ese instructions, procedures, or drawings.
Procedure AP 21D-003, " Control of Information Tagging," Revision 1 Step 6.6.10 requires operatur aids to be approved and documented by the Shift Supervisor. p Contrary to the above, from October 8, to October 22, 1997, operators used markings on Drawing EID-0003 as an operator aid without documented approval of the shift supervisor.
This is a Severity Level IV violation (Supplement 1) (50-482/9719-01)."
heason for Violation:
Engineering Information Drawing (EID)-0003, " Refuel Level Indication," was referred to by Control Room operators between October 8, and Octooer 25, 1997.
The inspector noted that EID-0003 listed the levels in percent while the wide range cold pressurizer level was calibrated in inches. In order to provide a correlstion between the two, a calculation was performed and EID-0003 was marked-up with handwritten notes. EID-0003 and the handwritten noces should have been controlled as either an operator aid, or the notes should have been lacorporated as a revision to the drawing.
The reason for the violation is failure to follow procedures which resulted in use of information which had not been verirled and validated. AP 21D-003,
" Control of Information Tagging" was not followed when the hand written notes were added to the drawing, and therefore not verified, validated and approved for usage.
Corrective Steps Taken and Results Achiev,eg On November 3, 1997, Revision 1 to EID-0003 was issued. This revision removed all Callaway site specific information and verified the tygon tubing water level (feet).
Corrective Stopa That Will Be Taken:
The contributing cause and generic implications related to this event are being evaluated by PIR 97-0945 which was written in association with Self Assessment 97-017, " Evaluation of Desktops or c,the r Informal Instructions,"
which looks at the generic implication of site wide uncontrolled documentu.
The expected completion date is January 15, 1998.
The Superintendent Operations Support will meet with each operating crew and review -AP 21D-003, " Control of Information Tagging" in conjunction with Per f ormance Improvement Request (PIR) 97-3442, associated with this violation, to ensure thev understand the appropriate use of documents. This action will be completed by February 2, 1998.
s Each Operations Shift Supervisor and the Superintendents of Operations and Operations Support will meet with their direct reports and ensure all uncontrolled documents that could be used to make decisions in operating the plant are removed from the Operations office spaces and the Control Room.
These uncontrolled documents are then to be either destroyed or submitted for processing to become controlled documents. The expected completion date for these meetings is February 2, 1998.
_ _ _ _ _ - - 1
, 'Attcchm:nt to WM.97 0151 Paga 2-of 9 Cate When Full Compliance Will Be Achieved:
WCNOC is currently in full cornpliance. Compliance was achieveJ on October 25, 1997 when EID-0003 was removed from the Control Room.
'Attachmont t o !?M 97-0151 2 Paga 3 of 9-Violat' ion 50-482/9719-02:
Criterion V of Appendix B to 10 CFR Part 50 requires, in part, that activities ,
affecting quality shall be prescribed by documented instructions, procedures, and drawings appropriate to tha circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
Administrative Procedure AP 28A-001, "Performaace Improvement Request,"
Revision 8, Step 6.1 1.1, requires that an effectiveness followup review be performed foi all Significance Level I and II performance improvement requests.
Contrary to the above, on October 22, 1997, effectiveness followup reviews were not performed for Performance Improvement Requests 96-2966 and -2989.
Both were Significance Level II perfctmance improvement requests.
o This !* e Ca"arity Level IV violation (Supplement 1)(60-482/9719-02).
Reason for the Violation Additional reviews by WCNOC personnel identified 35 Performance Improvement Requ7sts (PIRs) past their effectiveness follow-up review due dates. Twenty-seven of these were significant PIRs which are required to have an effectiveness follow-up review. Eight of the PIRs were non-significant which are not required to have an effectiveness follow-up revicw. Eight different groups had effectiveness follow-up reviews past due.
The reason for the violatien is that during initial development of the PIR ,
orogrem, mechanisms were not designad to provide management all of the tools to effectively monitor effectiveness follow-up reviews. Specifically, though the requirement was in place to perform effectiveness follow-up reviews, guidance for reporting and trending and the responsibility for performing these actions were not established, o Contributing Cause The controls to execute a computer search for effectiveness followup review dates were not user friendly and were different from the usual search techniques.
Corrective Steps Taken and Results Achieved Responsible managers were contacted to advise them of the concern and request they review their PIRs or re-schedule them to an appropriate time. Immediate actions included the. Operations department completing six effectiveness follow-upa and the Maintenance department re-scheduling four follow-ups and deleting one follow-up date that was assigned to a non-significant PIR. By October 29 1997, all the overdue effectiveness fol?ow-up reviews had been completed or re-scheduled.
On October 26, 1997, the PIR data base was modified to make the search for of tsct iveness follow-up review dates more user friendly. PIR Logkeepers were then interviewed and on-the-job training performed to ensure they know how to search for effectiveness follow-up review due dates and have adequate knowledge to find PIR due dates.
The Licensire and Corrective Action group began monitoring effectiveness follow-up review due datos on October 29, 1997 A 30-day "look ahead" report is now provided to managers to advise them of effectiveness follow-ap reviews coming due. This corrective action was implemented on December 19, 1997.
%ttachment to WM 97-0151 Page 4 of 9-A Corrective Stepr. That Will Be Taken The program for monitoring effectiveness follow-up reviews will be modified to assign PIR Coordinators the responsibility to monitor effectiveness follow-up review due dates. Procedure AP 28A-001, " Performance Improvement Request,"
will be revised by- December 31, 1997, to clearly state the PIR Coordinator responsibility for this monitoring function.
Licensing and Correction Action will develop performance indicators for tracking corrective action effectiveness follow-up reviews. These performance indicators will be developed by February 2, 1998.
PIR Coordinators will bc trained by December 31, 1997, to use the search functions in tca PIR data bace to find effectiveness follow-up review due dates.
Date When Full Compliance Will Be Achieved:
Full compliance was achieved on October 29, 1997, when the overdue effectivenuss follow-up reviews were either performed or reacheduled.
' Attachment to WM 97-0151 Page 5 of 9 Violation 50-482/9719-03:
" Technical Specification 6.8.1.a requires, in part, that written procedures be established, implemented, and maintained covering- the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Regulatorv Guide 1.33, Revision 2, Feb-uary 1978, Section 3.f., recommends, in part, that procedures be established for surveillance tests.
Surveillance Procedure FTS MT-008, " Main Steam Safety Valves Settings,"
Revision 8, Section 4.3, requires the test performer to not operate the root valves. indicated on Attachment C.
ntrary to the above, on September 30 ,1997, the test performers closed then opened Valve AB V0028, the instrument root valve indicated on Attachment C of Procedure STS MT-000, causing an inadvertent opening of valve AB PV0003, utmospheric relief valve for Steam Line C.
This is a Severity Level IV violation (Supplement 1) (50-482/9719-03)."
Russon for Violation:
The reason for t!.is violation is personnel error in that Maintenance personnel failed to comply with procedural requirements. The procedure, STS MT-008, did not contcin step for operating valve ABV0028, a root valve. It contained a caution note telling the worker not to operate the valve.
Contributing to the event were two additional causas:
- 1. There was inadequate communication between personnel olved in the work activities. There were missed opportunities to provide more specific direction, to confirm what was misunderstood or to call " time-out".
- 2. The pre-jnb briefing was incomplete in that there was a failure to cover specific responsibilities, procedural procautions, and procedure use requirements. The failure to covar these items in the pre-job briefing was a missed opportunity to make s .e everyono understood their roles and responsibilities.
Corrective Steps Taken and Results Achieved:
The Manager Maintenance met with Mechanical Maintenance personnel, tirst line Maintenance supervisors, and contractors on September 30, and October 1-2, 1997, to reinforce the limits and expectations for maintenance personnel operatiq plant equipment. Additionally, the expectation that the Control Room be contacted immediately upon recognizing a component or system manipulation error was reinforced.
Training for all Mechenical Maintenance personnel, reaffirming the requirements of procedure AP 15C-002, " Procedure Use and Adherence," was completed on October 2, 1997 The training also included instructions for use of three-way communication and the exoected elements of pre-job briefings.
Fact find! discussions and job counseling were done with those personnel involved. nese actions were completed on October 7, 1997.
E Procedute MTS MT-008 was revised on October 9, 1997, to correct valve misnomers,- idd caution notes and incorporate other human factor improvements.
"Communica' ion for Error Prevention" training was given to Maintenance craft personnel. This training was completed on December 22, 1997.
. Aitochmant to WM 97-0151 Page 6 of 9 4
Corrective Steps that will be Taken!
The lessons learned from this event will be shared with the other maintenance groups through review of Performance Improvement Request (PIR) 97-2959 during group s">fety meetings. This corrective action will be completed by February 27, 1998.
Date When rull Compliance Will Be Achieved:
WCHOC is current 4y in full compliance. Compliance was achieved on September 30 1997, when ABV0028 was opened.
. ' Attachment to WM 97-0151 Pag @ 7 of 9
' Violat$ ion 50-482/9719-04:
" Technical Specification 6.8.1.a requires, in part, that written precedures be established, implemented, and maintained covering the applicable procedure 3 recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Regulatory Guide 1,33, Revision 2, February 1978, Section 3.f., recommends, in part, that procedures be established for replacement of important filters."
Procedure MCM M7230-01, "NSSS Filter Changeout," Revision 9, Section 8.4, requires maintenance personnel to reinstall tne hatch cover over the equipment compartment as part of the restoration.
Contrary ta the above, on October 12, 1997, maintenance personnel signed for the ccmpletion of Procedure MCM M723Q-01 following the replacement of the
- filter cartridge without reinstalling the equipment hatch cover. The failure to replace the hatch cover resulted in tne area near the filter to be accessible as radiation levels increased to 3 Rem per hour 12 inches from the filter housing after operators returned the filter to service.
This is a severity Level IV violation (Supplement 1) (50-482/9719-04)
Response to Violation The reason for the above stated violation and the asscciated corrective actions were documented in WCNOC's response to violation 97-020-01, in letter WM 97-0133, dated December 12, 1997, which pertained to the same event.
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. ' Attachment to WM 97-0151 Page 8 of 9 Violation 50-482/9719-05:
" Technical Specification 6.11 requires, in part, that radiation workers adhere to procedures for personnel radiation protection consistent with. the requirements of 10 CFR Part 20.
Administrative Procedure AP 25A-100, " Radiation Protection Manual" Revision 2, Section 6.7.4, requires that access to the RCA [ radiologically controlled area} be controlled by an approved RWP tradiation work permit].
Contrary to the above:
- a. On October 5, 1997, a mechanic accessed the radiologically controlled area using Radiation Work Permit 970009 and used an.
internally contaminated gauge while performing work in the radiologically controlled area, an activity prohibited by the radiation work permit.
- b. On October 10, 1997, a radiation worker exited the radiologically controlled area and logged out of Radiation Work Permit 972601.
The wveker subsequently reentered the radiologically controlled area without logging onto a radic. tion work permit and without obtaining any dosimetry,
- c. On October 26, 1997, a radiation worker entered containment without an alarming dosimeter as required by Radiation Work Permit 970034
- d. On October 27, 1997, a radiation worker entered the radiologica.ly controlled area without the thermoluminescent dosimeter required by Radiation Work Permit 970009.
This is a Severity Level IV violation (Supplement IV) (50-482/9719-05)."
Reason for Violation:
As the above examples are similar in nature and pertain to violations of the radiation worker practices they were researched together to determine the root cause and appropriate corrective actions.
In the case of example b. it was concluded that the initial cause was a human error resulting from either a short-cut being taken or failure to implement rules learned in radiation worker training.
In the remaining examples it was determined that the radiation workers exhibited inattention to detail that caused them to violate radiation protection program requirements. The errors were unintentional and occurred either due to overconfidence on the part of the employee or due to an unplanned interruption that took the employees' attention away from the radiation protection program requirements, Corrective Steps Taken and Results Achieved:
Corrective actions for each example included these common actions:
- Each employee or contractor had their access to the radiologically controlled area (RCA) revoked.
- Employee retraining or counseling was performed which met the standards of management.
- Job performance counseling was performed.
- Each event was discussed during group or safety meetings to ensure lessons learned were shared.
, ' Attachment to WM 97-0151 Paga 9 of 9 Other actions implemented by the Health Physics organization included the establishment of the RCA access control area as a "No Talking Zone" to allow for greater concentration, and posting of a security officer at the RCA access door as an interim control during outage activities.
Corrective Steps That Will Be Takent Performance Improvement Request (PIR) 97-2389 was initiated by Health Physics on August 7, 1997, to identify general adverse trends regarding violations of the Radiation Protection Program. Short term corrective actions for tnis PIR were completed as of. October 2, 1997. Long term corrective actions including evaluation of changes to radiation worker training are due to be complete by January 30, 1998.
In an offort to improve human performance in the Access Control area, WCNOC Health Physics personnel will submit a proposed facility change to be evaluated using the design change process. This proposal will be submitted by January 1, 1998.
Date When Full Compliance Will Be Achieved:
WONOC is currently in full compliance. Full compliance was achieved on the date of occurrence of each event when the individuals involved were brought into compliance with WCNOC's radiation protection program requirements.
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