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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 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-1999-010, 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 ML20212C9211999-09-15015 September 1999 Forwards NRC Form 536, Operating Licensing Examination Data, in Response to NRC Administrative Ltr 99-03 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 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 ML20211M7151999-09-0303 September 1999 Forwards Changes to Wolf Creek Generating Station Data Point Library.Emergency Response Data Sys Points Affected Are EJL0007 & EJL0008 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 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 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 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 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 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 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 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 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, 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 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 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 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:OUTGOING CORRESPONDENCE
MONTHYEARML20217F7481999-10-14014 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20209A7461999-06-29029 June 1999 Informs of Changes in Project Mgt Staff Assigned to Wcgs. Effective 990628,J Donohew Will Assume PM Responsibilities ML20195G3451999-06-0909 June 1999 Ack Receipt of Ltr Dtd 990105,which Transmitted Wolf Creek Emergency Plan Form Apf 06-002-01 Emergency Action Levels, Rev 0,dtd 990105,under Provisions of 10CFR50,App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20195D5111999-06-0202 June 1999 Forwards Safety Evaluation Authorizing Inservice Inspection Program Alternative for Limited Reactor Vessel Shell Weld Exam & Relief Request from Requirements of ASME Code,Section XI for Wolf Creek Generating Station ML20207A8681999-05-25025 May 1999 Informs That NRC Ofc of NRR Reorganized Effective 990328. as Part of Reorganization,Division of Licensing Project Mgt Created ML20207E2791999-05-25025 May 1999 Announces Corrective Action Program Insp at Wolf Creek Reactor Facility,Scheduled for 990816-20.Insp Will Evaluate Effectiveness of Activities for Identifying,Resolving & Preventing Issues That Degrade Quality of Plant Operations ML20207A3491999-05-21021 May 1999 Forwards Insp Rept 50-482/99-03 on 990321-0501.Four NCVs Noted ML20206H3901999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamentals Exam Section of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However Copy of Master Exam with Answer Key Encl for Info.Without Encl ML20206H5941999-05-0505 May 1999 Forwards Insp Rept 50-482/99-04 on 990405-09.No Violations Noted.Scope of Inspection Included Review of Implementation of Licensee Inservice Insp Program for Wolf Creek Facility Refueling Outage 10 ML20206H2891999-04-30030 April 1999 Forwards Exemption from Requirements of 10CFR50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation, for Wcgs.Exemption Related to Application ML20205L8541999-04-0909 April 1999 Forwards Insp Rept 50-482/99-02 on 990207-0320.Five Violations Identified & Being Treated as Noncited Violations ML20205J3371999-04-0606 April 1999 Forwards Request for Addl Info Re Wolf Creek Generating Station IPEEE & 971208 Response to RAI from NRC Re Ipeee. RAI & Schedule for Response Were Discussed with T Harris on 990405 ML20205K4451999-04-0303 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/98-05 & of Need for Larger Scope of Review for Planned C/As for Violation 50-482/98-05,which Requires Extending Completion Time ML20205H7091999-04-0202 April 1999 Discusses 990325 Meeting at Plant in Burlington,Ks to Discuss Results of PPR Completed on 990211 ML20205G5851999-04-0101 April 1999 Forwards RAI Re Licensee 960214 Submittal of 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant. Response Requested within 120 Days of Receipt of Ltr ML20205C2101999-03-26026 March 1999 Informs That NRC Staff Reviewed WCNOC 960918,970317 & 980429 Responses to GL 96-05, Periodic Verification of Design- Basis Capability of Safety-Related Movs. Forwards RAI Re MOV Program Implemented at Wolf Creek Generating Station ML20204H7571999-03-23023 March 1999 Discusses WCNOC 990202 Proposed Rev to Response to GL 81-07, Control of Heavy Loads, for Wcgs.Rev Would Make Reactor Building Analyses Consistent with TS & Change Commitment Not to Allow Polar Crane Hook Over Open Rv.Revs Approved ML20205A4221999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from Wolf Creek Plant Performance Review for Period 980419-990125. Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl ML20207L5941999-03-0404 March 1999 Informs That Staff Accepts Util 981210 Requested Approval for Use of ASME Code,Section III Code Case N-611, Use of Stress Limits as Alternative to Pressure Limits,Section III, Div 1,Subsection NC/ND-3500, for Certain Valve Components ML20207F3121999-03-0303 March 1999 Informs That Info Provided in Entitled, Addl Info Requested for Topics Discussed During Oct 14-15 Meeting, from Wcnoc,Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20207F4491999-03-0303 March 1999 Forwards Signed Copy of Updated Computer Access & Operating Agreement Between NRC & Wcnoc,Per ML20207F0411999-02-26026 February 1999 Informs That KM Thomas Will Resume Project Mgt Responsibilities for Wcngs,Effective 990301 ML20206U6131999-02-0202 February 1999 Forwards Draft SER on Proposed Conversion of Current TSs for Wolf Creek Generating Station to Improved Tss.Encl Draft SER Being Provided for Review to Verify Accuracy & to Prepare Certified Improved TSs ML20202B7391999-01-26026 January 1999 Forwards Insp Rept 50-482/99-01 on 990111-14.No Violations Noted.Nrc Understands That During 990114 Exit Meeting,Vice President,Operations/Chief Operating Officer Stated That Util Would Revise Security Plan ML20199H4671999-01-15015 January 1999 Forwards Insp Rept 50-482/98-20 on 981115-1226.No Violations Noted.Conduct at Wolf Creek Generally Characterized by safety-conscious Operations & Sound Maintenance Activities ML20199B0591999-01-11011 January 1999 Forwards Y2K Readiness Audit Rept for Wolf Creek Nuclear Generating Station.Purpose of Audit Was to Assess Effectiveness of Wolf Creek Nuclear Operating Corp Programs for Achieving Y2K Readiness ML20199A0991998-12-29029 December 1998 Informs That on 981202,NRC Staff Completed Insp Planning Review (Ipr) of WCGS & Advises of Planned Insp Effort Resulting from Ipr.Forwards Historical Listing of Plant Issues,Referred to Plant Issues Matrix IR 05000482/19980121998-12-18018 December 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/98-12.NRC Have Withdrawn Violation 50-482/98-12-02 for First Example Re Procedure AP 05-0001 ML20198B2701998-12-16016 December 1998 Informs That Staff Has Incorporated Rev of Bases for TS 3/4.7.1.2, Afs Into WCGS Tss,Per 981108 Request.Rev Specifies Essential SWS Requirements for turbine-driven Afs. Overleaf Pages Provided to Maintain Document Completeness ML20196K0321998-12-0808 December 1998 Informs That Staff Has Incorporated Rev of Bases for TS 3/4.4.4, Relief Valves, Requested by .Rev Clarifies Bases to Be Consistent with Amend 63 to Wolf Creek TSs .Rev Acceptable.Bases Page Encl 1999-09-29
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WR-51997 Otto L. Maynard, President and 4 Chief Executive Officer 3 Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66839 i
SUBJECT: NRC INSPECTION REPORT 50-482/96-24
Dear Mr. Maynard:
Thank you for your letter of February 28,1997,in response to our letter and Notice
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- of Violation dated January 30,1997. We have reviewed your reply and find it responsive
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to the concerns raised in our Notice of Violation. We will review the implementation of
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Arthur T. Howelllli Acting Director Division of Reactor ojects )
Docket No.: 50-482 License No.: NPF-42 l
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Chief Operating Officer Wolf Creek Nuclear Operating Corp. ///
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Jay Silberg, Esq. 'V j Shaw, Pittman, Potts & Trowbridge
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2300 N Street, NW Washington, D.C. 20037 9703110162 970305 PDR ADOCK 05000482 G PDR
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Supervisor Licensing Wolf Creek Nuclear Operating Corp. l P.O. Box 411
- Burlington, Kansas 66839 l Chief Engineer *
. Utilities Division
{- - Kansas Corporation Commission
, 1500 SW Arrowhead Rd.
Topeka, Kansas 66604-4027
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Office of the Governor
, State of Kansas j. Topeka, Kansas 66612 i
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- Attorney General Judicial Center 301 S.W.10th
- 2nd Floor Topeka, Kansas 66612-1597
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Public Health Physicist Division of Environment
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- and Environment i. Bureau of Air & Radiation Forbes Field Building 283
, Topeka, Kansas 66620 Mr. Frank Moussa Division of Emergency Preparedness *
2800 SW Topeka Blvd Topeka, Kansas 66611-1287 i
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Branch Chief (DRP/B) DRS-PSB Project Engineer (DRP/B) MIS System
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DOCUMENT NAME: R:\_WC\WC624AK.JFR To receive copy of document, Indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy RIV:DRP/B C:DRP/B l _ AD:QFf DNGraves;df po WDJohnsongyh AT@ ell 3/ q /97 3/y /97 3/f /97 OFFICIAL RECORD COPY
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bec to DCD: (IE01) !
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I DOCUMENT NAME: R:\_WC\WC624AK.JFR To receive copy of document, Indicate in box: "C" = Copy without enclosures "E" = Copy wdh enclosures "N" = No copy RIV:DRP/B C:DRP/B _ AD:Q$P DNGraves;dt po WDJohnsongyh ATib Well 3/ q /97 3/( /97 3/_6 /97 OFFICIAL RECORD COPY
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W4pLF CREEK NUCLEAR OPERATING CORPORATION l
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. Ik P9 ( +, l Otto L Maynard
'4 Prescent aind I i Chief Executive Officer
[f N~.d February 28, 1997 REGIO"~ WM 97-0025 l
U. S. Nuclear Regulatory Commission
ATTN: Document Control Desk
, Mall Station F1-137 i Washington, D. C. 20555 Reference: Letter dated January 30, 1997, from J. E. Dyer, NRC, to N. S. Carns, WCNOC l Subject: Docket No. 50-482: Response to Notice of
' Violations 50-482/9624-01, -02 and -05 Gentlemen: l This letter transmits Wolf Creek Nuclear Operating Corporation's (WCNOC,5 response to Notice of Violations 50-482/9624-01, 02, and -05. Violation 9624-01 involves an operability evaluation for moisture intrusion into the turbine-driven auxiliary feedwater pump governor oil which was made without acknowledging or evaluating vendor requirements for the equipment. Violation 9624-02 involved Maintenance workers failing to follow procedures in not installing the spindle nut cotter pin in one of the main steam safety valves.
Violation 9624-05 involved the failure to accurately document the basis for why a change to the Updated Safety Analysis Report did not involve an unreviewed safety question.
WCNOC's responses to these violations are in the attachment. If you have any questions regarding this response, please contact me at (316) 364-8831, extension 4000, or Mr. Richard D. Flannigan at extension 4500.
Very truly yours,
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Otto /
OLM/jad Attachment cc: J. E. Dyer (NRC), w/a W. D. Johnson (NRC), w/a J. F. Ringwald (NRC), w/a J. C. Stone (NRC), w/a 97- OT N RO. Box 411/ Burhngton, KS 66839 / Phone: (316) 364-8831 S* ., , An Equal opportunny Ernpooyer uf NCNET
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Attachment to WM 97-0025 Page 1 of 6 I
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I Reply to Notice of Violations 50-482/9624-01, -02, and -05 i
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I Violation 50-462/9624-01: An operability evaluation of moisture jatrusion into the turbine-driven auxiliary feadwater pump governor oil was made without acknowledging or evaluating vendor requirements for the equipment.
"A. 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 the circumstances, and shall be accomplished in accordance with tnese instructions, procedures, or drawings. ;
Procedure ADM C2-024, " Technical Specification Operability,"
requires operability determinations to include a determination of the requirement or commitment established for the equipment. ;
Contrary to the above, on December 6, 1996, at 2:38 p.m., the shift supervisor documented an operability determination for the turbine-driven auxiliary feedwater pump that identified a governor oil sample result of 3915 ppm water, but failed to acknowledge the ;
vendor's technical manual limit of 5000 ppm and an intrusion rate l of approximately 700 ppm per hour." ;
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Admission of Violation:
Wolf Creek acknowleoges and agrees that a violation of Criterion V of Appendix j B to 10 CFR Part 50 occurred on December 6, 1996, when an operability '
determination for the turbine-driven auxiliary feedwater pump failed to consider relevant information in the vendor's technical manual.
Reason for Violation: l l
l Root Cause:
The root cause for this event was personnel error on the part of the Shift Supervisor in that he did not exhibit a thorough questioning attitude. The :
Shift Supervisor accepted System Engineering input and conclusions without i requiring System Engineering to perform an Evaluation of Nonconforcing Conditions per procedure AP 28-001, " Evaluation of Nonconforming Conditions of Installed Plant Equipment." Poor communications between the Shift Supervisor and the System Engineer contributed to the Shift Supervisor's impression that no further information was needed to determine operability. All of the information evaluated by the System Engineer, concerning the ability of the turbine-driven auxiliary feedwater pump to perform its safety function, was not communicated to the Shift Supervisor.
The System Engineer had called the vendor, Dresser-Rand, to resolve the initial question of water intrusion in the turbine lube oil, but was unable to reach the appropriate person. The vendor manual, M-021-0086, available at the time of the event, indicated a limit of 5000 ppm water intrusion into the oil.
The system was experiencing a water-intrusion rate of 700 ppm per hour while the cumo was operating. The System Engineer then consulted a former employee of Dresser-Rand who is respected in the industry. That conversation led the System Engineer to conclude there was no operability concern, and that conclusion was given to the Shift Supervisor. On De. ember 12, 1996, Dresser-Rand faxed information to the System Engineer which clarified the acceptability limits for moisture intrusion.
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Based on the System Engineer's information, the log entry on December 6, 1996, briefly summarized the System Engineer's efforts to gather definitive
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Attachment to WM 97-0025 Page 2 of 6 l
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information, and the conclusion of the :e being no operability concern. On December 9, 1996, the Shift Supervisor supplemented the log entry to address concerns that the Decemoer 6, 1996, log entry was inadequate in that it did not meet the Manager Operations' expectations to make detailed log entries for operacility evaluations. The extended evaluation on December 9, 1996, confirmed that the turbine-driven auxiliary feedwater pump was operable. i l
Correcti~e Steps Taken: I I
Procedure ADM 02-024, Revision 3, " Technical Specification Operability," was I revised and is now AP 26C-004, Revision 0, " Technical Specification I Operability." This revision added form APF 26C-004-01, " Technical Specification Operability Screening Checklist," which aids the Shift Supervisor in ensuring thoroughness of operability evaluations and consistency in documentation. This revision states that "When Technical Specification Operability is in question. . . an entry shall be made in the Shift Supervisor Log defining the concern, the potentially degraded safety function, the Technical Specification and/or USAR section affected, and the justification for the operability determination."
Performance Improvement Request (PIR 97-0181) which documented corrective actions to prevent recurrence of this event, was placed into Operations required reading on February 28, 1997.
The Shift Supervisor was counseled on December 7, 1996, and the Auxiliary j Feedwater backup System Engineer was counseled on February 26, 1997, regarding ;
lessons learned from this event.
l Corrective Steps to Be Taken:
System Engineering will issue a revision to vendor manual M-021-0086 ensuring the manual reflects the correct information regarding acceptable moisture l content in the turbine lube oil. This will be complete by July 25, 1997
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. Attachment to WM 97-0025 Page 3 of 6 l
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Violation 50-482/962' 02: The failure by Maintenance workers to follow procedures in not installing the spindle nut cotter pin in one of the main steam safety valves.
"B. Tecnnical Spec;ficat an 6.8.1.a states, in part, that written procedures snall be established and implemented covering the o
applica'le procedure * recommended in Appendix A of Regulatory i Guide 1.33, Revision 2.
Regulatory Guide 1.33, Appendix A, Section 8.b. (a) (x), requires procedures for surveillance tests of main steam safety valves.
Surveillance Procedure STS MT-008, " Main Steam Safety Valve
. Settings," Revision 5, Step 7.11.1, required workers to install the spincie nut and spindle nut cotter pin.
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Contrary to the above, on March 3, 1993, maintenance workers
failed to install the spindle nut cotter pin on Valve AB V0046."
Admission of Violation:
Wolf Creek acknowledges that a violation of Technical Specification 6.8.1.a occarred on March 3, 1993, when Maintenance workers failed to install the l
, spindle nut cotter pin on Valve ABV0046.
Reason for Violation:
Root Cause:
During November 1996, Wolf Creek inspected all of the Main Steam Safety Valves (MSSVs) specifically for verification that all spindle nut cotter pins were in i place. This was the result of information of an event at another plant. l
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During that inspection, one cotter pin was found missing on Valve ABV0046.
The root cause is failure to follow procedure due to procedure weakness.
Steps are included in the procedure to install the cotter pin. However, the procedure, STS MT-008, Revision 7, " Main Steam Safety Valve Settings," had some weaknesses that could have contributed to the event. Section 4.0, ,
" Precautions / Limitations," did not include a precaution that not installing :
the spindle nut cotter pin could, following an actuation, result in the valve I not completely reclosing. Prior to step 8.11.1 which called for installation of tne cotter pin, no information alerted the mechanic of the importance of ensuring the cotter pin is installed. After reassembly, the Quality Control verification only verified that a tag and safety seal were installed.
Corrective Steps Taken:
The spindle nut cotter pin was installed on valve ABV0046.
All installed and spare MSSVs were inspected to ensure the spindle nut cotter pin was installed.
Procedure STS MT-008, " Main Steam Safety Valve Settings," Revision 8, was issued December 20, 1996. This revision strengthens the procedure with an auded note of precaution of specific information on the importance of the cotter pin being installed; an added specific sign-off for the installation of the cotter pin; and an added independent verification by Quality Control for the installation of the cotter pin.
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Attachment to WM 97-0025 Page 4 of 6
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Corrective Steps to Be Taken:
Maintenance personnel who supervise work on the subject equipment, and Quality
, Control inspectors who are qualitied to independently verify the installation of the cotter pin, will receive retraining on this issue to reinforce the i importance of the function of this cotter pin, Past procedure weaknesses will be part of this training to be completed by March 14, 1997 Mechanical Maintenance and Maintenance Planning personnel who may perform or
- supervise performance of these functions will be retrained in the reassembly i aspect of STS MT-008, Revision 8, " Main Steam Safety Valve Settings." This will be completed by March 14, 1997
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Procedure MCM M140-01, Revision 1, " Main Steam Safety Valve Maintenance," will be revised to provide further enhancements to correct similar weaknesses
. regarding installation of the spindle nut cotter pin. This will be completed j j by March 14, 1997.
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Attachment to WM 97-0025 Page 5 of 6
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Violation 50-482/9624-05: The failure to accurately document the basis that a change to the Updated Safety Analysis Report did not involve an unreviewed safety question.
"C. 10CFR 50.59 requires, in part, that licensees maintain a written safety evaluation which provides the bases for the determination that the change does not involve an unreviewed safety question.
Contrary to the above, on July 3, 1996, the licensee changed i Section 16.3.1.5 and other sections of the Updated Safety Analysis Report without documenting an adequate basis that an unreviewed safety question was not involved in that the unreviewed safety question determination contained substantive errors.
Admission of Violation:
WCNOC acknowledges and agrees that a violation of 10CFR 50.59 occurred on July 3, 1996, when Section 16.3.1.5 and otner sections of the Updated Safety Analysis Report (USAR) were changed without documenting an adequate basis that an unreviewed safety question was not involved in that the unreviewed safety question determination contained substantive errors. ,
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Reason for Violation:
Root Cause:
The root cause of this event is personnel error in that the preparer and approver of the Unreviewed Safety Question Determination (USQD) 59 96-0075 for USAR Change Request 96-051 did not comply with section 5.2.4 and 6.7.2 of AP 26A-003, " Screening and Evaluating Changes, Tables, and Experiments."
Procedure AP 26A-003, Revision 1, " Screening and Evaluating Changes, Tables, and Experiments," indicates that preparers and approvers, by their signatures, certify that the information contained in the Regulatory Screening and USQD is complete and accurate. The USQD 59 96-0075 stated that the change to delete a requirement to report to the NRC on an inoperable monitoring system was not a regulatory requirement. However, for the Regulatory Guide 1.133, Section 5.b, WCNOC states that this reporting requirement should be in technical specifications. WCNOC USAR, Appendix 3A, indicates that WCNOC meets the requirements of this Regulatory Guide, with the exception being that this specification has been relocated to the USAR.
Corrective Steps Taken:
Performance Improvement Request (PIR) 97-0083 was initiated to evaluate this event.
The preparer and approvers of the USAR Change Request, Regulatory Screening, and USQD have been counseled relative to the errors made in the USAR Change Request and associated Screening and USQD.
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Attachment to WM 97-0025 i i
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e Corrective Steps to Be Taken:
USAR Change Request 96-051 will be reviaed to include necessary changes to i USAR Appendix 3A, as will the associated 50.59 Screening and USOD. This will !
be ccepleted by March 14, 1997.
The content of all other USQDs performed by the preparer of USOD 59 96-0075 will be reviewed for error. This will be completed by March 14, 1997. j Since the occurrence of this problem, Engineering has implemented a Work Product Evaluation Process. Letter WM 96-0081, Response to Enforcement Action EA 96-124," describes the implementation of this process.
Engineering Work Product Evaluations are used to re-inforce expectations l involving completeness of documentation of work, attention to detail, and procedural compliance. Engineering Work Product Evaluations will assist in j preventing problems such as the error made in USOD 59 96-0075, j
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