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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: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 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 ML20207A8681999-05-25025 May 1999 Informs That NRC Ofc of NRR Reorganized Effective 990328. as Part of Reorganization,Division of Licensing Project Mgt Created 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
[Table view] |
See also: IR 05000482/1996018
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DEC 241996
Neil S. Carns, President and
Chief Executive Officer
Wolf Creek Nuclear Operating Corporation
P.O. Box 411
Burlington, Kansas 66839
SUBJECT: NRC INSPECTION REPORT 50-482/9618
Dear Mr. Carns:
Thank you for your letter of December 6,1996,in response to our letter and Notice
of Violation dated November 7,1996. We have reviewed your reply and find it responsive
to the concerns raised in our Notice of Violation. We will review the implementation of
your corrective actions during a future inspection to determine that full compliance has
been achieved and will be maintained.
Sincerely,
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P
. Dyer, Director
h J.Division of Reactor Projects
Docket No.: 50-482 !
License No.: NPF-42
cc w/ enclosure:
Vice President Plant Operations !
Wolf Creek Nuclear Operating Corp.
P.O. Box 411 :
Burlington, Kansas 66839 l
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Jay Silberg, Esq.
Shaw, Pittman, Potts & Trowbridge
2300 N Street, NW l
Washington, D.C. 20037 l
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Wolf Creek Nuclear -2-
Operating Corporation
Supervisor Licensing
Wolf Creek Nuclear Operating Corp.
P.O. Box 411
Burlington, Kansas 66839
Supervisor Regulatory Compliance
Wolf Creek Nuclear Operating Corp. ,
P.O. Box 411 '
Burlington, Kansas 66839
Chief Engineer
Utilities Division
Kansas Corporation Commission
1500 SW Arrowhead Rd.
Topeka, Kansas 66604-4027
Office of the Governor
State of Kansas )
Topeka, Kansas 66612
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Attorney General I
Judicial Center l
301 S.W.10th
2nd Floor
Topeka, Kansas 66612-1597
County Clerk
Cof fey County Courthouse
Burlington, Kansas 66839-1798
Public Health Physicist
Division of Environment
Kansas Department of Health
and Environment
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
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Project Engineer (DRP/B) MIS System
Branch Chief (DRP/TSS) RI V File
Leah Tremper (OC/LFDCB, MS: TWFN 9E10)
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DOCUMENT NAME: R:\_WC\WC618AK.JFR
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DEC 241996
bec to DMB (IE01)
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L. J. Callan Resident inspector
DRP Director SRI (Callaway, RIV)
Branch Chief (DRP/B) DRS/PSB
Project Engineer (DRP/B) MIS System
Branch Chief (DRP/TSS) RIV File
Leah Tremper (OC/LFDCB, MS: TWFN 9E10)
DOCUMENT NAME: R:\_WC\WC618AK.JFR
To receive copy of document, indicate in tp: "C" = Copy without enclosures *E" = Copy with enclosures "N" = No copy
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Neil S. " Buzz" Cams I
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Chairman, President and
Chief Executrve Omcer December 6, 1996 i
WM 96-0137
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U. S. Nuclear Regulatory Commission I
ATTN: Document Control Desk
Mail Station P1-137
Washington, D. C. 20555
Reference: Letter dated September 23, 1996, from
J. E. Dyer, NRC, to N. S. Carns, WCNOC
Subject: Docket No. 50-482: Response to Notice of
Violations 50-482/9618-02, -03, -04, and -07
Gentlemen:
This letter transmits Wolf Creek Nuclear Operating Corporation's (WCNOC)
response to Notice of Violations 50-482/9618-02, -03, -04, and -07. Violation
9618-02 concerns the failure to correctly remove power from a safety injection
pump discharge valve. Violation 9618-03 concerns the failure to maintain
containment integrity during core alterations. Violation 9618-04 concerns the
incorrect performance of a portion of the surveillance requirements specified
by Technical Specification 4.8.1.1.2.g (6) (c) , while at power. Violation 9618-
07 concerns the failure to perform required post modification testing.
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 4100, or Mr. Terry S. Morrill at extension 8707.
Very truly yours,
. gv-
Neil S. Carns
NSC/jad
Attachment
ec: L. J. Callan (NRC), w/a
W. D. Johnson (NRC) , w/a
J. F. Ringwald (NRC) , w/a
J. C. Stone (NRC), w/a g3Q
PO. Box 411 / Burhngton, KS 66839 / Phone: (316) 364-8831
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4 Recly to Notice of Violations 50-482/9618 -02. -03, -04, and -07
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l Violation 50-482/9618-02: The failure to correctly remove power from a
, safety injection pump discharge valve.
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l "A. Technical Specification 3.5.4 requires that all safety injection
j pumps be inoperable during Modes 5 and 6 with the reactor vessel
- head on. The pumps are to be made inoperable by securing the
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motor circuit breaker in the open position. The inoperable pump
- may be energized for testing or for filling accumulators provided
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the discharge at the pump has been isolated from the reactor
l coolant system by a closed isolation valve with power removed from
the valve operator or by a manual isolation valve secured in the
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closed position.
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Contrary to the above, on March 23, 1996, with the plant was in '
, Mode 5, operators discovered that Safety Injection Pump Discharge
! Valves EM HV-8802A and -8021A handswitches were tagged *Do Not
l Operate" closed, but still had power available to them. The pump
j motor circuit breaker was racked. closed so that safety Injection
Pump A could be started." '
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- W saion of Violation
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- Wolf Creek Nuclear Operating Corporation (WCNOC) acknowledges and agrees that
j a violation of Technical Specification 3.5.4 occurred in March 1996, when
i operators failed to remove power - from Safety Injection Pump Discharge Valves
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EM HV-8802A and -8821A. This event was self discovered and reported to the
j NRC in Licensee Event Report (LER) 96-004-00 (WCNOC Letter Number WM 96-0054,
- , issued on April 19, 1996).
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l Reason for Violation:
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Root Cause and Contributing Factors:
! See LER 96-004-00.
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j Corrective stens Taken and Results Achieved ]
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l In addition to the corrective actions documented in LER 96-004-00, the
! following actions have been implemented:
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1. The ' er t director involved with the clearance order was counseled. l
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4 2. Tht: shift supervisor that authorized the change to the clearance order was
- counseled.
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3. The individuals responsible for implementing the corrective actions were
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counseled.
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Attachm3nt to WM 96-0137
/ Page 2 of.7
The corrective actions as documented in LER 96-004-00 and the additional
corrective actions documented above, are considered adequate for compliance
with the requirements of the technical specifications. The paragraphs below
describe additional measures being undertaken to enhance the root ,
cause/ corrective action process. )
Corrective Stoos That will Be Taken And Their Excocted Cosapletion Dates:
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Discussions, to review the root cause determination process, will be held with 1
Operations department supervision. These discussions will focus on lessons I
learned and procedural requirements associated with the root cause l
determination and appropriate corrective actions. This action will be )
completed by December 31, 1996. I
Performance Improvement Request (PIR) 96-2592 was issued to address the
mismatches between the root causes and corrective actions documented in LERs
96-004-00 and 96-005-00. This PIR will be placed in Operations required
reading to familiarize the staff with the errors made and the lessons learned.
The corrective action program is being modified to include the following:
1. The formation of a formal corrective action review board. This board chair
will be assigned by the Chief Operating Officer. This board will review
root cause determination and corrective action plan for all significant
PIRs. This action was implemented on November 30, 1996.
2. Organizational changes will be implemented such that each group within the
Plant Operations Organization will have personnel whose primary
responsibility will be to support the corrective action process. This
action will be completed by January 31, 1997.
3. Additional training will be conducted for all managers (one day) and
individuals responsible for implementing ~ the corrective action program
(three days). This action will be completed by January 31, 1997.
Safety Sianificance:
During the time frame that the Technical Specification for cold over-pressure
protection was not being met, administrative controls remained in place to
protect the vessel from over-pressurization. The discharge valves EM HV-8802A
and EM HV-8821A were tagged closed, and no additional volume could have been
added to the vessel. Even if the SI pumps were inadvertently started, the
closed discharge valves would have prevented volume addition to the vessel.
Therefore, the safety significance of this event is low.
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Attachm2nt 'o WM 9F-0137
,~/. Pcga 3 of 7
- Violation 50-482/9618-03
- The failure to maintain containment integrity
during core alterations.
"B. Technical Specification 3.9.4 requires that each penetration
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providing . direct access from the containment atmosphere to the
l outside atmosphere be closed by an isolation valve, blind flange,
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manual valve, or be capable of being closed by an operable
automatic containment isolation valve. This Technical
[ Specification is applicable during core alterations or movement of
irradiated fuel within containment.
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Contrary to the above, on March 14, 1996, the licensee found that
"
operators had directed the opening of Containment Isolation Valve
, BM-V046 to allow draining of Steam Generator B and C. Core
j alterations were in progress at the time the valves were open."
!
W saion of violation:
WCNOC acknowledges and agrees that a violation of Technical Specification
3.9.4 occurred in March 1996, when operators had incorrectly directed the
opening e'. a containment isolation valve (resulting in a loss of containment
integrity) during core alterations. This event was discovered and reported to
the NRC in LER 96-005-00 (WCNOC Letter Number WO 96-0096, issued on June 19, ,
1996).
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Reason for Violation
Root Cause and Contributing Factors:
In addition to the root cause and contributing factor, as documented in LER
96-005-00, the following contributing factor has been identified:
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System Operating Procedure SYS BM-201, " Steam Generator Draining," failed to !
clearly establish initial conditions necessary to allow the draining of the
steam generators. Because this contributing factor was not identified the
responsible personnel failed to perform a review to determine if other similar
procedures failed to establish adequate initial conditions prior to
performance of required actions.
Corrective Stecs Taken and Results Achieved i
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In addition to the corrective actions documented in LER 96-005-00, the I
following corrective actions have been implemented:
A review was conducted of similar procedures and two additional procedures
needed revision. They are:
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1. SYS EF-420, " Draining ESW Trains"
2. SYS EG-401, " Component Cooling Water System Drain Procedure" i
The procedures will be revised by December 31, 1996.
The errors associated with the initial root cause evaluation were discussed
during a group meeting with the Operations' Support Staff.
Attachm:nt to WM 96-01'J7
/ Pega 4 of 7
Safety sianificanen
The water drainett from Steam Generators B and C was non-radioactive, secondary
system water. Valve BM-V046 was open for one hour and twenty-four minutes.
During that time, the flow of water varied and, toward the end of the event,
flow reduced to a trickle. Dee to the piping configuration and atmospheric
conditions in bots buildings, loop seals formed during the draining process
and no direct air to air access occurred. Additionally, no fuel handling
accident occurred during this time, and no increase of radioactivity was noted ,
by the containment radiation monitors. The health and safety of the public j
and plant safety were assured during this event. I
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Attcchm:nt to WM 96-0137
l Paga 5 of 7
Violation 50-482/9618-04: The incorrect performance of a portion of the
surveillance requirements specified by Technical
Specification 4. 8.1.1.2.g (6) (c) , while at power.
- C. Technical Specification 4 . 8 .1.1. 2 . g . ( 6 ) . ( c ) requires testing
during shutdown to verify that all automatic diesel generator
trips except those that remain during emergency operation be
automatically bypassed upon loss of voltage on the emergen#: / bus
concurrent with a safety injection actuation signal, once 1er 18
months.
Contrary to the above, on July 23, 1996, while the plant was at
approximately 100 percent power, technicians performed Work
, Packages 114086 and 114087, which accomplished a portion of the ,
surveillance required by Technical Specification i
4. 8.1.1. 2.g . (6 ) (c) . " l
Admission of violation
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WCNOC acknowledges and agrees that a violation of Technical Specification j
3.8.1.1 occurred on July 23, 1996, when technicians performed Work Packages l
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114086 and 114087, in an attempt to meet the testing requirements of Technical
Specification 4. 8.1.1.2.g (6) (c) . This evt.nt was self discovered and reported
to the NRC in LER 96-007-00.
Reason for Violation:
Root Causes:
The root causes of this event were determined to be:
1. Inadequate pre-job briefing: During the pre-test review and discussion
between the shift supervisor and system engineering, the technical
speciff<: tion requirement that this testing be performed *during shutdown"
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was not considered. The decision, that the work package testing was
equivalent to Surveillance Procedure STS KJ-001A, ' Integrated D/G and
Safeguards Actuation Test-Train A," which can only be performed when
shutdown, was incorrect.
1. Tne failure to establish adequate administrative controls: AP 29B-003,
" Surveillance Testing," allows credit for meeting surveillance requirements
by alternate means. Section 6.2.3 of this procedure provides guidance for
situations where " tests / events" may be approved as satisfying technical
specifications. These guidelines require the designation of a * Test
Performer" who is responsible for reviewing the test / event for credit.
This review, as described in the procedure, only requires the Test
Performer to compare the test / event to the plant procedure incorporating
the same requirements. In this case, the work package test was c.ampared to
only a single section, Attachment M - Step Mll, of STS KJ-001, and found to
e meet the requirements for that step of the procedure. This comparison was
used as the basis for taking credit for meeting the technical specification
surveillance requirement. The procedure did not require review of the
applicable technical specification requirements.
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, Attachm:nt to WM 96-0137
f Pega 6 of 7 i
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3. An inappropriate organizational culture Following recognition that the
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technical specifications required the testing to be performed "during l
shutdown,"- WCNOC personnel justified . the acceptability of this testing i
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based. on compliance with the perceived intent of the technical ;
i specifications. The basis clearly acknowledged that the testing did not *
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achieve verbatim compliance with technical specifications. ,
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2 Corrective Actions Taken And Results Achieved: ,
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1. On November 6, 1996, the Chief Operating Officer issued Letter WO 96-0146,
l " Compliance With Requirements." This letter clearly communicated, to all i'
personnel, the requirement regarding literal compliance with Title 10 of
the Code Of Federal Regulations, technical specifications and the Updated )
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Safety Analysis Report. 1
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1 Corrective Stoos That Will Be Taken And The Date when Full Compliance Will Be
3 Achieved:
) 1. The process of taking credit for meeting surveillance requirements by
alternate means, as detailed in AP 29B-003 will be evaluated and revised to
j limit the use of " credit sheets." The use of work package tasks, or other
i documents not subject to the review and approval requirements for
i Surveillance procedures, will be prohibited. A detailed review of
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applicable Technical Specification requirements will be required as part of
the " credit" process.
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2. Applicable operations procedures will be reviewed and revised as necessary
j to require that any testing to satisfy surveillance requirements on
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inservice equipment be performed in accordance with an approved procedure. l
(Similar to controls currently in place for maintenance on inservice d
j equipment - reference AP 16-001, " Control of Maintenance," section 6.6.2-4,
- and AP 16C-003, " Work Package Task Planning," section 6.2.3.1).
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3. LER 96-007 will be revised to address that the testing performed on July
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i 23, 1996, which was a corrective action for the failure to perform this
surveillance during refueling outage VIII, did not fulfill the requirement
to perform the test "during shutdown," but did demonstrate operability of
j the emergency diesel oenerator volts / hertz relays. l
The above discussed actions will be completed by January 31, 1997.
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safety sienificance: l
) The failure to perform the post modification operability testing did not :
. result in any adverse consequences to the plant. No systems were rendered
i inoperable, and no equipment was damaged. The relays were individually tested
l upon completion of the modification installation process to assure their
functionality. The post-modification testing performed on July 23, 1996,
demonstrated the relays were correctly installed and were operable. Based on
- the results of the testing WCNOC is confident that if a condition had occurred
f between the time of installation and the time of testing, the relays would
have been bypassed and the EDGs would have started and functioned as required.
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Attachmsnt to LH 96-0137
p Paga 7 of 7
Violation 50-482/9618-07: The failure to perform required post f
modification testing.
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"D. Technical Specification 4. 8.1.1. 2.g . (6 ) . (c) requires testing I
during shutdown to verify . that all automatic diesel generator
trips except those that remain during emergency operation be l
automatically bypassed upon loss of voltage on the emergency bus. j
concurrent with a safety injection actuation signal, once per 18 !
months. j
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Contrary to the above, on July 23, 1996, the licensee found that j
the required testing had not been performed for the volts per i
L hertz relays which had been installed in the two emergency diesel
generator control circuits during Refueling Outage VIII in ,
February 1996."
W ssion of Violation:
WCNOC acknowledges and agrees that a violation of Technical Specification
4.8.1.1.2.g. (g) . (c) . occurred during Refueling Outage VIII, when WCNOC failed
to perform the require post modification testing on the volts / hertz relays
prior to returning to power. This event was self discovered and reported to
i the NRC in LER 96-007-00 (WCNOC. Letter Number WO 96-0118, issued on August 22, 1
l 1996).
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l EggmRD for Violation (Root Cause) and Corrective Steps Taken and Results
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L Aeved
, LER 96-007-00 describes the root cause and corrective steps taken and results
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achieved.
Safety Sicrnificance :
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t The failure to perform the post modification operability testing did not
result in any adverse consequences to the plant. No systems were rendered
inoperable, and no equipment was damaged. The relays were individually tested
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upon completion of the modification installation process to assure their
l functionality. The post-modification testing performed on July 23, 1996,
demonstrated the relays were correctly installed and were operable. Based on !
the results of the testing WCNOC is confident that if a condition had occurred f
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between the time of installation and the time of testing, the relays would
have been bypassed and the EDGs would have started and functioned as required.
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