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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
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UNITED STATES t>" 909
- IS NUCLEAR REGULATORY COMMISSION
,$ REGION IV
- , E 611 RYAN PLAZA DRIVE, SUITE 400
4 AR LINGTON, T EXAS 76011-8064 9***** June 4,1998-i Otto L. Maynard, President and
[ Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66839 SUBJECT: NRC INSPECTION REPORT 98-07
Deari.5 Maynard:
Thank you for your letter of May 29,1998, in response to our April 30,1998, letter. We !
I have reviewed your reply and find it responsive to the emergency preparedness concerns identified. We will review the implementation of your actions during a future inspection.
Sincerely, JWu Blaine Murray, Chief Plant Support Branch Division of Reactor Safety Docket No.: 50-482 License No.: NPF-42 cc:
I Chief Operating Officer Wolf Creek Nuclear Ooorating Corp.
P.O. Box 411 Burlington, Kansas 66839 Jay Silberg, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Washington, D.C. 20037 Supervisor Licensing )
Wolf Creek Nuclear Operating Corp. I P.O. Box 411 Burlington, Kansas 66839 9906090126 990604 PDR ADOCK 05000482 a PDR
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Wolf Creek Nuclear -2-Operating Corporation
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Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Rd.
Topeka, Kansas 66604-4027 Office of the Governor
[. . State of Kansas
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Topeka, Kansas 66612 Attomey General Judicial Center
!301 S.W.10th .
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2nd Floor Topeka, Kansas 66612-1597 County Clerk Coffey County Courthouse Burlington, Kansas 66839-1798 Vick L. Cooper, Chief Radiation Control Program Kansas Department of Health
- and Environment Bureau of Air and 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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Wolf Creek Nuclear -3-Operating Corporation DISTRIBUTION w/coov of licensee's May 29.1998:
DMB (IE35)
Regional Administrator WC Resident inspector DRS Director DRS Deputy Director ,
l DRP Director SRI (Callaway, RIV)
Branch Chief (DRP/B)
DRS-PSB Project Engineer (DRP/B)
, Branch Chief (GRP/TSS)
i l MIS System RIV File DRS Action item File (98-G-0070)(Hodges)
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DOCUMENT NAME: R:\ WC\WC807AK,THA l
- To receive copy of document, Indicate in box:"C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy l RIV:PSB E C:DRS\PS 1 THAndrews:nh 4% BMtyray D 06/3/98 064f98 I OFFICIAL RECORD COPY l
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{ O Wolf Creek Nuclear -3-Operating Corporation DISTRIBUTION w/coov of licensee's May 29.1998:
l !DMB (IE35)-
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Regional Administrator WC Resident inspector DRS Director DRS Deputy Director j DRP Director SRI (Callaway, RIV)
Branch Chief (DRP/B)
DRS-PSB Project Engineer (DRP/B)
Branch Chief (DRP/TSS)
MIS System RIV File DRS Action item File (98-G-0070)(Hodges)
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DOCUMElJT NAME: R:\_WC\WC807AK.THA l To receive copy of document, indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy l RIV:PSB lE C:DRS\PS1 l l THAndrews:nh 4% BMurray D l 06/3/98 064f98 i OFFICIAL RECORD COPY j I
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W$LF CREEK NUCLEAR OPERATING CORPORATION Otto '
Presdent and Chief Executive Othcer WlAY 2 91998 l
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WO 98-0048-v, g
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U. S. Nuclear Regulatory Commiss: ,on ;c ,
ATTH: Document Control Desk L_- 'r',
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Mail Station Pl-137 Washington, D. C. 20555 Reference: Letter dated April 30, 1998, from Blaine Murray, NRC, to O. L. Maynard, WCNOC Subject: Docket No. 50-482: Response to Inspection Followup Item 50-482/9807-01.
Gentlemen:
This letter transmits Wolf Creek Nuclear Operating Corporation's (WCNOC)
response to Inspection Followup Item (IFI) 50-482/9807-01. IFI 9807-01 identified a performance weakness involving one crew that failed to properly assess plant conditions to permit classification of a general emergency. This occurred during the use of the simulator for the emergency preparedness inspection. WCNOC's responte to this IFI is provided in Attachment I.
Attachment I also contains WCNOC's response to four additional items discussed in the inspection report: 1) Three self-contained breathing apparatus (SCBA)
cylinders had low air pressure, 2) A Shift Supervisor did not know the spare air cylinder storage locations, 3) Silver-:colite cartridges were found with no shelf-life expiration date, and 4) WCNOC does not perform SCBA fit testing.
I If you have any questions regarding this response, please contact me at (316) l 364-8831, extension 4000, or Mr. Michael J. Angus at extension 4077. l l
. Very truly yours,
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.to OLM/r1r Attachment cc: M. D. Johnson (NRC), w/a E. W. Merschoff (NRC), w/a J. F. Ringwald (NRC), w/a K. M. Thomas (NRC), w/a (% - I 6 0 4>
P 0, Box 411/ Burhngton, KS 66839 / Phone, (316) 364 8831 An ELu-9-9bCOJopy alOpponunnyErnpioyerM/F/HCNET
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. e, (- Attachment I to WO 98-0048 Page 1 of'4
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Response to Inspection Report 98-07 Performance Weakness / Inspector Followup Item 9807-01 The cover letter on Inspection - Report 98-07 identifies the following excerpt as a " performance weakness," and on page 7 of the Enclosure to the Inspection
. Report, the excerpt is identified as an inspection followup item:
"Because this - [ operating) crew did not declew a general emergency, key elements of the emergency plan associated .v ith the general emergency (notification of offsite agencies and protective action recommendations)
were not demonstrated. 10 CFR Part 50, Appendix E.IV.F.2.g, requires that deficiencies or weaknesses identified during drills or exercises shall be -
corrected. The review of measures to be taken by the licensee was identified as an inspection followup item (IFI 50-482/9807-01)."
l The inspection report states on page 8 that the second crew declared the general emergency but exceeded the goal of 15 minutes to assess the plant condition to make the declaration. The declaration took 18 minutes, three minutes longer than the goal provided in NRC Emergency Preparedness Position No. 2. The inspectors acknowledged that the 3 extra minutes delay would not have significantly affected the protective action recommendation process, and that had the performance of the first crew not been considered, this issue would likely have only been a discussion item with the licensee. However, the inspectors considered that the delay was the result of the second crew having trouole assessing plant conditions. The inspectors pointed out that there may have been a common factor associated with assessing plant conditions for both crews.
Response to IFI 9807-01 WCNOC recognizes that during the Emergency Preparedness inspection of March 30 through April 2, 1998, the NRC observed that one crew had difficulty determining the presence of a 2000 scfm leak in the Containment boundary. The Containment pressure dropped approximately three psig while Containment temperature continued to increase. The crew considered the pressure trend to be due to the cooling effect of the Containment coolers. This resulted in the crew not declaring a general emergency classification for the scenario.
Immediately after the completion of the scenario, the crew critique discussed the Containment- pressure response and cooler operation. The crew then recognized that the only way the Containment coolers can decrease pressure is to decrease temperature.
The inspectors observed twv crews perform the scenario on the simulator. The first operating crew' observed by the inspectors misdiagnosed the Containment leak. Thel second crew correctly assessed plant ' conditions, but took 18 minutes to declare the generel emergency. Inspection Report 98-07 states that there may have been a common factor associated with assessing plant conditions based on the second crew taking 18 minutes to declare a general emergency.
WCNOC'does not believe that there is a common factor between the performance of _ the first and second crew. The same training scenario was used on nine operating crews during requalification cycle 98-3. Similar to the second crew, the other crews performing the same scenario correctly assessed. plant
- conditions, correctly characterized all applicable Emergency Action Levels, and met.WCNOC's expectations for-timeliness.
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' Attachmant I to WO 98-0048 Fage 2 of 4
WCNOC considers the failure to identify the Containment conditions to be a training issue for the crew involved. WCNOC does not agree that the three
, minutes used beyond the NRC's Emergency Preparedness Position No. 2 goal of 15 minutes is indicative of a weakness in assessing plant conditions and should I not be associated with the first crew that misdiagnosed plant conditions. As
! stated at the exit meeting, WCNOC's position is that although timeliness is
! important, a correct and accurate declaration is paramount during emergency i conditions. The second crew met these expectations and appropriately l diagnosed the event in a timely manner.
l l Corrective Actions l In response to the ,e crew that misdiagnosed the Containment leak, WCNOC has
! added training on parameters and trends that should be used to determine if a breach of Containment exists to requalification cycle 98-4. Requalification cycle 98-4 will be completed by July 1, 1998.
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! a, Attachment I to WO 98-0048 l Page 3 of 4
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Additional Information Low Pressure in SCBA Air Cylinders
l During the inspection, one Self Contained Breathing Apparatus (SCBA) cylinder l in the Control Room Emergency Planning storage area was found to be below the acceptable pressure range. In accordance with AI 10-001, " Fire Brigade Monthly Inventory," these cylinders are checked on a monthly basis. The cylinder in question was last checked on March 3, 1998, and was found to be within the acceptable range. On March 30, 1998, the cylinder was found to be l
out of range. Investigation determined that the valve was fully closed. The
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cylinder was replaced with a fully charged cylinder, and the pressure gauge monitored for five days at the low pressure and no further decrease in pressure occurred.
The cylinder was then recharged to full operating pressure. It was noted that the pressure dropped in approximately three days to an unacceptable level as found on March 30, 1998. This indicated that a high pressure leak in the valve was present. The vcive was dismantled and inspected. A sealing o-ring was found to have a small tear on the seating side. The o-ring was replaced, and the cylinder was charged to full operational pressure. The cylinder now appears to be holding the required amount of air. This cylinder has been in use for one and half years and had shown no previous air loss.
Two additional fire brigade cylinders were identified as indicating questionable pressures. The two cylinders, located in the fire brigade storage area, .were known to be approaching the lower acceptance level and were being monitored. They were scheduled to be replaced or refilled on March 31, 1998. When these t'wo cylinders were replaced, the pressure indicator was found to be in the middle of the gauge between 30u0 and 4000 psi, which is the normal change-out range. The cylinders were refilled and no leaks were
- identified. The cylinders have since maintained their pressure.
The SCBA vendor was contacted for assistance, but could not identify any additional causes for the pressure decreases in the cylinders. The fire brigade SCBAs were purchased three years ago and the Emergency Planning SCBA was purchased one and one half years ago. This was the first time that pressure problems have occurred. The maintenance record program and Performance Improvement Request (PIR) program will track any deviations in air cylinder pressures for potential continuing trends.
Location of Replacement Air Cylinders The inspectors noted a concern with a Shift Supervisor's familiarity with spare air cylinder locations. An e-mail was sent to each Shift Supervisor on April-3, 1998, explaining the location of spare air cylinders. In addition, the SCBA lesson plan for fire brigade and non-fire brigade use was reviewed and updated identifying the storage areas of spare air cylinders.
Silver Zeolite Cartridge Storage Inspection activities indicated that the shelf life of the sealed silver zeolite and charcoal cartridges used in Emergency Planning may have expired.
WCNOC personnel further investigated this issue, and produced a letter dated November 2, 1988, from the vendor stating that the cartridges purchased by
'WCNOC "...have indefinite shelf life." Based on information from the inspector, WCNOC learned that the vendor now indicates that these cartridges have a ten year shelf life limitation, as stated in a letter included with each'new purchase of the silver zeolite cartridges. Because WCNOC had not
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' Attachment-I to WO 98-0048 Pa,ge 4 of 4
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madem a - recent purchase, personnel were unaware of this -ten year storage e..piration. A review of WCNOC's stock revealed that a number of cartridges
'had exceeded the ten year shelf life. This difference in storage conditions was' resolved to the inspector's satisfaction through communication with the vendor.
The entire stock of silver zeolite cartridges was ' examined. Replacement cartridges were ordered from the vendor, then properly distributed. During the shipping interim, a contingency plan for distribution of remaining silver zeolite cartridges throughout 'the ERO facilities was developed and communicated with the site Health Physics group. WCNOC personnel inspected Emergency - Planning storage cabinets for ..other materials which might need expiration dates; no new items were identified. In addition, WCNOC sent a message to alert . the rest of the industry of the shelf life expiration information on silver zeolite cartridges.
SCBA Fit Testing The inspection report discusses that WCNOC does not currently perform fit testing for SCBAs. Many guidelines exist for the use and testing of SCBAs.
WCNOC follows the OSHA requirements. The current OSHA requirements do not include fit testing of SCBAs. At the time of the inspection, WCNOC was in compliance with the -current OSHA regulations for a Respiratory Protection-Program (29 CFR 1910.134 ) . Prior to the NRC inspection, WCNOC was aware of the impending changes to the OSHA regulations. The required revisions will be processed and the date to be in compliance with the new OSHA standard of October 5, 1996, will be met. Necessary fit testing equipment has been purchased in preparation for meeting these new requirements.
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