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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] |
Text
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%, ,? AR LINGTON. TE X AS 76011 8064 DEC 9 1996 Neil S. Carns, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66839
SUBJECT:
MANAGEMENT MEETING
SUMMARY
This refers to the meeting conducted in the Region IV office on December 6,1996. This meeting related to your corrective action process and safety system functional assessment of the auxiliary feedwater system. The meeting was beneficialin providing us with an understanding of your goals, and changes to achieve those goals, in your corrective action process including your Plant Safety Review Committee, as well as the status and findings associated with the functional assessment of the auxiliary feedwater system.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter will be placed in the NRC's Public Document Room.
Should you have any questions concerning this matter, we will be pleased to discuss them with you.
Sincerely, J. E. Dyer, Director Division of Reactor Projects
Enclosures:
- 1. Attendance List
- 2. Licensee Presentation ec:
Vice President Plant Operations Wolf Creek Nuclear Operating Corp.
P.O. Box 411 Burlington, Kansas 66839 9612120378 961209 PDR ADOCK 05000482 p PDR
o Wolf Creek Nuclear Operating Corporation Jay Silberg, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW l Washington, D.C. 20037 '
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 I Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Rd.
Topeka, Kansas 66604-4027 Office of the Governor i State of Kansas i Topeka, Kansas 66612 Attorney General Judicial Center 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
. 1
's Wolf Creek Nuclear Operating Corporation Mr. Frank Moussa Division of Emergency Preparedness 2800 SW Topeka Blvd Topeka, Kansas 66611-1287 i
4 DEC 9 1996 i Wolf Creek Nuclear Operating l Corporation g;bcc.to DMB (IE45)y7w bec distrib by RIV:
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)
PAO SLO l
l l
1 To receive copy of document. Indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy PE:DRP/B C:DRP /) D:DRP _ _ l DNGraves:cmjf) WDJohngon JEDyer (M7 12/ 6/96 12/(g /96 12/9 /96 OFFICIAL RECORD CONY 120004
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DEC 9 1996 Wolf Creek Nuclear Operating Corporation bec to DMB (IE45) bec distrib. by RIV:
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)
PAO SLO i
l To receive copy of document, indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy PE:DRP/B C:DRP /) D:DRP _ .
i)NGraves; cmp) WDJohnfon JEDyer @7 12/ b /96 12/9 /96 12/9 /96 OFFICIAL F;ECORD COPY
Enclosure 1 MEETING: WOLF CREEK NUCLEAR OPERATING CORPORATION
SUBJECT:
CORRECTIVE ACTION PROGRAM /SSFA STATUS l l DATE: DECEMBER 6, 1996 ATTENDANCE LIST (PLEASE PRINT CLEARLY)
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Corrective Action Program:
Areas for Improvement .
eChallenges:
Trending Resource Allocation Planning and Scheduling of Resources Root Cause analysis Ownership of Corrective Action Program Management oversight t
4 i l
Corrective Action Program:
Improvements .
i e Electronic initiation document for Performance Improvement Requests (PIRs}
(9-16-96}
e Electronic initiation increases ease of tracking and trending (1C-14-96}
e Resource loading of PIRs (1st qtr '97}
e Integrated work control software (4th qtr '97) 5
.j Corrective Action Program:
Improvements
.l e PIR Coordinators assigned in each line organization (11-22-96) e PIR Coordinators will track and trend PIRs (1st qtr '97) e Failure Prevention Inc. (FPI) will conduct Root Cause and Causal Factors training for PIR Coordinators and line management (1st qtr '97}
e Quarterly sampling of PIRs by PIR Coordinators (1st qtr '97)
Corrective Action Program:
Improvements I E
e Performance Indicators o Corrective Action Review Board:
Membership: Plant Manager (chairman),
VP Engineering, Director Site Support, Manager Pl&A, and subject PIR Manager Reviews Root Cause, Causal Factors, and Corrective Actions for each Significant PIR Teaches and re-inforces proper corrective action methods, and sets standard for the Site 7
l
KEY Elements eComprehensive Corrective l Action Program
- eLine Management Ownership, and involvement in the program I
8
PSRC:
Purpose and Scope e Advises Plant Manager on all matters related to Nuclear Safety, per Technical Specification 6.5.1 e Sets performance standards and teaches the organization the attributes of safe plant operation 9
PSRC:
Improvements e New PSRC Chairman Recent INPO loaned employee (12 plants}
e ' Conduct Standard' under development (1st qtr '97)
Input from Chief Operating Officer and Plant Manager to ensure short term improvements were implemented right away Use of industry best practices to ensure that PSRC provides maximum value in their reviews e Line Organizations will present materials i
10
PSRC:
Improvements .
e Reviews selected topics each Quarter to assure Plant is operated safely (1st qtr '97):
Training performance by organization System Health Self Assessments Audits and Surveillances Regulatory findings Performance Trends
- Corrective Action 11
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O I; Auxiliary Feedwater System O
Functional Assessment 0
o Status 0
o , December 6,1996 0
0 0
O iA O
O O i 0
O l 0
0 iA ALSFA Commitment Sources a
O[
O E*J m Enforcement Conference meeting of May 8 10,1996 (Icing Event) 0 h oO 0
m LER 96-006, Roll Pin m LER 96-007, Missed PMT E },
0 m NEIIndustry Initiative to Address g
o License Basis Conformance Issues O
A O
o 2 U
O O
O 8 A Most Risk Significant Systems 0
O O{
0 EJ System Functional Assessment 0 m Auxiliary Feedwater a ALSFA(12/31/96) o a Stand'oy Diesel Generators a EDSFA(91/92)
O o a Essential Service Water a Planned (6/30/97)
S , a Component Cooling Water a Planned (12/31/97) .
O m Emergency Fuel Oil a EDSFA(91/92) 0 m Residual Heat Removal u Planned (4/30/98)
O m Diesel Building HVAC a EDSFA(91/92) o a Auxiliary Turbines a ALSFA(12/31/96)
O O
O 3 0
~
---.-7 0
O O
O A Purpose O{
O gaJ m Assess agreement of USAR with the design O
basis and current design output documents 8S 0
m Assess adequacy of current design assumptions o m Assess effectiveness of the testing and E{
S surveillance program to verify design basis (active functions) 0 o u Assess effectiveness of our operating o experience program 0
O O 4 .
O
O i O
O 0
A Additional Tasks 0 m Assess if design changes effectively addressed spare parts 0
and procurement. In addition, determine if design changes O are correctly reflected in vendor manuals and drawings 0 m Verify the Technical Specification requirements for the 0 AFW are met by current AFS surveillance testing U m Survey USQDs, OIRs and TS clarifications to determine if o they agree with the design and licensing bases of the plant O , a Evaluate the targeting and prioritization tool and the work 0 Product evaluation tool O m Review a sample of completed design modifications to g ensure necessary post modification testing was completed O m Assess the adequacy of equivalency evaluations O
O O
0 5 O
J
Aux N CONTAWMENT OUTSIDk IUX BLDG ALMV-5 ALMV-34 MOTOR PUMPB 500 GPM I GENERATOR FAI ALMV4 AL HV-30 D
V TRAIN LSP 1r ESSENTIAL SERVICE } ' s Jk WATER IJ MAW AL-HV 31
~~~~~""-~"---l FEED
.g. TRAIN ]gp i GENERA OR g
J SE } hF9 M GPM FM ! A WATER ALMW4 MOTOR FC 3 AL HV-35 b s M
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MAIN MAIN ST*AM ST* ALMV-9 p-_..@ . .
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O Assessment Team iA l 8 =====
iS 0
0 3 Review Panel Members:
l 0 Abdy Khanpour-INPO Britt McKinney - Piant Manager '
O Biii ausseii- consultant nick Muench - VP Engineering Jim Kammer- Duke Power Brad Smith - Project Engineer O Mark Kachmar- Westinghouse Brad Norton - Manager O
l 0 1
O
- Previous or current Estimated Workforce IIours Expended to Date: 8120 0 SRO license or certified individual Estimated Workforce Ilours Remaining: 1760
(
0 7 l 0 l
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I . .
O O
O Relevant Findings to Date O
A
, O Ef; m 48 USAR discrepancies O
o u 3 LERs O
O m 0 Apparent Design Bases issues O
m 0 Unreviewed safety issues O 3 0
0 0
0 lA O
O O 8 0
~
O O ,
O 0
A License Basis Review 0[E; 0
O a Assume all requirements were established in license S documents in place at time ofinitial license.
O m Identify differences between the USAR and the FSAR 0 '
s Strategy will verify the USAR is currently accurate O m Review the present license basis to identify functional S requirements.
0 m Identify active functions design bases from the USAR O
iA O
O O 9 0
O O
O O
A License Basis Review Observations O
Sf; a Approximately 35 USAR corrections noted 0
o a Problems noted were typically:
0 o + Editorial 0
0 + Typographical 0 + Some technical changes during conversion 0 process that do not have specific USQD o evaluations referenced iA O
O O 10 0
O O
D 0
A RCMS Review Conclusions 0
Sf; a No USAR cLiscrepancies noted O
o a No cases were found in which we failed to meet a commitment o a 10 administrative problems with RC MS/Procec ure '
0 , references 0
o .1 m 120 RC MS items reviewed 0
O O
O A
D 0 ii
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O O
O iA O
TSC/OIR Review Purpose O
E J m Reviewed active AFW OIRs and TS E clarification to determine if they are in ES esteement withthe de8isn se8eeaed E licensing basis of the plant.
O 3 0
0 0
0 iA O
O 12 0
~
O O
O O
A rsc/01R Review Discussion O
O 8 {m J m Technical Specification clarifications 8 associated with Auxiliary Feedwater aS reviewed - F1R ieeeed cio/8/96) eed E further work delegated to the TSC IIT.
O g3 oI m Reviewed open OIRs against Auxiliary 0
Feedwater.
iA O
O O i3
a O
O :
O oesign Change Reivew A'
O O am
"'**""i"""P""*"d*'"**"*"*"'""*""'"' I O desegn basis and that the results do not invaldste the conclussons of USAR. It is l
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O o Design Change Review Preliminary g Observations O
Ef; a Changes and outputs accomplished by the packages 0 are consistent with the design basis e Input / assumptions are consistent with design basis.
o a Improvement in the documentation of design inputs S , coincident with new procedures.
O O 1. m 1 USAR discrepancy noted out of 190 packages O
O iA O
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O O
Calculation Review Preliminary Observations O
O m Calculations inputs and assumptions are accurate and consistent with and 2 support the design bases with a few exceptions.
O O m Subject matter and purpose is normally well defined and a consistent O
methodology is used to produce similar calculations O a Calculation methodology is based on sound engineering principles and O consistent with normally accepted industry standards with one exception O
o , a Civil, structural, stress and seismic calculation assumptions are sometimes O based on engineeringjudgment rather than reproducible references. The O basis for this engineeringjudgment is often undocumented O
O m 3 USAR discrepancies found during review in which the assumptions in O the USAR needed to be updated O
O m 17 discrepancies noted out of 330 calculations reviewed to date such as O lack ofinput reference source documents O
O i7 0
._ _ - _ - - - - _ _- -_ _ _ - _ _ - _ - _ - _ _ _ _ _ - _ ___-_-_____ w
O O
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A PostNkx8ficationTestin9Review O agat .
This reviewis evalumbon the aw y i.-- ,.and '
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Roll Pin Review Preliminary g
O .
O 3 O
o a Of 371 change packages reviewed for material .
i S considerations, five di.screpant parts issues were 0
discovered. ;
E a 3 discrepancies were parts in warehouse that were O f, not per design.
E a 2 cases found where parts were install in plant 0 (Airset and MFW Bypass Valves) m No USAR discrepancies noted O
O 20 0
i i
O ,
O :
O AL 0
This reviewis looking at the ststability of testing to venfy system O ;
g 250 fmetions. . ___.. - _ _ _ - . _ _ . _ _ _ _ _ . _ . . _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ ___
O j Total P@-: 267 C 200 _ . _ . . _ . . - - _ _ _ _ _ _ _ _ . _ . - _ - _ _ . . - . -
O = i O ,g _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ ___ _ _ ______
O 0
S 100 - - - - _ - - - - - -- -_ _ - - - - _ - - -
O a , w .. __- ._ -- -. -- - - - _ .
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0 [~gggRewwxi-FdnUxfl 0 l __ Goal __ _j g
O O
O 21 0
s
O O
F unct ion and Testing Review A Preliminary Observations 0
Sb 0
u For every technical specification and USAR function, an active design function was identified 0 that fulfills the functional requirement.
0 m With 3 exceptions, the surveillance requirements of 0 TS were complied with.
O 1 0 m Four USAR discrepancies were noted i S a Verifying that active function design bases are being 0 met 0
O O 22 0 i J
O '
O Lessons Learned Review A Methodology O
U OTRJ m Reviewed the following documents associated with o Auxiliary Feedwater O
o + Approximately 80 ITIPs associated with the ,
O Auxiliary Feedwater System were reviewed 0 + Approximately 200 PIRs associated with Auxiliary U
Feedwater were reviewed.
0 m Follow-on review by PSE Group of approximate 111 O Operation Experience notifications from INPO to U
ensure appropriate documents were entered into the 0 program.
0 0
0 23 0
_ - - - _ _ - - _- _ _-__ -__ --_-_-_---__-_-_-_----_--__-_ __-- _J
.u .. ... . _r-- . - . . . . . - . . . - . . . ~ . - . . . . - -. ,.~.--.--......n~. -.. . -.. . . ~ . . -. . ..- - . . . . . . . . - ~ . . . . .
O O
Lessons Learned Review A Preliminary Conclusions 0
J m PIR and ITIPs review did not identify any new impact o the design or license basis of the plant i O
o a The PIR process needs enhancement U
a Corrective actions associated with PIRs needs 0 improvement a Trending and monitoring of PIRs should be enhanced O
O 0
A O
O 24 0 l
O O
O O
A coxettsrox O
Sf; a 5 people years expended on an extensive system 0
functional assessment o E No significant issues discovered o a No recommended change in scope for ESW 0
0 3 i O
O 0
O aA O
O i
O O 25 0 t
_ - _ _ _ _ - _ _ _ _ - - _ _ - - _ _ _ _ - - _ _ _ _ - _ _ - _ _ - - _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _