|
---|
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 05000482/1997012
Text
. e
pS"2 UNITED STATES
%,$*
[
o.
.
,
O
NUCLEAR REGULATORY COMMISSION
{ g REGIO?11V
,4 611 RYAN PLAZA DmVE, SUITE 400
k+9 +0,, AR LINGTON, T EXAS 76011-8064
MAR 101995 ,
1
Otto L. Maynard, President and
l
Chief Executive Officer '
Wolf Creek Nuclear Operating Corporation
P.O. Box 411 ,
Burlington, Kansas 66839
l
I
SUBJECT: NRC INSPECTION REPORT 50-482/97-23 I
l
Dear Mr. Maynard: I
Thank you for your letter of February 27,1998, in response to our letter and Notice of
'
huion dated Jant ary 29,1998. We have reviewed your reply and find it responsive to the
concems laised in our Notice of Violation. We will review the implementation of your corrective
actions during a future inspection to determine that fuli compliance has been achieved and will
be maintained.
Sincerely,
}!
W. D. Johnson, Chief !
Project Branch B
j
Division of Reactor Projects
Docket No.: 50-482
License No.: NPF-42
cc:
Chief Operating Officer
Wolf Creek Nuclear Operating Corp.
P.O. Box 411
Buriirigton, Kansas 66839
Jay Silberg, Esq.
Snaw, Pittman, Potts & Trowbridge
2300 N Streat, NW
Washington, D.C. 20037
9803120361 900310
PDR
lflllllllllf!!fllllllllllllllllfllllll
G ADOCK 05000482
PDR ,
1
l.
k-
Nolf Creek Nuclear Operating Corporation -2-
l
L
Supervisor Licensing
. Wolf Creek Nuclear Operating Corp. j
P.O. Box 411 j
Burlington, Kansas 66839
Chief Engineer
Utilities Division -
Kansas Corporation Commission
'1500 SW Arrowhead Rd.
Topeka, Kansas 66604-4027 -
Oflice of the Governor
State of Kansas
. Topeka, Kansas 66612
Attorney General
Judicial Center-
' 301 S.W.10th
2nd Floor ,
'
Topeka, Kansas 66612-1597
County Clerk l
Coffey County Courthouse i
Burlington, Kansas 66839-1798 ;
I
'
Vick L. Cooper, Chief
. Radiation Control Program
Kansas Depsttment of Health
and Environment i
Bureau of Air and Radiation I
Forbes Field Building 283 l
Topeka, Kansas 66620 1
Mr. Frank Moussa l
Division of Emergency Preparedness )
3
2800 SW Topeka Blvd
Topeka, Kansas 66611-1287
l
l
l
. .
l
Wolf Creek Nuclear Operating Corporation -3- J
l MAR I O 1998
)
bec to DCD ilE01)
bec distrib. by RIV: i
L Regional Administrator Resident inspector
DRP Director SRI (Callaway, RIV)
Branch Chief (DRP/B) DRS-PSB
Project Engineer (DRP/B) MIS System
Branch Chief (DPP/TSS) RIV File
l
L
l
l
l
l 1
I
i l
!
l
l
,
I
I
l.
I
DOCUMENT NAME: R:\_WC\WC723AK.JFR ,
To receive copy of document, Indicate in box:"C" = Copy without enclosures "E" = Copy with enclosurer "N" * No copy j
RIV:SPE:DRP/B C:DRP/B { le
DNGraves;df M WDJohnsgpT~
'
3/ io /98 3/ (G98 '
OFFICIAL RECORD COPY l
L-
- . . . . ,
]
1
-
- Wolf Creek Nucita- Operating Corporation' -3 -
MAR I 0 1998 -
i
1
.4 6
bec distrib. by RIV:
Regional Administrator Resident inspector
DRP Director SFtl (Callaway, RIV)
Branch Chief (DRP/B) DilS-PSB
,
Project Engineer (DRP/B) MIS System
[ ' Branc!: Chief (DRP/TSS)- RIV File
i
l
l'
!
!
,
j
,
(-
I
l
l
!
.
-
1
. DOCUMENT NAME: R:\_WC\WC72%K.JFR
To receive copy of document, Indicate in beu:f * = Copy without enclosures "E" = C_opy with enclosures "N" = No copy
RIV:SPE:DRP/B C:DRP/B - l jf
DNGraves til if WDJohns# j
3/ l098 '
'
3/ 0/98 !
,
,
OFFICIAL RECORD COPY i
i
l
!
-
.
' '
,.
l
!
~
W$LF CREEK NUCLEAR OPERATING CORPORATION
.
~
Gary D. Boyer ~
CNef Admirustrative Ofreer
4
! -
J
( .e ,,
i
. _ - . _
,_ _ ,
Febrdary 27, 1998 l
Co 98-0015
U. S. Nuclear Regulatory Commission
ATTN: Document Control Desk
Mail Station Pl-137
Washington, D. C. 20555
Reference: Letter dated January 29, 1998, from W. D. Johnson,
NRC, to O. L. Maynard, WCNOC ;
Subject: Docket No. 50-482: Reply to Notice of Violations
50-482/9723-01, and 50-482/9723-02
Gentlemen:
This letter transmits Wolf Creek Nuclear Operating Corporation's (WCNOC) reply ,
to Notice of Violations 50-482/9723-01 and 50-482/9723-02. . !
i
Notice ot Violation 50-482/9723-01 identified that WCNOC personnel performed
procedure steps out of sequence while changing the charging pump line up.
Notice of Violation 50-482/9723-02 identified the failure of WCNOC personnel
o follow procedural guidance. WCNOC's response to these violations is
provided in the Attachment.
In the Executive Summary and Section 06.lb, of Inspection Report 50-482/97-23
the Inspectors identified a situation where the Plant Safety Review Committee
(PSRC) considered an Unreviewed Safety Question Determination without
pertinent information, which was omitted by the issue presenter.
In follow-up to the inspector observation during the PSRC review of the
Unreviewed Safety Question Determination evaluation regarding the use of
contact lenses while using respiratory protection devices, the PSRC assistant
chairman and the PSRC chairman met separately with the inspector. The PSRC
chairman agreed that accurate decision making by the PORC requires an adequate
understanding of the parameters of the decision. At the following PSRC
meeting, a separate item was placed on the agenda to discuss this issue and to
explore reasonable methods for assurance that the PSRC obtained sufficient
information in support of decisions. At the conclusion of the discussion, the
PSRC adopted two methods to facilitate gaining the necessary information for
decision making; 1) presenters to the PSRC would be verbally given the
expectation that information pertinent to the decision should be provided in
the presentation and 2) PSRC memoers would direct lines of questioning to the
i
presenter focused at assuring information necessary for decision making was
!
clearly understood. This discussion and the conclusions were subsequently
documented in the PSRC minutes and discussed with the inspector.
'
R S ~0Y%
P O Box 411/ Burkngton, KS 66839 / Phone- (316) 364 8831 i
l An Equal Ooportunity Ernployer DNF/HCNET
$ h l' [
c- ,
l<
L , . '. ..
l-
Yr i -
'
Letter'CO 98-0015
Page 2 of 2 ,
i
.
.
l
If'you have any questions regarding.this response, please contact me at (316)
l' 364-8831; extension 4450, or Mr. Michael J. Angus'at extension 4077.
l
l
.Very truly yours,
.GDB/jad
!
Attachment <
L- cc W. D. Johnson (NRC), w/a
l .E. W. Merschoff (NRC), w/a ,
J. F. Ringwald.(NRC), w/a
K. M.-Thomas-(NRC), w/a
l ..
-!
I.
I
l
l
r
.
I
i.
l
l ..
-
I
i
f .
'
! i
l
i
I
!
'
i
i
W .
'
" '
Attachment I-to'CO 98-0015'
, s Page 1 of:5-
7 Attachment
violation 50-462/9723-01-
" Technical Specification 6.8.?.a requires, in'part, that written procedures be
established, implemented,' and maintained covering the applicable procedures-
recommended in Appendix A of Regulatory Guide 1.33, Revision 2, . February 1978.
p Regulatory Guide 1.33, Revision 2, February 1978, Section 1.d, recommends, in
!
part, that procedures be established for procedure adherence.
Procedure AP 15C-002, ' Procedure Use and Adherence,' Revision 8, Section
6.2.3, requires that each step be completed or properly N/A'd (not applicable]'
before proceeding to the next step.
Contrary to the above, on January 15, 1998, a reactor operator performing.
Procedure SYS BG-201, ' Shifting Charging Pumps,' Revision 31, directed a
nuclear station operator to perform Steps 6.1.7 through 6.1.10, then proceeded
E
to complete Steps 6.1.11 - through 6.1.17 without superrn ary approval before
- receiving notification from the nuclear station operate: that Steps 6.1. 7 -
l -through 6.1~.10 were complete."
Dpacription'of Violation:
On January 15, 1998, a Reactor Operator proceeded with steps in Procedure SYS
BG-201, '" Shifting Charging Pumps," before previous procedural steps 'were "
.
. comp 10ted by a nuclear ~ station operator at a remote location (i. e., the steps
were performed concurrently instead of the prescribed sequence) . Performing
steps out of sequence is allowed with Shift Supervisor or Supervising Operator l
! concurrence if there is no adverse ef fect . on the system.. In this case, the ]
l Reactor Operator did'not'have autnorization from the Supcrvising Operator nor 1
i the Shift Supervisor to complete steps for swapping from the Normal Charging
l Pump. to Centrifugal Charging ~ Pump "A" before discharge pressure gauge
l isolation valves were manipulated. Although the evolution did not adversely .
impact public health and safety, this practice is in violation of Procedure AP 3
15C-002, " Procedure Use and Adherence," Revision 8, step 6.2.3, and is not in
accordance with Operations management expectations.
.)
l Reason for Violation: l
The root cause of this event is determined to be misjudgment on the part of
=the Reactor' Operator involved, due to habit intrusion. It became an accel ed
practice, and therefore a habit, to perform steps concurrently in the fi , d
i while Reactor Operators performed steps in-the Control Room.
I
j. A centributing factor to this event is inconsistency in Operations procederes
'
' regarding when steps can be performed concu: rently.
-Corrective Steps Taken and Results Achieved:
Performance Improvement Request (PIR) 98-0198 was written to determine root
cause and corrective action for this event.
l
The- Reactor Operator has been counseled by the Supervising Operator in )
accordance with the Management Action Response Checklist (MARC) process for j
failing to obtain concurrence from the Shift Supervisor or the Supervising 1
Operator prior te performing steps out of sequence,
_
i
I
i
j
!
.
]
[ Attachment 11 to CO 98-0015
Page 2 of 5
'
i Attachament
This; event, and the expectation to comply with procedure requirements, was
Jiscussed at a ~ Shift Supervisor / Supervising Operator meeting conducted
February 24,'1998. The Information discussed at this meeting was trarsmitted
to those individuals who were unable to attend.
Corrective Stepe To Be Taken:
The Superintendent Operations will counsel the Shift Supervisor and
Supervising Operator involved in accordance with the MARC process for failing
to provide adequate oversight of programmatic requirements. This activity
will be complete by March 20, 1998.
The conditions under which steps may be performed out of sequence or
concurrently will be evaluated by Operations and a . single method, adopted for
all' operating procedures, if feasible. If it is determined that a' single ,
method cannot be adopted for all procedures, then one method will be adopted !
for normal operating procedures. The existing guidance for emergency and off- !
normal procedures will not be changed. This evaluation will be complete by
April 3, 1998.
AP 15C-002 will be revised. outlining the conditions and requiremer.cs for
performing stops out of sequence or concurrently. Normal operating procedures
will be revised as applicable, to include the approved method adopted for
performing steps out of sequence or concurrently. Revisions will be complete !
June 19, 1998. 1
I
The Superintendent Operations or the Superintendent Operations Support will
discuss this event with each operating crew. Emphasis will be placed on ,
ensuring compliance with a l l, procedures and Wolf Creek Nuclear Operating l'
Corporation (WCNOC) approved programs. These discussions will clearly state
that future failures to implement WCNOC approved program requirements will be
dealt with in accordance with the MARC process. For on-shift personnel, these
discussions will begin on March 3, 1998, and continue until all crews have ;
been wtated back on-shift. These discussions will be complete by April 7, '
1998.
The Operations standards will be modified to include adherence to approved
WCNOC programs. This activity will be complete by March 13, 1998.
.The operations Field Supervisor will perform frequent observations of control
room and field activities to observe procedural use and adherence, and to
reinforce the expectation of programmatic adherence. All operating crews will
be observed. This activity will be complete by May 1, 1998.
Evaluation criteria for programmatic adherence will be added to complex
simulator scenarios. The data collected from these evaluations will be fed ;
'
back , to Operations management during end-of-cycle meetirtgs beginning with
Training Cycle 98-4, which begins April 27, 1998. This feedback will be used
to evaluate the progress of continuing a culture change in Operations that is
related to programmatic adherence.
l Date When Full Compliance Will Be Achieved:
I
Full compliance was achieved on January 15, 1998, immediately following
completion of surveillance test STS BG 100A, " Centrifugal Charging System 'A'
Train Inservice Pump Test, " which was the oterall controlling procedure for
'this activity.
1
'
l
." Attachment I to CC 98-0015
Page 3 of 5
Attachment I
violation 50-482/9723-02
l " Technical Specification 6.8.la requires, in part, that written procedures be
established, implemented, and maintained covering the applicable procedures
recommended in App 9ndix A of Regulatory Nide 1.33, Revision 2, February 1978.
Regulatory Guide 1.33, Revision 2, February 1973, Section 1.d, recommends, in
I part, that procedures be established for procedure adherence.
Procedure STS IC-450B, ' Channel Calibration Containment Atmosphere and RCS
Leak Detection Radiation-Monitor GTRE31,' Revision 12,. Step 8.4.1.4, requires
Technicians to remove field wires from TB1-1, and Step 8.4.1.5 requires
Technicians to connect the variable transformer hot lead to TB1-6 and neutral
lead to TB1-1.
, Contrary to the above, on January 7, 1998, Technicians failed to comply with
! these procedure steps. They removed the vendor wire (instead of the field
wire) from TB1-1 and reversed the variable transformer leads."
Description of Violation:
On January 7, 1998, three Instrument & Control (I&C) Technicians were
dispatched to perform STS IC-4508, " Channel Calibration Containment Atmosphere
and RCS Leak Detection Radiation Monitor GTRE31." This procedure provides
guidarice for performing calibration of Containment Atmosphere and Reactor
l
Coolant System Leak Detection Radiation Monitor GTRE0031.
The Lead I&C TechnicAan was performing Step 8.4.1.2 of Procedure STS IC-450B.
A CAUTION note ahead of step 8.4.1.2 requires the test performer to inform the
Reactor Operator that the next step may effect communications to some of the
! monitors on the RM-11 display. The Lead I&C Technician proceeded with the
performance of step 8.4.1.2, requesting the Control Room to de-energize
breakers NG02BAR130 and 116 without first making the Control Room aware of the
CAUTION note. The CAUTION note was brought to the attention of the Control
, Room after the NRC Senior Resident Inspector, who was present during
l performance of the procedure, queried the I&C Technician about performance of
the CAUTION note.
Procedure STS IC-450B contains another CAUTION note before step 8.4.1.3. This i
note states: "Use EXIREME caution while working inside the Motor Controller
l Assy. Use insulated tools because 120 VAC nay be present." The NRC Senior
Resident Inspector observed, during "he performance of STS IC-450B, that the
screwdriver teing used by the Technician was not insulated all the way to the
tip.
i
Step 8.4.1.4 directed the test performer to remove the field wires from
terminal TB1-1. During performance of this step, the NRC Senior Resident
Inspector inquired how the Technician knew that the lead being lifted was the
field wire and not the vendor wire. The I&C Technician explained the decision
process for this determination to the NRC Senior Resident Inspector. Without
performing a verification, the Technician incorrectly assumed that the wire
going into the conduit at the bottcm of the cabinet was the field wire.
Step 8.4.1.5 directed the test performer to connect variable transformer, set
for 0 VAC, to TB1-6 (HOT) and TB1-1 (Neutral). The variable transformer was
connected, black test lead to TB1-1 and white test lead to TB1-6. The NRC
Senior Resident Inspector questioned the I&C Technician as to whether this was
the correct connectica 'or the test lead.
1
l .
.
! 2 .
l ,' ' Attachment I to CO 98-0015
Page 4 of 5
j Attachment
i
The I&C Technicians re-examined the test equipment connections, identified i
the.t the test equipment was miswired, end performed the appropriate l
l corrections. These corrections were to connect the white test lead to TB1-1 j
- (Neutral) and black test lead to TB1-6 (Hot). During the process of
correcting the miswiring, the NRC Senior Resident Inspector noted that the
Technician touched the uninsulated portion of the screwdriver. When AC power
l was applied to the variable transformer, the Ground Fault Interrupter (GFI),
j which was supplying power to the test equipment, tripped.
l At this point in the evolution, the I&C Technician called time out. Test
equipment was removed and wires which had been removed in step 8.4.1. 4 were
re-terminated. The I&C Technician then determined that the wire lifted in
step 8.4.1.4. was the vendor wire and not the field wire after the Technician
i located the field cable marker. Once the job was-in a safe condition, the IsC 1
!
Technicians returned to the shop and noti ed the Assistant Superintendent of j
IEC of the problems that were being encountered. 1
Reason for Violation:
This violation was caused by the involved I&C Technician failing to comply
- with the instructions provided by Pr'cedure STS 10-450B. In addition, the
L Technician failed to perform validation or verification techniques necessary '
to ensure procedural compliance.
A contributing factor to this event was that Procedure STS IC-450B did not I
provide a specific verification technique. !
An additional contributing factor was that the Technician became nervous and i
lost focus on the job being performed. While performing the procedure, the l
l technician was responding to questions about the work activities being l
l performed. In addition, the environmental conditions of the area where the
testing was being conducted were unfavorable, in that working space was
restricted and lighting was poor. The combination of these factors increased
the nervousness of the Technician; however, the Technician did not use " Time
Out" techniques when faced with uncertainty.
l
Corrective Steps Tzkon and Results Achieved:
An editorial. change to Procedure STS IC-450B was implemented on January 7,
1998, to clarify location of field wires on the terminal block and to clarify
! test equipment connections. An additional change was incorporated into STS
l
IC-450B on February 20, 1998. This change made the CAUTION note ahead of step
l 8. 4.1. 2 a procedure step with a check-off block. The procedure, after the
editorial change was implemented, was re-performed with .natisfactory results
on January 7, 1998.
Perf o rmance Improvement Request (PIR) 98-0057 was written to determine the i
root cause(s) and corrective action (s) for this event. I
The topic of screwdriver insulation was discussed at an Electrical and I&C ;
Shop meeting on January 13th, 1998, and awareness was raised with respect to -
having too much bare metal on the screwdriver tip exposed.
The Technicians involved were counseled and awareness levels raised with
respect to use of verification techniques while performing work activities.
The awareness level was raised regarding the expectation to use the " Time Out"
process to ensure activities do not proceed in the face of uncertainty. The
MARC process has been implemented to address performance expectations.
1
!
.
f, ,
]
l; .. , . .
) ,* Attachmtnt I to CO 98-0015 i
'
l Paga 5 of 5
i
l' Attachment
!
Corrective Steps To Be Taken: I
None. All corrective actions are complete.
Date When Full Compliance Will Be Achieved: '
rull compliance was achieved on January 7, 1998, when the Technicians returned 1
to the work area and properly performed Procedure STS IC-450B with
'
satisfactory results.
l
l
-
l
1
i"
!
s
g ,.
'
. . . . . ,
l
J
i
l
l
l
l
I
-
L l
i
i \
l I
i
i
I
!
l
,
I
l
i
I
!
i
I