|
---|
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:NRC TO UTILITY
MONTHYEARIR 05000482/19900261990-11-14014 November 1990 Ack Receipt of Responding to NRC Requesting Addl Info Concerning 900731 Notice of Violation from Insp Rept 50-482/90-26 IR 05000482/19900341990-11-0909 November 1990 Forwards Notice of Violation Re Insp Rept 50-482/90-34 & Summary of Enforcement Conference on 901106 ML20058D7601990-11-0101 November 1990 Forwards Summary of Staff Understanding of Current Status Re GSIs Remaining Unimplemented at Facility,Per GL-90-04 ML20058E1391990-10-26026 October 1990 Forwards Final SALP Rept 50-482/90-14 on 900401-0630 ML20058B2831990-10-23023 October 1990 Forwards Insp Rept 50-482/90-34 on 900926-1005.Violations Noted ML20062C9971990-10-19019 October 1990 Forwards Insp Rept 50-482/90-31 on 900801-0914 & Notice of Violation ML20058A3621990-10-18018 October 1990 Advises That Util 900925 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2, Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20059P0671990-10-15015 October 1990 Ack Receipt of Requesting Withdrawal of Request for Relief Re Procurement of ASME Section III Matls ML20062B3081990-10-0505 October 1990 Forwards Insp Rept 50-482/90-30 on 900730-0810.Violations Noted But Not Cited.Four Open Items Identified ML20059N3091990-10-0101 October 1990 Forwards Insp Rept 50-482/90-28 on 900701-31 & Notice of Violation ML20059M6851990-09-28028 September 1990 Ack Receipt of 900830 Response to Violations Noted in Insp Rept 50-482/90-26.Addl Info Re Troubleshooting Required ML20059M0451990-09-27027 September 1990 Requests Addl Info Re Seismic Design Consideration for safety-related Vertical Steel Tanks.Info Needed within 90 Days Following Receipt of Ltr ML20059J3541990-09-11011 September 1990 Forwards Initial SALP Rept 50-482/90-14 for Apr 1989 - June 1990.Areas of Operations,Radiological Controls,Maint/ Surveillance & Engineering/Technical Support Rated Category 2,while Area of Security & Emergency Remained Category 1 ML20059C4171990-08-23023 August 1990 Accepts Util 890531 Response to NRC Bulletin 88-011 Re Surge Line Stratifiction.Nrc Topical Rept Evaluation Encl ML20059A7431990-08-14014 August 1990 Ack 900808 Visit to Region IV & Info Re Status of Actions on Recent Kansas City Power & Light Co Offer to Purchase Kansas Gas & Electric Co.Util Assurance That Offer to Purchase Will Have No Effect on Safety Operations of Importance to NRC ML20058P2581990-08-14014 August 1990 Ack Receipt of Transmitting Scenario for Upcoming Annual Exercise.Nrc Understands That Util Taking Actions to Resolve Concerns Expressed in FEMA 900727 Memo ML20058P2421990-08-13013 August 1990 Forwards Insp Rept 50-482/90-23 on 900507-11 & 0629-0703 & Notice of Violation.No Response to Violation Required Due to Corrective Action Implemented Prior to Inspectors Departure IR 05000482/19900241990-08-0606 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-24.Responses to Training Violation & Unresolved Item Re Min Protective Action Recommendations Responsive to Insp Rept Concerns ML20055J4891990-07-31031 July 1990 Advises That NRC Form 474, Simulation Facility Certification, Submitted on 900110,complete & Requires No Further Info.Simulation Facility Acceptable for Purposes of 10CFR55.31(a)(4) Based on Certification of Facility ML20055J4881990-07-31031 July 1990 Discusses Util 891226 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20056A2851990-07-31031 July 1990 Forwards Insp Rept 50-482/90-26 on 900601-30 & Notice of Violation.Violation Re Failure to Update Info Into Updated FSAR Noted But Not Cited ML20056A1731990-07-30030 July 1990 Advises That Requalification Program Evaluation Scheduled at Plant Site During Wks of 901022 & 29.Util Requested to Furnish Approved Items Listed in Encl 1.Failure to Supply Ref Matl May Result in Postponement of Exam ML20058L3311990-07-27027 July 1990 Summarizes 900724 Meeting W/Util in Region IV Ofc Re Changes to Operator Licensing Program.Meeting Agenda,Attendance List & Viewgraphs Encl ML20055J3971990-07-24024 July 1990 Requests Addl Info Re Steam Generator Tube Rupture Operator Action Times for Plant.Response Requested within 30 Days of Receipt of Ltr IR 05000482/19900171990-07-19019 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-17 ML20059N8021990-07-10010 July 1990 Ack Receipt of Transmitting Objective & Guidelines for Upcoming Emergency Preparedness Exercise. Util Exercise Scenario,Submitted on 900628,currently Under Review ML20055F6251990-07-0909 July 1990 Forwards Summary of 900626 Meeting W/Util in Region IV Ofc Re Licensee Performance During Latest Refueling Outage. Attendance List Encl ML20055D9881990-07-0505 July 1990 Forwards Insp Rept 50-482/90-25 on 900611-15.No Violations or Deviations Noted.One Unresolved Item Noted ML20055D9531990-07-0505 July 1990 Forwards Insp Rept 50-482/90-22 on 900501-31.Noncited Violation Noted.One Unresolved Item Identified IR 05000482/19900051990-07-0505 July 1990 Ack Receipt of 900629 & 0413 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-05 ML20058K3611990-06-26026 June 1990 Forwards Insp Rept 50-482/90-24 on 900514-18 & Notice of Violation.Unresolved Items Noted Re Discrepancy Between Emergency Plan & Emergency Plan Implementing Procedures Re Min Protective Action Recommendations During Emergency IR 05000482/19900161990-06-26026 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-16 ML20055C7671990-06-18018 June 1990 Forwards Insp Rept 50-482/90-27 on 900604-08.No Violations or Deviations Noted ML20059M9091990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248C6401989-09-27027 September 1989 Forwards Insp Rept 50-482/89-25 on 890911-25.No Violations Noted or Deviations Identified ML20248E7801989-09-21021 September 1989 Forwards Amend 4 to Indemnity Agreement B-99.Amend Increases Primary Nuclear Energy Liability Insurance.Util Requested to Submit Signed Amend to Signify Acceptance ML20247N1671989-09-20020 September 1989 Forwards Safety Evaluation Re Plant First 10-yr Inservice Testing Program & Requests for Relief Re Reclassification of 16 Valves from Passive to Active & Clarification of Cold Shutdown Justification ML20247M9531989-09-19019 September 1989 Forwards Insp Rept 50-482/89-22 on 890828-0901.No Violations Noted ML20247K0501989-09-14014 September 1989 Forwards Insp Rept 50-482/89-23 on 890801-31.No Citation for Violation Described in Paragraph 3 Issued,Per Section V.G.1 of NRC Enforcement Policy IR 05000482/19890051989-09-0606 September 1989 Ack Receipt of 890531 & 0831 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/89-05 ML20247B1931989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executives Meeting on 890818 in Arlington,Tx.Topics Discussed Included, Improving Communications,Salp Process in Region IV & Enforcement.List of Attendees & Agenda Encl ML20246F9131989-08-21021 August 1989 Forwards Request for Addl Info Re 880620 Proposed Revs to Tech Specs 3/4.4.9.1 & 3/4.4 9.3, RCS Pressure/Temp Limits & Overpressure Protection Sys, Respectively ML20246D6441989-08-17017 August 1989 Informs That Request to Withdraw Application for Amend to License NPF-42 Granted ML20245J6031989-08-14014 August 1989 Advises That Licensing Exams Scheduled for Wk of 891120.Ref Matl Listed on Encl Should Be Provided by 890920. Procedures for Administration of Written Exams Also Encl ML20245H2921989-08-0808 August 1989 Forwards Insp Rept 50-482/89-21 on 890701-31.No Violations or Deviations Noted ML20248A2171989-07-31031 July 1989 Forwards Summary of 890623 Meeting at Facility to Discuss SALP for Apr 1988 - Mar 1989 & Util 890721 Response to SALP Rept.Viewgraphs Also Encl ML20247N7251989-07-31031 July 1989 Concurs That Requirements of License Condition 2.C.(7), Attachment 3,Item (2) Re Emergency Response Capabilities Have Been Met,Based on Review of Util & on Past Emergency Preparedness Insps 1990-09-28
[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
{{#Wiki_filter:*
, : ,
In Reply Refer To:
Docket: STN 50-482/84-43 M 181985 Kansas Gas and Electric Company ATTN: Glenn L. Koester Vice President - Nuclear O P. O. Box 208 Wichita, Kansas 67201 Gentlemen:
A copy of the enclosed draft inspection report was given to a member of your staff on January 18, 1985. With the exception of minor editorial changes, the final version of this report issued on January 18, 1985, is the same as the enclosed draft inspection repor NRC policy requires that released drafts be placed in the public document room and be retained and made a part of NRC official files. Therefore, a copy of this letter and the enclosed draft inspection report will be placed in the NRC Public Document Roo
Sincerely,
/s/
R. P. Denise. Director Division of Reactor Safety and Projects
Enclosure:
Draf t NRC Inspection Report 50-482/84-43
REGION III==
NRC Inspection Report: 50-482/84-43 CP: CPPR-147 Docket: 50-482 Category: A2
'
Licensee: Kansas Gas and Electric Company (KG&E)
Post Office Box 208
-
Wichita, Kansas 67201 Facility Name: Wolf Creek Generating Station (WCGS)
- Inspection At: Wolf Creek Site, Coffey County, Burlington, Kansas Inspection Conducted: October 1-31 and November 1-30, 1984 Inspectors: . /7!I4 Date /
- . Wi 11ams /* J/ 9 Date /
/
M Mc ormick-Barger /* f9 Date / . Gu6mond
/2[g4 k Date Approved By: M. A g Chief / T[.'J/S /
Test Programs Section Dat'e l
'
L. E. Martin, Chief Wolf Creek Task. Force Date l
R. P. Denise, Director Reactor Safety and Projects Date ,
'
> n/70n-rn >
,
DJ WL' t' P 7 fd E
/5ff ,
.
Inspection Summary Inspection on October I through November 30, 1984, (Report No. 50-482/84-43(DRS))
Areas Inspected: Routine announced inspection of licensee action on previous inspection findings; approved preoperational test procedures; preoperational test performance; approved preoperational test results package evaluations; preoperational test procedure verification; preoperational test results package verification; approved startup test procedures; voiding of completed preoperational tests; preoperational test schedule; technical specification review; and preoperational test content. The inspection involved a total of 167 inspector-hours onsite and 100 inspector-hours offsite by four NRC inspectors, including 54 inspector-hours onsite during off-shift Results: Of the eleven areas inspected, four items of noncompliar.ce, with multiple examples, were identified, in the area of preoperational test content (paragraph 12). These items of noncompliance were a topic of an enforcement conference held on December 4,198 .
G e
$
i
.
f
2
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
. .
-
. .
DETAILS Persons Contacte_d l
* L. Koester, Vice President-Nuclear l
*C. C. Mason, Director of Nuclear Operations l
*F. T. Rhodes, Plant Manager i
*0. L. Maynard, Manager of Licensing
* Williams, Superintendent Regulatory and Quality Administrat o
* P. Rathbun, Manager, Licensing and Radiological Services
, *K. R. Petersen, Licensing Lead Engineer
*R. M. Grant, Director of Quality
* J. Rudolph II, Manager, Quality Assurance
'
,
* Mathis, Startup Quality Control
*R. L. Hoyt, Emergency Plan Administrator
*R. B. Glover, Startup Manager I
R. L. Straight, Licensing
.
F. D. McLaurin, Assistant Startup Manager R. * Ellison, Startup Lindsay, Quality Technical Assurance Systems Support Supervisor Supervisor *W
* B. Norton, Reactor Engineering Supervisor 9 198 * Denotes those attending the exit interview on November contacted by2 ,
Additional plant technical and administrative i personnel were the inspectors during the course of the inspect o ;
Licensee Action on Previous Inspection Findings Safety Injection _
k i mod (Closed) Unresolved Item (482/84-30-01(DRS)):
Signal (SIS) override of Feedwater Isolation Valve e erc s h 1 *
This item has been upgraded to an item o Improper testing of air (Closed) Open Item (482/84-30-02(DRS)):This item has been I
l operated valves. noncompliance and is discussed in paragraph 1 l Environmental conditions (Closed) Open Item (482/84-30-04(DRS)): This item has been upgra d in paragraph 1 l for 24 hour diesel generator load tes ' to an item of noncompliance and is discusse Wedge anchor bolt thread
. .I
,j J (Closed) Open Item (482/84-30-09(DRS)):The nt was inspector engagemen Q licensee which demonstrated thatd adequate thread deter- enga p{ provided by engagement of two or three threa sThe
{{ diamete mined that the analysis was correct, and ,
, this are i d
? .
_ . . . _ _
. . ,
Pump start and acceleration (Closed) Open Item (482/84-30-06(DRS)): This item has been capabilities under degraded voltage conditions. upgrade (
l I
Natural Circulation Startup Procedure I (0 pen) (482/84-30-07(DRS)):The procedure wording was modified so th comment mapping is used to meet a test Theobjective ascontinuing licensee is specifiedtoin the Final Safety Analysis Report (FSAR). evaluate the inspector's commen the phrase contained in step 6.12, Note b which states, " wide range T is approximately equal to core exit thermocouple average tI8herature".
Administrative controls for (Closed) Open Item (482/84-30-08(DRS)): The inspector reviewed a completed preoperational test package .
recently issued administrative procedure which pro The inspector has no further questions in this and accountabl '
are Pump start and acceleration (Closed) Open Item (482/84-30-05(DRS)): The licensee capability under 75% nominal voltage condition <
provided the inspector with test documentation to show that safety-related pumps had been factory tested to show their ability to start g and accelerate to rated speed under full load at 75%
condition questions in this are . Preoperational Test Procedure Reviews Below is a list of preoperational tests for which the inspectors have completed their test procedure review during the inspection perio Unless otherwise noted, the inspectors have no further questions on l these procedure SU3-AB04, Rev. O, " Main Steam System" SU3-BG02, Rev. O, " Seal Injection System" SU3-BG04, Rev. O, " Boron Thermal Regeneration System" SU3-NE01, Rev.1, " Diesel Generator Electrical Test" SU3-NK01, Rev. O, "125 VDC Class IE Electrical System" SU3-EN01, Rev. O, " Containment Spray Nozzle Air Test" SU3-EJ01, Rev. O, " Residual Heat Removal System (Cold)"
S03-5B01, Rev. O, " Reactor Protection System"
. The procedures were reviewed against the Final Safetyides, Analysis
'r
'
(FSAR), Safety Evaluation Report (SER), and applicable Regula i Standards, and portions of 10 CFR 5 comments with respect to the review of:
fL
-
. - . <
km hFU -
4
-,
.-.
. . . SU3-AB04, Rev. O, " Main Steam System" deter-During the review of this preoperational testification the inspector has been o mined that not all testing required for design verThe Wolf Creek-SNUPP included in the procedur .3.7.2 page 25 states "the control sequence for i the 10 percent close signal..."
test would be interrupted The in the event of an act licensee has had not been incorporated into the procedur his design acknowledged this concern and has committed to verify tl i
function during the retest of SU3-AB03, " Main S (Cold)".
l discussed in paragraph 1 l SU3-NK01, Rev.1, "125 VDC Class IE Electrical Test" The Wolf Creek - SNUPPS FSAR Section Contrary to d and the
.
tions, record and retain as a permanent plant re licensee appeared unaware of this commitmen t t committed to incorporate this requirement into the NK01 re es .
This item ofisnoncompliance a failure to meet and is an FSAR further commitment discussed in paragraph an
. SU3-NE01, Rev. 1, " Diesel Generator Electrical Test" s The inspector noted that the stated acceptance criteria t for diesel start time, full load rejection peak voltage and larges (Essential Service Water Pump) load shed peak iew voltage support the requirements of the most recent proof and rev i l test technical specifications. tion could lead tot circumstances its opera-was accepted but the diesel generator could not meeThe in identified tional requirements. acknowledged the concern and l the con inoperable diesel generato issued to change the acceptance criteria to reflect tec specification requirement has no further questions in this matte llow I The method used for the 35 start reliability test betweendid not a the diesel generator to return to ambient conditionsAm in successive condition start under which the diesel would be expected Guide to s
,
c' -
the event'of an actuation (in accordance tho with 1.108).
"' and a TCN was issued to correct the improper test me h-9. * * Failure of the review process to identi .
j[d= discussed in paragraph 1 ,
'i
--.; .
$
.
,
. .
-
5U3-5801, Re O. " Reactor Protection System" .
Several errors were noted in switch operations of the Nuclear Instrument Thesesystem during its use as a signal input to the pro errors would have been self-identifying and tion syste td the test could not have proceeded until they were correc e . Although the function was tested, no accep trip the reactor.
t An error in the setup and operation of the switched T and decade resistors would have prevented the Overpower Delta Overtemperature Delta T sections from being completed as writte .
Appendices AH and AI, which identified where blank.test instr tion connections were to be made, were left completely
-
The The low flow reactor trip requires two of four coincidenc hich test setup started with two low flow signals present, t and would w
would not have allowed the protection system to rese ,
have prevented the test from proceeding as writte cie The inspector met with licensee staff to discuss The inspectorthese discrep Major TCNs were issued to correct these problems. in this are reviewed these TCNs and has no further questions Preoperational Test Witnessing following l
i~ The inspectors witnessed the performance id of portions of the
-
preoperational tests during this inspection per o :
SU3-NE01, Rev. O, " Diesel Generator Electrical" S03-5801, Rev. O, " Reactor Protection System" SU3-kJ01, Rev. O, " Diesel Generator Mechanic it was conducted The inspectors witnessed test performance to assurethat thatipment the w l
in accordance with approved procedures, adequate, that that te t test changes
,
ability of licensee personnel conducting the test i ! were processed in an approved manne :s l with respect to the performance of:
;
$U3-NF01, Rev. 1, " Load Shedding and Load Sequencer"
,
-
-
rn that During the conduct of this test the inspector complete expressed during testing,conce
> i k} not all FSAR commitments had ting." been demons The preopera-w_
'
m the automatic actuation circuitry will override tesfeature by injecting t the actuation by a
'
tional proceddre attempted to verify this design
a e~
l
. .
The inspector believed that the opposite initiating the test circuitr The test circuitry l ,
approach would have better demonstrated this feature.sho The licensee I
to verify that this signal overrides the test circuitr l acknowledged the concern and wrote a TCN to prove the design featur l This is considered an item of noncompliance and is further discussed in l paragraph 1 .
Preoperational Test Results Packaaes Evaluations The inspectors completed review of the following preoperational test results packages during this inspection period:
.,
SU3-AB04, Rev. O, " Main Steam System" SU3-BG02, Rev. O, " Seal Injection System"
,
SU3-BG04, Rev. O. " Boron Thermal Regeneration System" SU3-EJ01, Rev. 1, " Residual Heat Removal System (Cold)"
SU3-EN02, Rev. O, " Containment Spray Nozzle Air Test"
, SU3-NB01, Rev. O, "4160 VAC Class IE Electrical System" The packages were reviewed to assure that test results i i are being
,
adequately evaluated, test data meets acceptance criteria, i dev at ons are properly identified and resolved, review procedures are be ng
;
followed, and administrative practices are adequate with respe execution and data evaluatio with respect to the review of:
] SU3-AB04, Rev. O, " Main Steam System" During the review of the results package it became evident l tion that
.
problems had existed with the operation The of thef'irstMain attemptSteamat Iso a I
'
Valves (MSIV) during the fast closure testin For some valves fast closure timing resulted in excessive times. Successive tests show 3 '
this exceeded two minute Further testing still outside the acceptance criteria limit '
resulted in the valvesWhenmeeting acceptance questioned by the criteria inspector, and thethis lic- test was
* considered acceptabl (1) the valves ensee presented two possible causes of these problems:
{ had been repacked and this was the first time that they had i been f]* stroked, (2) the startup testing engineer felt th l to nominal pressure before actuatio t l ~;
t explanations, no supporting data is available except for i able fast closure time.further demonstrate the acceptable However, at this operati
- fE; would be no further concern by the inspector. time, j
~{*
.;
acceptance criteria timing limits. Based on this issue and the major main-l in
"*1 concern to the licensee.tenance activities on the actuator lfing systems on
. h {' progress, the inspector has requested a justification for re
N
'9 the recorded times.
,
'
pending further evaluation by the licensee and the inspector.
i .
!
. - _ _ _ _ - _ _ . .-.
. _ - - - . .
. . . SU3-BG02, Rev. O, Seal Injection System Failure mode testing of system air operated valves did not check valve position af ter loss of electrical power to the solenoid operated air valve. This is an item of noncompliance and is discussed further in paragraph 1 . From the data on data sheet 8.2 it would appear that one of the check valves in the seal injection line for Reactor Coolant Pump B is not opening fully or that the line is plugge Compared to the three other pumps, only the minimum acceptable flow of 7.5 gallons per minute was obtained with its respective throttle valve considerably more open than the others. The licensee has committed to conduct a retest of seal injection flow balancin Evaluation of this retesting by the licensee and the inspector is an open item (482/84-43-02(DRS)) pending demonstration of satisfactory operatio . SU3-BG04, Rev. O, Boron Thermal Regeneration Failure mode testing of system air operated valves did not '
- check valve position after loss of electrical power to the solenoid air valve. This is an item of noncompliance which is discussed further in paragraph 1 . The clamp-on ammeter that was indicated as used in the test was The range not equivalent to that specified in the procedure.
,
-
of the instrument used in the test was 100-999 Amps with an accuracy of i 1% while the specified instrument range was 0-100 amps with an accuracy of i 3%. Discussions with the licensee i
.
:
revealed that the instrument was multi-range and.that The the wrong inspec- i
' range was recorded when identifying the instrumen l
* tor reviewed a corrective entry to the results package and has no further questions in this area.
{o Valve BG-UV7056 was identified as exhibiting stroking problem The solution was to raise control air pressure to 60 psi Test entries did not provide justification for this action and did not address any investigation to determine if of.her mechanical problems existed. Discussion with the licensee
;
revealed that 60 psig was the correct pressure and that control air pressure was initially low. The inspector has no further questions in this matte ; SU3-EJ01, Rev.1, '.' Residual Heat Removal (Cold)"
,{ 1 During verification of pump performance, a 0-800 psig gage with j an accuracy of i 16 psig was used to measure pump suction d,1 pressures ranging from 4.5 to 30 psig. The inspector met with l licensee staff to discuss the validity of the test data and the E validity of the test method. The licensee responded that an u immediate post-test calibration check of both pump suction ;
pressure gages against a 0-1000 psig,la% accuracy test gage i revealed that the gages used in the test were in fact
. .
.
. _ -
*
.
indicating as accurately as the precision gage. This post test Failure of information was not included in the test packag the procedure review and test results review process to identify, question, and correct the use of improper test equip-ment is an item of noncompliance and is further discussed in paragraph 1 . The inspector noted a step discontinuity Thisindiscontinuity the pump perform-occurred ance data recorded for both pump during the performance of identical steps in the testing of each pump. It was not clear that the review process noted or evaluated this discrepancy and the validity of the procedural step and resulting data is questionable. Evaluation of the step discontinuity by the licensee is an open item (482/84-43-03(ORS)) pending review of that evaluation by the inspecto . Preoperational Test Procedure Verification
.
The inspectors reviewed the following preoperational test procedure against the FSAR, SER, proposed technical specifications, Regulatory Unless Guides 1.68, and the licensee's administrative procedure otherwise noted, the inspectors had no comment SU3-GM01, Rev. O, " Diesel Generator HVAC System" No items of noncompliance or deviations were identified.
- Preoperational Test Results Verification
-
The inspector reviewed the following preoperational test re.sults packages and verified that the test results were reviewed against approved accept-
*
* ance criteria and an evaluation of the test results had been performed in accordance with Regulatory Guide 1.68 and the licensee's administrative procedure Unless otherwise noted the inspector had no comment SU3-GM01, Rev. O, " Diesel Generator HVAC System" No items of noncompliance or deviations were identifie ! Initial Startup Test Procedure Review l '
.
Below is a list of startup test procedures for which the inspectors have-l completed their review-
_
SU7-SF03.1, Rev. O, " Rod Drop Time Measurement (Cold, No Flow)"
SU7-SF03.2, Rev. O, " Rod Drop Time Measurement (Cold, Full Flow)"
SU7-SF03.3, Rev. O, " Rod Drop Time Measurement (Hot, Full Flow)"
.
SU7-SF03.4, Rev. O, " Rod Drop Time Measurement (Hot, No Flow)" .
[4 *SU7-0004, Rev. O, " Initial Criticality"
*
*SU7-0003, Rev. O, " Inverse Count Rate Ratio Monitoring for Approach to
'
h Initial Criticality"
*1 .
t
- _- . ._ ._ . -
. ., _ _ . ..
. .
O, " Initial
" Denotes procedures incorporated in procedure SU7-5011, Re Criticality and Low Power Test Sequence".
The procedures were reviewed again d the FSAR, Theard applicable inspector had Regulatory the Guides, Standards, and portions of 10 CFR 5 l folic, wing comments with respect to the review of: SU7-SF03.1, Rev. O, " Rod Drop Time Measurement (Cold, No Flow)"
(1) The note at Step 6.0 stated " Rod Position Indication System, SU7-SF04.1 should be done concurrently with this procedure."
Both procedures required that rods be withdrawn a certain number of steps and then stopped so that data could be take Numerous transfers from one procedure to the other would be needed as the procedures were performed because one procedure required that data be taken at 18, 210 and 228 steps (shutdown banks) or at 24 step intervals (control banks) while the other procedure required that data be taken at 48 steps (all banks).
, The procedures did not contain statements At the timetothat coordinate trans-the inspector ferring from one to the othe discussed this with the Reactor Engineering Supervisor, he indicated that he had been considering combining these proce-
,
dures (and possibly an additional procedure) in a manner similar to the procedures that were combined into 5U7-5011 This is
" Initial Criticality and Low Power Test Sequence."
' considered an unresolved item (482/84-43-04(DRS)) pending licensee action to revise the procedures to eliminate any ambiguities related to coordination between the procedure the
.(2) During the conduct of the test this procedure requires Residual Heat Removal (RHR) pumps to be stoppe .. Step stated "The Residual Heat Removal pumps should not be operated
;
during this test. If their operation is deemed absolutely
~ necessary to maintain equilibrium cold plant conditions, the recorder traces for the affected rod drops should be marked
'
*
However, there was no statement with the RHR flow rate."
within the procedure to identify the Proof and Review Technical Specification 3.4.1.4.1 requirement that, after beingAlso, deener-gized for one hour, an RHR pump must be restarte ment to return the RHR pumps to service when the test was complete. The licensee's Reactor Engineering Supervisor
.
indicated that the procedure would be modified to address these concerns; that the Reference Section would be modified to
&
include references to Technical Specification 3/4.4.1, and to
-
add the procedure that will be used to start the RHR pump '
This is considered an open item (482/84-43-05(DRS)) pending procedure revisio SU7-SF03.3, Rev. O, " Rod Drop Time Measurement (Hot, Full Flow)'.'
O ~
F
- (1) The note at Step 6.0 stated " Rod Position Indication System, SU7-SF04.2, should be done concurrently with this procedure."
,
.
____- ___
'-
___ -
- .
I kd
[The a.(1) above; resciution of this comment will be trac esame a details of this comment are the via the unresolved item mentioned in a.13 t Prerequisite 5.4 specified Thisthat the reactor was different from the coolant Hot, tempera (2) i be between 500*F and 557* be Full Flow Rod DropThesurveillance licensee agreed described greater than or equal to 551 Technical the procedure to agree with the Proof and ReviewThis Specificatio pending procedure revisio Flow)" SU7-SF03.4, Rev. O, " Rod Drop Time Measurement Review (Hot, No During the inspector's review, it was noted that2.0, Proof and Technical Specification 3/4.10.5, "Special Test Exceptions: i Position Indication System-Shutdown", was listed in Sect on
"Step References", and addressed in the body of
'
.
6.0, i d in either 3/4.10.4, "Special Test Exceptions:
.
also applied directly to this procedure, was not me locatio of this procedure to address Proof and Review Tec n c
.
3/4.1 O, s
507-0004, Rev. O, " Initial Criticality", and SU7-0003, il Re " Inverse Count Rate Ratio Monitoring for Approach to Init a Criticality" l boron Regulatory Guide 1.68, Revision 2, lies states thatmay be a notedcritica ,
concentration should be predicted so that any anomaTh and evaluate This is considered an unresolved item this statemen (482/84-43-08(DRS)) pending procedure revisio d e listed or The inspectors commenced review of the startup
.
belo Power" (This SU-SF08, Rev. O, "RCCA or Bank Worth Measurement at Zero" procedure is incorporated in SU7-5011, Rev. O, Low Power Test Sequence").
id No items of noncompliance or deviations were identif e .
i3 Voiding of Completed Preoperational Tests tional tests 9.
f ,j{ rocedure viola-The inspectors observed that several safety-related i preopera d and had
-
'
have tion recently been voided due to numerous adm i
' -
'
proceeded through various levels of the normal l i rev this ewThe in situa-action was initiate P~' ,
i lack of overview and monitoring by the licensee in al f tion to develo .
.
l _- .
.-
.
tests that have problems but should indicate more involvement by moni-toring groups within the licensee's organization. The inspectors further indicated that this trend will continue to be evaluated to determine if adequate corrective action has been implemented and to determine the impact on the acceptability of the preoperational test progra . Preoperational Test Scheduling The inspector has again informed the licensee that the published preoperational test completion date, plus the exhibited time frame for licensee review of completed test results packages does not support the proposed fuel load date. The inspector's concern is that attention to meeting proposed fuel load date may negatively influence the licensee's results review proces The inspector also indicated that the level of review by qualified people must not decrease due to pressure to meet proposed schedules. The licensee has acknowledged the concerns. This item is of particular interest due to the recent voiding of completed test packages by the licensee as discussed in paragraph 9.
.
1 Technical Specifications Review The inspector reviewed the draft proof and review technical specifica-tions in detail in preparation for procedure and results review No items of noncompliance or deviations were identifie . Preoperational Test Content Review of procedures and test results packages during both this and the previous inspection period revealed deficiencies in the technical content of approved preoperational test procedures. These deficiencies can be categorized into four areas and are listed below along with examples of these deficiencie Failure to provide verification of designed safety features (1) The ability of an SIS or Feedwater Isolation Signal to override the exercise mode of the Main Feedwater Isolation Valves was not verified in SU3-AE01, " Main Feedwater System". This item was discussed fully in inspection report 50-482/84-30(DRS).
(2) The ability of an SIS to override the slow closure mode of the MSIVs was not verified in SU3-AB04, " Main Steam System". This item is discussed in paragraph 3.a of this repor (3) The ability of an SIS to override the Automatic Test Insertion sequence in the Load Shed/ Emergency Load Sequencer system was not verified in SU3-NF01, " Load Shedding and Load Sequencer".
This item is discussed in paragraph 4 of this repor .
Failure of preoperational test procedures to verify the proper operation of designed safety functions is considered an item of noncompliance (482/84-43-09(DRS)).
.
'
;
. . Failure to verify an FSAR commitment Preoperational test SU3-NK01, "125 VDC Class 1E Electrical System",
did not monitor and record hydrogen concentration during battery operations for retention as a plant permanent record. This item is discussed in paragraph 3.b of this repor Failure to verify an FSAR commitment is an item of noncompliance (482/84-43-10(DRS)). Improper test methods
. (1) Failure mode testing of air operated valves (A0V) did not verify correct fail position on loss of air and loss of electrical power to the solenoid air valve. This item was discussed in report 50-482/84-30(DRS) and in paragraphs and 5.c of this repor (2) An improper pressure gage was used to record pump performance data for acceptance criteria in SU3-EJ01, " Residual Heat Removal System". This item is discussed in paragraph 5.d of this report.
.
(3) The method used for conducting the 35 start diesel generator reliability test did not provide correct test condition This item is discussed in paragraph 3.c of this repor Incorporation of improper test methods and failure of the review processes to identify and correct them is an item of noncompliance (482/84-43-11(DRS)). Failure to test equipment in the conditions under which it is
~
expected to operate (1) SU3-NF02, "LOCA Sequencer", did not provide proper environmental conditions for the diesel generator during its 24 hour load test. This item is fully discussed in report 50-482/84-3 (2) SU3-NF03, " Shutdown Sequencer", did not test the emergency pumps'
ability to start and accelerate to full load under degraded voltage conditions. This item was discussed in report 50-482/84-3 Failure to test equipment in the condition under which it is expected to operate in'the event of an actuation is an item of noncompliance (482/84-43-12(DRS)).
These items of noncompliance identified in preoperational test content were discussed at an Enforcement Conference held on December 4, 198 Any enforcement action based on these findings will be discussed in inspection report 50-482/84-5 .
.
.
+
_ -
- ..
.
'
. .
1 Open Items Open items are matters which have been discussed with the licensee, which will be reviewed further by the inspector, and which involve some action on the part of the NRC, the licensee or bot Open items disclosed during the inspection are discussed in paragraphs 5.a, 5.b.(2), 5.d.(2), 8.a.(2),
8.b.(2), and . Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompli-ance, or deviations. Unresolved items disclosed during the inspection are discussed in paragraphs 8.a.(1) and . Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1)
,
on November 29, 1984 to discuss the scope and findings of the inspectio *
The licensee acknowledged the statements made by the inspectors with respect to items discussed in the repor .
.
l l
!
l l
l
.
l l
.
l
___
. .
bec to DMB (IE01)-
bcc distrib by RIV:
RPB2 Resident Inspector SectionChief(RPB2/A)
EP&RPB R. D. Martin, RA R. P. Denise, D/DRSP
.W. L. Brown, RC RIV File Myron .Kannan, ELD, MNBB (1)
J. Harrison, RIII .
M. Resner, 0IA J. G. Keppler, RIII R. L. Spessard, RIII W. J. Dircks, EDO
!
!
>
!
i i
}}