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Category:CORRESPONDENCE-LETTERS
MONTHYEAR05000482/LER-1999-002, Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl 05000482/LER-1994-014, Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl1999-10-15015 October 1999 Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl ML20217F7481999-10-14014 October 1999 Informs That Based on Approval of Core Assessment Damage Guidance in WCAP-14696,rev 1 for Westinghouse Nuclear Power Plants,Licensee May Use WCAP-14696,rev 1 at Wolf Creek Generating Station ML20217F8701999-10-13013 October 1999 Provides Summary of Meeting on 991007 with Representatives of Wolf Creek Nuclear Station in Burlington,Kansas Re Status of Licensee Radiation Protection Program.List of Meeting Attendees & Licensee Presentation Encl ML20217C1721999-10-0707 October 1999 Forwards Insp Rept 50-482/99-09 on 990830-0903.No Violations Noted.Purpose of Insp to Perform Routine Operational Status Insp of Emergency Preparedness Program & to Resolve Questions Re Revised Emergency Plan ML20217A4881999-09-29029 September 1999 Forwards Changes to Plant Data Point Library,Iaw 10CFR50,App E,Section VI.3.a.ERDS Point Affected Is RDS0001 ML20216H9291999-09-29029 September 1999 Informs That Licensee Responses to GL 97-06, Degradation of Steam Generator Internals Acceptable & Did Not Identify Any New Concerns with Condition of SG Intervals at Plant ML20212G1681999-09-24024 September 1999 Notifies NRC of Change in Status of Licensed Individual at Plant,Per 10CFR50.74.RL Acree Holds License OP-42654 at Plant,But Has Been Permanently Reassigned from Position for Which Plant Has Certified Need for RO License ML20216F9591999-09-22022 September 1999 Forwards Withdrawal of Amend Request Re Ultimate Heat Sink Temp for Wolf Creek Generating Station ML20212G5641999-09-20020 September 1999 Forwards Insp Rept 50-482/99-13 on 990725-0904.Three Violations Being Treated as Noncited Violations 05000482/LER-1999-011, Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I1999-09-17017 September 1999 Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I 05000482/LER-1999-010, Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util1999-09-16016 September 1999 Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util ML20212D9381999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of WCGS on 990818.Areas of EP & Engineering Warranted Increase in NRC Action.Nrc Plan to Conduct Add Insp Beyond Core Insp Program Over Next 7 Months to Address Listed Questions 05000482/LER-1999-006, Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl1999-09-15015 September 1999 Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl ML20212C9211999-09-15015 September 1999 Forwards NRC Form 536, Operating Licensing Examination Data, in Response to NRC Administrative Ltr 99-03 ML20216F1641999-09-14014 September 1999 Forwards Insp Rept 50-482/99-12 on 990816-20.No Violation Noted.Determined That Solid Radwaste Mgt & Radioactive Matls Transportation Programs Were Properly Implemented 05000482/LER-1999-009, Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER1999-09-10010 September 1999 Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER ML20212A5651999-09-10010 September 1999 Informs of Completion of Review of & Encl Objectives for Wolf Creek Generating Station 1999 Emergency Preparedness Exercise Scheduled for 991117.Determined Exercise Objectives Appropriate to Meet EP Requirements 05000482/LER-1999-008, Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER1999-09-0303 September 1999 Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER ML20211M7151999-09-0303 September 1999 Forwards Changes to Wolf Creek Generating Station Data Point Library.Emergency Response Data Sys Points Affected Are EJL0007 & EJL0008 ML20211N0081999-09-0202 September 1999 Informs That NRC Staff Has Reviewed Submittals & Concluded Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20211K8301999-09-0202 September 1999 Forwards marked-up TS Page Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band,Per 990708 Application to Amend License NPF-42 ML20211K1941999-08-31031 August 1999 Forwards Rev 31 to WCGS Physical Security Plan,Safeguards Contingency Plan & Training & Qualification Plan,Iaw 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20211H1491999-08-26026 August 1999 Forwards Insp Rept 50-482/99-16 on 990809-13.No Violations Noted.Insp Focused on Low as Is Reasonably Achievable Program,Training Program for Contract Radiation Protection Personnel & Radiation Protection QA Program ML20211A8581999-08-18018 August 1999 Forwards Insp Rept 50-482/99-08 on 990316-0724.One Violation Being Treated as Noncited Violation ML20211G2201999-08-17017 August 1999 Forwards Exam Rept 50-482/99-301 on 990726-29.Exam Evaluated Six Applicants for SO Licenses & Three Applicants for RO Licenses ML20210U0991999-08-13013 August 1999 Forwards Insp Rept 50-482/99-11 on 990712-16.No Violations Noted.Insp Was to Review Radiological Environ Monitoring Program ML20210U9751999-08-13013 August 1999 Informs That Licensee Identified That Answer Key for One Question on 990720 Written Exam & Event Classification for on Job Performance Measure Required Mod.Description & Justification for Proposed Mod,Including Technical Ref,Encl ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210R5621999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Revised Repts for Apr,May & June 1999,correcting Number of Hours Reactor Critical,Encl ML20210P7491999-08-0909 August 1999 Ack Receipt of ,Which Transmitted Wolf Creek Radiological Emergency Response Plan 06-002,Rev 0,under Provisions of 10CFR50,App E,Section V ML20210N0061999-08-0303 August 1999 Forwards Response to NRC 990401 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Motor-Operated Gate Valves ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210H2551999-07-29029 July 1999 Provides 180-day Response to NRC Request for Info Re GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210J1371999-07-29029 July 1999 Requests NRC Approval of Methodology for Determining RCS Pressure & Temp & Overpressure Mitigation Sys PORV Limits. Attachment I Provides Proposed Changes to Improved TS ML20210F5931999-07-27027 July 1999 Forwards semi-annual Fitness for Duty Performance Data Rept for Wcnoc,Per 10CFR26.71(d).Rept Covers Period of 990101- 0630 ML20210F5881999-07-23023 July 1999 Submits Response to Administrative Ltr 99-02, Operator Reactor Licensing Action Estimates, ML20210B8191999-07-20020 July 1999 Ack Receipt of ,Which Transmitted Wolf Creek EP Implementing Procedure 06-005,Rev 1.Implementation of Changes Will Be Subj to Insp to Confirm That Changes Does Not Decrease Effectiveness of EP ML20209H5411999-07-15015 July 1999 Forwards Insp Rept 50-482/99-07 on 990614-18.No Violations Noted.Insp Focused on Radiation Program During Normal Operating Conditions ML20209H0441999-07-14014 July 1999 Forwards Response to NRC 990326 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. Summary of Util Commitments Provided in Attachment 2 ML20209H0751999-07-14014 July 1999 Forwards Monthly Operating Rept for June 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Max Dependable Capacity Has Been Updated from 1163 to 1170,as Determined by Calculations Based on Capacity Test Results of July 1998 ML20209G9871999-07-14014 July 1999 Informs of Changes Affecting Wolf Creek Security Plan,Per 10CFR50.54(p)(2).Encl Provides Description of Changes & Justification for Changes ML20209E3581999-07-12012 July 1999 Discusses Util 980925 Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Wolf Creek Generating Station ML20209E0611999-07-0808 July 1999 Forwards Addl Pages to Rev 12 of USAR & Commitment Changes, Inadvertently Omitted from 990311 Submittal ML20196K8231999-07-0606 July 1999 Submits Kansas Electric Power Cooperative,Inc Ltr Pursuant to Commission Direction in Memo & Order CLI-99-19.Addresses Disposition of Existing Antitrust Conditions Attached to License for Wolf Creek Unit 1 Re Proposed License Transfer ML20209C6031999-07-0606 July 1999 Provides Applicants View as Result of 990618 Memo & Order Directing Parties to Address Proper Disposition of Existing Antitrust License Condition Attached to OL for Facility Due to Planned Changes in Ownership of Facility.With Svc List ML20196K0501999-07-0202 July 1999 Forwards Insp Rept 50-482/99-06 on 990502-0612.Three Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20209B7131999-07-0101 July 1999 Submits Response to NRC Request for Info Re GL 98-01, Suppl 1, Y2K Readiness of Computer Sys at Npps. Response on Status of Facility Y2K Readiness Was Requested by 990701.Disclosure Encl ML20209A7461999-06-29029 June 1999 Informs of Changes in Project Mgt Staff Assigned to Wcgs. Effective 990628,J Donohew Will Assume PM Responsibilities ML20209B5151999-06-29029 June 1999 Informs That Util Completed Analyses & Modifications to Address Items Discussed in GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions 1999-09-03
[Table view] Category: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
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, g UNITED STATES -
g a NUCLEAR REGULATORY COMMISSION 5 I wasHwcrow.o. c.nosss 7
CocLEt No. 50-482 1 4 OCT 1386 Mr. Glenn L. Koester ~
Vice President - Nuclear Kansas Gas and Electric Company 201 North Market Street Post Office Box 208 Wichita Kansas 67201
Dear Mr. Koester:
SUBJECT:
LOW TEMPERATURE OVER PRESSURE PROTECTION By letter dated May 22,1985 you proposed to add an alam circuit to RHR ~ '
system suction valves 8702A and 8701B. According to the logic of that circuit if any one of the two valves is either open or has no power to its operator and the reactor coolant system (RCS) pressure has reached or exceeded the valve interlock activation setpoint of 682 psig, an alam will sound in the control room. These alams will provide assurance that the RHR system is properly isolated from the RCS suction relief valves for low temperature over pressure protection. The staff has reviewed the above proposed alam circuit and by letter dated August 16, 1985, concluded that it is acceptable..
Subsequently, during the course of completing the detailed design of this alarm circuit you became aware of a design conflict with the existing plant procedures.
By normal operating procedures and in satisfaction of another staff position the plant operator is required to close all RHR suction isolation valves and remove their power before the RCS is pressurized to operating conditions.
Although the RHR valves are now closed, when the RCS pressure is at or above the interlock activation setpoint the alam will be activated and cannot be cleared since one of its conditions is continuously satisfied, i.e., the operators of valves 8702A and 8701B have their power removed. In order to remedy this situation, KG8E proposed, by letter dated May 2,1986 and a supple-ment dated June 25, 1986, to modify the alam logic so that it will alam only if either of the above two valves is open above the interlock setpoint. Valve i position indications will receive their signals from contacts on the limit switch rotor internal to the valve actuator. Power to these signals will be provided by the annunciator system power supply. A diverse alam is provided by the computer annunciator.
8610200085 861014 PDR ADOCK 05000482 p PDR
The other two RHR suction isolation valves, 8702B and 8701A, continue to be interlocked independently. If open, these valves close automatically if the pressure setpoint of 682 psig is reached or exceeded. Since the proposed modification provides alanns if any of the subject valves were left inadvertently open, which is that same function as that of the originally proposed alarm circuit, this staff concludes that the proposed modification is acceptable.
Sincerely, Paul W. O'Connor, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A cc: See next page 0
1 l
] 1 4 00 N The other two RHR suction isolation valves, 8702B and 8701A, continue to be interlocked independently. If open, these valves close automatically if the pressure setpoint of 682 psig is reached or exceeded. Since the proposed modification provides alarms if any of the subject valves were left inadvertently open, which is that same function as that of the originally proposed alarm circuit, this staff concludes that the proposed modification is acceptable.
Sincerely, Paul W. O'Connor, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A cc: See next page nMTpimtg
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Mr. Glenn L. Koester Wolf Creek Generating Station Kansas Gas and Electric Company Unit No. 1.
cc:
Mr. Nicholas A. Petrick Mr. Gary L. Haden Director Executive Director, SNUPPS 5 Choke Cherry Road Research & Energy Analysis I Rockville, Maryland 20850 Kansas Co.rporation Commission '
4th Floor - State Office Building Jay Silberg, Esq. Topeka, Kansas 66612-1571 Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Regional Administrator, Region IV Washington, D.C. 20037 U.S. Nuclear Regulatory Comission Office of Executive Director for Operations l Mr. Donald T. McPhee l 611 Ryan Plaza Drive, Suite 1000 Vice President - Production Arlington, Texas 76011 Kansas City Power & Light Company 1330 Baltimore Avenue Mr. Allan Mee -
i Kansas City, Missouri 64141 Project Coordinator Chris R. Rogers, P.E. Kansas Electric Power Cooperative,Inc.
Manager, Electric Department P. O. Box 4877 Gage Center Station.
Public Service Comission Topeka, Kansas 66604 P. O. Box 360 Jefferson City, Missouri 65102 Resident Inspector / Wolf Creek NPS t
' Regional Administrator, Region III c/o U.S. Nuclear Regulatory Comission U.S. Nuclear Regulatory Comission P. O. Box 311 Burlington, Kansas 66893 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Brian Moline Chief Legal Counsel Brian P. Cassidy, Regional Counsel kansas Corporation Comission Federal Emergency Management Agency Region I 4th Floor - State Office Building Topeka, Kansas 66612-1571 J. W. McCorinack POCH Boston, Massachusetts 02109 Senior Resident Inspector / Wolf Creek NPS Mr. Robert Elliot, Chief Engineer c/o U.S. Nuclear Regulatory Comission P. O. Box 311 Utilities Division Burlington, Kansas 66839 Kansas Corporation Comission 4th Floor - State Office Building Topeka, Kansas - 66612-1571 Mr. Gerald Allen Public Health Physicist Bureau of Air Quality & Radiation Control Division of Environment
~
Kansas Department of Health and Environment Forbes Field Building 321 Topeka, Kansas 66620
4 KANSAS CAS AND ELECTRIC COMPANY
,i em eacrac ecwmv June 25, 1986 GLENN L MOESvEm
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Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Cm mission Washington, D.C. 20555 EMLNRC 86-116 Re: Docket No. STN 50-482 Ref: Intter EMIRRC 86-071 dated S/2/86 from GLKoester, KG&E, to HRDenton, NRC '
Subj: Iow Tenperature Overpressure Protection
Dear Mr. Denton:
' Wis letter corrects a discrepancy in the description of the low tenterature overpressure protection (LTOP) alarm circuitry as outlined in the referenced letter.
%e design described in' the referenced letter provides new alarm circuits to valves BB-W-8702A and FJ-HV-8701B such that if the interlock setpoint is reached and either valve is open an alarm will initiate on the main control board. W e referenced letter states that valve position for BB- W-8702A and EJ-HV-8701B will be derived "directly from valve stem mounted limit switches". However, the design utilizes a contact on the limit switch rotor internal to the valve actuator for valve position in31 cation. mis discrepancy does not change the function of the alarm circuitry as previously described.
If you have any questions concerning this subnittal, plasse contact me or Mr. O. L. Maynard of my staff.
Very truly yours, Glenn L. Koester Vice President - Nuclear GLK:see $
cc: PO'Connor (2)
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F i 201 N. Market - McNta, Kanses - Mel Address: RO. Box 200 i NcNta Kenses 67201 - Te6ephone: Area Code 016) 261-6451 O
KANSAS GAS AND ELECTRIC COMPANY 3 v4 acmc c==v etc t morevra
= = ~ = ~m a May 2, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D.C. 20555 RMLNRC 86-071 Re: Docket No. STN 50-482 Ref: 1)Ietter RMLNRC 85-122 from GLKoester, KG&E, to HRDenton, NRC, dated 5/22/85 -
2)Ietter from BJYoungblood, NRC, to GLKoester, KG&E, dated 8/16/85 Subj: Low Teperature Overpressure Protection
Dear Mr. Denton:
his letter describes a modification to the design of low tenperature overpressure protection (L'IOP) alarm circuitry described in Reference 1. A schedule for inplementation of this nodified design is also provided.
Reference 1 proposed reliance on existing Technical Specifications and administrative controls with the addition of alarm circuits on certain RHR/BCS suction isolation valves for LTOP. As the alarm circuit was proposed, if either valve BB-W-8702A or EJ-HV-8701B is open or does not have power available and the pressure interlock activation setpoint is reached, an alarm would annunciate in the control room. We NRC approved this design in Paference 2.
During the developnent of the installation package, it was determined that the design proposed in Referen::e 1 would perform its intended function, but would produce alarms that could not be cleared even with correct valve aligment. Wis is because the alarms would be generated above the closure i
interlock activation setpoint of 682 psig when power was removed from BB-W-l 8702A as procedurally required. In order to remedy this situation, Kansas Gas and Electric Capany (KG&E) proposes modified alarm circuits which will alarm if either valve BB- W-8702A or EJ-HV-6701B is open at pressures above the interlock setpoint. A single annunciator window will represent these ;
two alarm circuits, but they will be alarmed individually on the Balance of '
' Plant Conputer.
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201 N. Market - Wichtra, Kanses - Mac Address:RO. Box 206 I nicNta, Kansas 67201 - kephone: Area Code (316) 261-6451
l Mr. H.R. Denton KMWRC 86-071 Page 2 '
May 2, 1986 Figure 1 outlines the design as described in Reference 1 and the modified design. 'Ihe modified alarm circuits do not affect the analysis provided in Reference 1 with regard to conpliance to Standard Review Plans 5.2.2 and 5.4.7 and the corresponding Branch Technical Positions RSB 5-2, and RSB 5-1.
'Ihe valve position inputs for the alarms in the modified circuit come directly from valve stem mounted limit switches rather than from the motor control center inputs as in the previous design. 'Ihe modified circuit continues to provide annunciation in the control room for misaligned valves once the interlock setroint is reached. An alarm response procedure will direct the operator to verify valve closure upon receipt of this alarm.
'Ihe modified design requires new cables to be run- to the valves in containment and requires an outage to conplete. Inplementation of this modification refueling which is scheduled to be empleted prior to startup following is currently planned to begin October 9, 1986. the schedule for inplementation of the modified design is consistant with that outlined in Wolf Creek Generating Station SSERS Section 5.2.2.
If you have any questions concerning this subnittal please contact me or Mr.
O. L. Maynard of my staff.
Very truly yours, Glenn L. Koester GLK:see Vice President - Nuclear i
Enclosure cc: PO'Connor (2)
JCunmins l
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e FIGURE 1 .
I Present NRC Approved Design .
(Ref: KMLNRC 85-122) Modified Design BB-PV-8702A or BB-PV-87E2A or EJ-HV-8791B EJ-HV-8701.B 682 psig l OPEN* No Power OPEN** Interlock Setpoint l
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i j 682 psig Interlock Setpoint Conn on Annunciator
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- Position provided by auxiliary relay at MCC
- Position provided by valve stem mounted limit switches i
Ccmh. o Annunciator
f , l,. #l ./,'g UNITED STATES NUCLEAR REGULATORY COMMISSION ,
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Docket No.: 50-482 Mr. Glenn L. Koester
-Vice President - Nuclear Kansas Gas and Electric Company 201 North Market Street Post Office Box 203 Wichita, Kansas 67201 ~
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Dear Mr. Koester:
Subject:
Wolf Creek - Low Temperature Overpressure Protection The staff has completed its review of your May 22, 1985 submittal regarding p(LTOP) system and procedures.roposed Thetstaff findsmodifications to the plant's that these modifications Low Tempera along iois Uie plant's Technical Specifications provide and adequate LTOP system that meets staff positions.
Accordingly, the staff finds that the submittal requirement of License Condi-tion 2.C.(13) has been met. A copy of the related Safety Evaluation is enclosed.
In addition, we have also enclosed h copy of.the staff's safety evaluation related to the removal of one 345 kV offsite transmission line between Wolf Creek and the West Gardner switching station. This evaluation which was docketed by staff memorandum dated March 14, 1984 is provided for your
. infomation.
~
Sincerely, f,. N For B. J. Youngblood, Chief Licensing Branch No. I Division of Licensing
Enclosures:
- 1. Safety Evaluation Re: Low Temperature Overpressure Protection
- 2. Safety Evaluation Re: Design Change in -
the Wolf Creek Offsite Power Systein cc: See next page I I ,
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ENCLOSURE
~SAFETY EVALUATION 30LF CREEK GENERATING STATION \
J DOCKET.NO. 50 482
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_kHRS LTOPS MODIFICATION .
Introduction The staff has imposed the followl6g license conditions on the owner of the Wolf Creek nuclear plant, the Kansas Gas & Electric (KG&E) Company: '
- 13) Low Temperatree Overpressure Protection (Section 15 SSER #3) .
By June 1,1985, KG&E shall submit for NRC review and approval a description of equipment modifications to the residual heat removal system (RHRS) suction isolation valves and to closure circuitry which conform to the applicable staff requirements (SRP 5.2.2).
Within one year of receiving NRC approval of the modifications, KG&E
_ shall have the approved modifications installed. Alternately, by June 1,1985, KG&E shall provide acceptable justifications for.
, reliance on adeinistrati've mean,s alone to meet the staff's RHRS
" isolation requirements; or otherwise, propose changes to Appendix A to this license which remove reliance on the RHRS as a means of low temperature overpressure protection.
To resolve t: .aove license condition, KG&E submitted for staff review certain system and pr::edural modifications by a letter from G. L. Koester, KG&E Company to H. R. Denton, NRC, dated May 2R, 1985. These modifications.are described and evaluated below.
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For the low temperature overpressure protection (LTOP)'of the Reactor Coolant l 1
System (RCS), the plant relies on eMer two power operated relief valves '
l (PORVs) or two residual heat removal (RHR) suction relief valves. The RHR relief valves are located at the suction of the RHR pumps downstream of the RHR
. . l suction valves. The two RHR p6mpt take suction separately from the RCS via two 1 motor operated valves (MOVs) in series.(see attached schematic). The MOVs ;
closesttopumpsAand5are8701Aand8701Brespectively. The MOVs closest to the RCS are 8702A and 8702B. Both MOVs 8701A and B receive their auto close interlock signal from a single pressure transmitter, while the other two MOVs !
8702 A and B receive their signal from another pressure transmitter.
The Wolf Creek Technical Specifications (TS) restrict plant operation when the l
reactor coolant is 368'F or colder, such that no more than one centrifugal l charging pump may inadvertently start, and such that an idle reactor coolant pump may not be started if the steam generator water temperature is more than-50*F hotter than that of the reactor coolant.
- l When the LTOP protection to the plant is provided by the RHR suction relief valves, all four RHR suction MOVs are opened to provide the required redundancy of the pressure relieving capacity. However, a single failure in one pressure
, transmitter could actuate the auto close interlock, thus isolating both RHR l trains, causing an everpressure event by the loss of the letdown flow, and I defeating the LTOP protection. To eliminate this single failure and render the LTOP a single-failure proof system KG&E proposes the following.
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- On decraasing RCS temperature and pressure to the RHRS entry conditions, when relying on RHRS for LTOP protection, the licensee proposes to open the four suction MOVs, then remove and lock out the power to NOVs 8702 A and 8701 B.
Valve opening and power removal are specified in the plant's Technical Specifi-cations.
Removing power to these two valves (defeating the interlocks) not only protects the RCS from single faliu're causing isolation of both RHRS suction relief ,
valves (loss of LTOPS), but also provides protection for both RHR pumps, when in operation, from a loss of suction due to a single pressure transmitter failure. Inadvertent isolation of the RHR suction valves has been a concern at other plants and has resulted in damage to a RHR pump.
~
On increasing pressure and temperature in addition to the nortial RHRS isolation procedures, KG&E proposes to add the following:
(a) . Administrative procedures to verify that power is restored to valves 8702A and 8701B and the valves are closed prior to exceeding the RHRS suction relief setpoint (this administrative procedure has already been implemented at the plant).
(b) Add an alarm circuit to the valves with the power locking feature, namely 8702A and 8701B, such that if any of these valves are open or do not have power available and the interlock activation setpoint is reached, the alarm would initiate on the main control board. If
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the alars initiates an annunciator alarm response, procedure wo01d require closing or verifying closure of the affected RHR suction isolation valves.
The existing auto close interlock has no visual indication in the control roora (other than valve position in'dication). Therefore, if a signal is generated to close the valve and the valve fails to close, the operator would not be alerted.
With the addition of the proposed alam circuit, if the valve is open or if ,
power is not available and the pressure setpoint is reached, an alarm is generated in the control room giving the operator positive indication. There-fore, protection is afforded if the operator fails to restore power or if the interlock actuates and the valve fails to close. Addition' ally, alarm response procedures would provide positive operator actions.
On increasing pressure and temperature,' if both series suction MOVs in one or
, more RHR trains were inadvertently left open, it would be difficult to continue pressurization. Furthermore, it would be highly unlikely for such a situation to go undetected during a normal startup due to indications such as relief valves lifting, pressurizer relief tank level, and pressure and temperature l alarms. These indications wou' 1 d alert the operator to take action to rectify '
the situation. If the reactor system pressure rises to the intericek setpoint l
despite the relief valve lifting, the operator would be alerted by an alarm.
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If only one suction MOV is inadvertently left open while the other series MOV is closed, then when the reactor system pressure rises to the interlock set-point the open valves would be closed by the auto-close interlock anS an alarm would sound in the control room.
With respect to the ability to'i' blate s the RHR system, should there be a break in the RHR system or a stuck open safety valve, it should be noted that one valve in each flowpath will have power available. Therefore, the operators ,
will retain the ability to isolate the system should the need arise.
Conclusion The staff has reviewed the licensee's proposed system and procedural modifica-tions to the Wolf Creek LTOP system and has reviewed the plant's Technical Specifir.ations and concludes.that in light of the plant's TS these modifica-tions are acceptable and that the LTO.P reliance on the RHRS suction relief valves meets the intent of the Standard Review Plan sections 5.2.2 and 5.4.7 and their associated Branch Techni' cal Positions 5-2 and 5-1 respectively.
Therefore, we conclude that the requirements of License Condition (13) have been met.
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