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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:INCOMING CORRESPONDENCE
MONTHYEAR05000482/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 05000482/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 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 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 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 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 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 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 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 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 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 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 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 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 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, 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 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 ML20209E0611999-07-0808 July 1999 Forwards Addl Pages to Rev 12 of USAR & Commitment Changes, Inadvertently Omitted from 990311 Submittal 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 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 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 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 ML20196G9681999-06-22022 June 1999 Informs NRC That BC Ryan Will Be Leaving Ks State Univ for Position with Wolf Creek Nuclear Operating Corp,Effective 990701 05000482/LER-1999-007, Forwards LER 99-007-00,re Condition in Which Wolf Creek Generating Station TS 3.3.2 Was Not Met.Commitments Made by Util Also Encl1999-06-18018 June 1999 Forwards LER 99-007-00,re Condition in Which Wolf Creek Generating Station TS 3.3.2 Was Not Met.Commitments Made by Util Also Encl ML20196A0251999-06-17017 June 1999 Requests That Written Exams for Reactor Operator & SRO for Plant Be Administered Beginning Wk of 990719 & Followed by Operating Exam During Wk of 990726 to Personnel Listed in Attachment.Proprietary Info Encl.Proprietary Info Withheld ML20195K0641999-06-15015 June 1999 Forwards MOR for May 1999 for Wolf Creek Generating Station & Corrected Page 2 of 2 of Apr 1999 Mor,Adding That Unit Entered Intomode 5 for Restart During Month of Apr & Correcting Shutdown Duration Hours from 672 to 671 ML20195G4391999-06-11011 June 1999 Provides Details for Missed Rept Re 10CFR50.46 Thirty Day Rept of ECCS Model Revs.Attachment I Provides Summary of Commitments Made in Submittal 05000482/LER-1999-005, Forwards LER 99-005-00,re Esfa.Commitments Made by Util Are Encl1999-06-11011 June 1999 Forwards LER 99-005-00,re Esfa.Commitments Made by Util Are Encl 05000482/LER-1997-027, Forwards LER 97-027-00 Re Identification of Missed Surveillance Required by TS 4.3.3.5.2.Encl 1 Identifies Actions Committed to by Util1999-06-0404 June 1999 Forwards LER 97-027-00 Re Identification of Missed Surveillance Required by TS 4.3.3.5.2.Encl 1 Identifies Actions Committed to by Util ML20195B9811999-05-26026 May 1999 Forwards 1998 Annual Repts for Ks Electric Power Cooperative Inc,Ks City Power & Light Co & Western Resources,Inc, Including Wholly Owned Subsidiary Kg&E Co ML20196L3361999-05-18018 May 1999 Forwards Rev 1 to Cycle 11 COLR for WCGS, IAW TS Section 6.9.1.9 05000482/LER-1999-004, Forwards LER 99-004-00 Re Failure to Maintain Containment Closure During Fuel Movement as Required by TS 3.9.4.c. Attachment I to Ltr Identifies Actions Committed to by Plant in Encl LER1999-05-12012 May 1999 Forwards LER 99-004-00 Re Failure to Maintain Containment Closure During Fuel Movement as Required by TS 3.9.4.c. Attachment I to Ltr Identifies Actions Committed to by Plant in Encl LER ML20206Q8141999-05-11011 May 1999 Requests NRC Work with Industry to Resolve Generic Changes to Allow Permanent Change to TSs Prior to June 2000.Encl Provides TS Limited Duration Action Statement Until 990930 05000482/LER-1999-003, Forwards LER 99-003-00,re Failure to Perform TS SR 4.9.2.c Prior to Entering Mode 6.Commitments Made by Util Are Encl1999-05-10010 May 1999 Forwards LER 99-003-00,re Failure to Perform TS SR 4.9.2.c Prior to Entering Mode 6.Commitments Made by Util Are Encl ML20206K5141999-05-0707 May 1999 Provides Info Re Number of Tubes Plugged in Each Sg,As Required by TS 4.4.5.5.ISI of SGs B & C Completed on 990424,resulting in Mechanical Plugging of One Tube in SG B & Five Tubes in SG C ML20206J0711999-05-0505 May 1999 Forwards Guarantees of Payment of Deferred Premiums for Owners of Wolf Creek Generating Station,As Required by 10CFR140.21 ML20206D9551999-04-29029 April 1999 Forwards 1999 Annual Radioactive Effluent Release Rept 22, for Reporting Period Jan-Dec 1998,per Section 6.9.1.7 of WCGS Ts.Attachment to Ltr Identifies Commitments Resulting from Correspondence ML20206C7321999-04-22022 April 1999 Provides Notification of Changes at WCGS Affecting Plant Physical Security Plan,Per 10CFR50.54(p).Changes Identified in Attachment I Will Be Incorporated Into Plan by 990831. Commitments Made by Util Are Included in Attachment II ML20206B2051999-04-20020 April 1999 Forwards Revs to RERP Implementing Procedures,Including Rev 1 to EPP 06-001, CR Operations, Rev 1 to EPP 06-002, TSC Operations, Rev 3 to EPP 06-004, Public Info Organization & Rev 1 to EPP 06-005, Emergency.. ML20205L7431999-04-0606 April 1999 Confirms 990401 Telcon with NRC Re Late Payment Notice That Util Received for Invoice RL0295-99.Licensee Understands Invoice to Be Cancelled ML20205F1601999-03-30030 March 1999 Forwards Rept Re Status of Decommissioning Funding for WCGS, Per 10CFR50.75.Kansas Gas & Electric Co Decommissioning Trust Agreement,Encl ML20205K9481999-03-26026 March 1999 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-482/98-05.Corrective Actions:Training Was Provided to Mrep Members Through Use of Contract Individual Experienced in Maint Rule Programs.Change to Commitment Date,Encl ML20196K7261999-03-26026 March 1999 Forwards Certified Copy of ITS & ITS Bases,As Committed in Licensee to Nrc.Summary of Editorial Corrections, Also Encl ML20205A1961999-03-25025 March 1999 Provides Suppl 2 to 970515 Application for Amend to License NPF-42,providing Changes to TS Based on 990310 & 19 Discussions with NRC Re Conversion to Improved TS 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A6951990-09-18018 September 1990 Requests one-time Waiver to Alter Licensed Operator Requalification Training Program Cycle to Be Better Aligned W/Natl Exam Schedule ML20059E6151990-08-29029 August 1990 Forwards Semiannual fitness-for-duty Program Performance Data Rept for Jan-June 1990,per 10CFR26.71(d) ML20059E9611990-08-28028 August 1990 Reaffirms Commitment to Safe & Responsible Operation of Facility in Face of Tender Offer for Util Stock.Accepts W/O Qualification,Responsibility for Continued Safe & Reliable Operation of Plant ML20059D5281990-08-27027 August 1990 Provides Correct Ltr Number for Jul 1990 Monthly Operating Rept.Correct Ltr Number Should Be No 90-0226 ML20059C1781990-08-21021 August 1990 Forwards Proprietary TR-90-0025 W01, Core Thermal-Hydraulic Analysis Methodology for Wolf Creek Generating Station, for Review & Approval by 920101.Rept Withheld (Ref 10CFR2.790) ML20059B3691990-08-21021 August 1990 Forwards Proprietary TR-90-0024 W01, Wolf Creek Nuclear Operating Corp Rod Exchange Methodology for Startup Physics Testing, Per Discussion at 890518 Meeting.Rept Withheld (Ref 10CFR2.790) ML20058P1001990-08-10010 August 1990 Forwards Wolf Creek Generating Station Inservice Insp Rept, for Fourth Refueling Outage,Period 2,Interval 1. Nonconforming Conditions Requiring Repair/Replacement of Supports Identified During Routine Maint Activities ML20058N1421990-08-0909 August 1990 Responds to Insp Rept 50-482/90-08 Re Effectiveness of Techniques Used to Detect Erosion/Corrosion Degradation. Existing erosion-corrosion Program Effective in Identifying Wall as Nonrelevant Volumetric Anomalies ML20058L2011990-08-0101 August 1990 Forwards Inadvertently Omitted Index of Proposed Tech Spec from Re RCS ML20055J0641990-07-26026 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-482/90-24.Corrective Action:All Dose Personnel Receiving Retraining within Normal 7-wk Training Cycle Which Began on 900723 & Emergency Procedure EPP 01-7.3 Will Be Revised ML20055H2091990-07-23023 July 1990 Informs That Util Has Commenced Cash Tender Offer to Purchase Outstanding Shares of Each Class of Common & Preferred Stock of Kansas Gas & Electric Co.Util Convinced That Proposed Merger Will Have No Effect on Plant Operation ML20055G8331990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20055F6671990-07-13013 July 1990 Forwards Monthly Operating Rept for June 1990 for Wolf Creek Generating Station & Corrected Pages 1,4 & 5 to May 1990 Rept ML20055D9941990-07-0505 July 1990 Forwards Addl Info Re Seismic Design Considerations for Certain safety-related Vertical Steel Tanks,Per 890525 Request ML20055D5011990-07-0202 July 1990 Forwards Change in Status of Licensed Operators Since Transmitted,Per 10CFR50.74 ML20055D0481990-06-29029 June 1990 Responds to NRC Re Violations Noted in Insp Rept 50-482/90-17.Corrective Actions:Procedure Adm 03-600 Revised on 900430,to Ensure That Respirator User Issued Model & Size for Which Fit Tested & Trained ML20055D2111990-06-29029 June 1990 Responds to Request for Addl Info Re Violations Noted in Insp Rept 50-482/90-05.Corrective Actions:Change Made to Adm 02-005, Reactor Operators Qualifications & Responsibilities ML20058K4011990-06-28028 June 1990 Forwards Emergency Preparedness 1990 Field Exercise Scenario for Exercise Scheduled for 900829 ML20043H2851990-06-18018 June 1990 Forwards Revised LERs 85-058-01 & 90-002-00,adding Rept Dates Inadvertently Omitted from Original Submittals ML20043G7691990-06-13013 June 1990 Responds to NRC 900514 Ltr Re Violations Noted in Insp Rept 50-482/90-16.Corrective Actions:Movement of Spent Pool Bridge Toward Location FF06 Halted & Bridge Crane Returned to Location DD02 ML20043F4051990-06-11011 June 1990 Forwards Monthly Operating Rept for May 1990 & Corrected Page 2 for Apr 1990 ML20043E8211990-06-0808 June 1990 Informs of Plant Radiological Emergency Preparedness Exercise for 1990 Scheduled for 900829.Schedule Discussed W/Personnel from Region IV Emergency Preparedness,Fema,State of Ks & Coffey County ML20043E7491990-06-0808 June 1990 Forwards Rev to Figure 3.4-2 to 880620 Application for Amend Revising Tech Specs 3/4.4.9.1 & 3/4.4.9.3.Rev Corrects Editorial Error ML20043E8721990-06-0505 June 1990 Notifies NRC of Changes in Status of Operator Licenses ML20043D3271990-05-31031 May 1990 Forwards Rev 17 to Physical Security Plan,Safeguards Contingency Plan & Security Training & Qualification Plan. Rev Withheld (Ref 10CFR73.21) ML20058K1911990-05-30030 May 1990 Forwards Radiological Emergency Preparedness Exercise Objectives for 1990 ML20043B4791990-05-24024 May 1990 Documents Administrative Error in Rev to Radiological Emergency Response Plan Submitted on 900116 ML20043B4361990-05-22022 May 1990 Responds to Request for Addl Info Re Proposed Revs to Tech Specs 3/4.4.9.1 & 3/4.4.9.3 Re Pressure/Temp Limits for RCS & Overpressure Protection Sys ML20042E8691990-04-30030 April 1990 Forwards Documentation of Util Ability to Make Payment of Deferred Premiums ML20042E3021990-04-13013 April 1990 Forwards Supplemental Response to NRC 900316 Ltr Re Violations Noted in Insp Rept 50-482/90-05.Corrective Actions:Air Check Valves to Main Steam & Feedwater Isolation Valves Added to Preventive Maint Program ML20012D9911990-03-22022 March 1990 Responds to NRC 900220 Ltr Re Violations Noted in Insp Rept 50-482/90-02.Corrective Actions:Procedure CNT-660, Rigging Revised to Incorporate safety-related Manway Covers Which May Be Removed W/O Addl Safety Evaluation ML20012C9841990-03-19019 March 1990 Provides Util Response to Generic Ltr 89-19 Re Request for Action on Resolution of USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Mods Made to ESFAS Logic Design ML20012C6841990-03-15015 March 1990 Responds to NRC 900213 Ltr Re Violations Noted in Insp Rept 50-482/89-26.Corrective actions:10CFR73.71,App G Reviewed to Determine If Any Reporting Requirements Not Properly Reflected in Security & Operations Procedures ML20012A1601990-02-23023 February 1990 Forwards Semiannual Radioactive Effluent Release Rept 10 for Jul-Dec 1989 & Rev 5 to ODCM for Wolf Creek Generating Station. ML20012A5631990-02-23023 February 1990 Forwards Total Pump Study & Revises Info Previously Provided on Safety Injection Pumps & Centrifugal Charging Pumps in Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. ML20006F7151990-02-21021 February 1990 Provides Present Levels of Onsite Property Damage Insurance Being Maintained,Per 10CFR50.54(w)(2) ML20012B0781990-02-14014 February 1990 Forwards Cycle 5 Radial Peaking Factor Limit Rept,Per Tech Spec Section 6.9.1.9 ML20006D6541990-02-0808 February 1990 Forwards Amend to Physical Security Plan.Proposed Change Will Require Submittal of Fingerprint Cards to NRC in Lieu of Currently Required Criminal Records Check.Proposed Changes & Safety Evaluation Withheld ML20006E3551990-02-0707 February 1990 Responds to NRC 900103 Ltr Re Violations Noted in Insp Rept 50-482/89-30.Corrective Actions:Communications Flow Process Between Facilities & Locations of Operations Status Boards Will Be Reviewed to Identify Needed Improvements ML20006E1871990-02-0707 February 1990 Advises That Bt Kckinney,Senior Reactor Operator,No Longer Employed at Util ML20011E1041990-01-30030 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Util Developed Plan & Schedule to Accomplish Reviews,Evaluations & Insps Recommended in Part IV ML19354E8831990-01-23023 January 1990 Forwards Response to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. ML20005G7791990-01-16016 January 1990 Forwards Monthly Operating Rept for Dec 1989 for Wolf Creek & Revised Operating Data Repts for Feb-Nov 1989,reflecting Thermal Generation Using New Calorimetric Procedure That Uses Main Steam Flow Instead of Feedwater Flow ML20006A0051990-01-16016 January 1990 Forwards Rev 25 to Facility Radiological Emergency Response Plan & Revs to Radiological Emergency Response Plan Implementing Procedures.Procedures Effective 891220 ML20005H1801990-01-15015 January 1990 Forwards Amend 4 to Indemnity Agreement B-99 ML20005E8591990-01-0404 January 1990 Certifies That Util Implemented fitness-for-duty Program That Meets Requirements of 10CFR26 ML20005E1921989-12-26026 December 1989 Affirms That Util Will Meet Schedule Requirements of Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. ML20011D4801989-12-20020 December 1989 Responds to NRC 891120 Ltr Re Violations Noted in Insp Rept 50-482/89-27.Corrective Actions:Personnel Completed Detailed Review of Tech Spec Surveillance Requirements to Ensure That Each Item Properly Addressed in Surveillance Procedures ML19332F8731989-12-14014 December 1989 Requests Authorization to Use ASME Section XI Code Case N-401-1, Eddy Current Exam,Section Xi,Div 1, Per 10CFR50.55a(a)(3),since Case Not Currently Listed in Reg Guide 1.147,Rev 7 as Endorsed by NRC ML19332F9131989-12-14014 December 1989 Notifies That DM Brown No Longer Employed at Facility as Senior Reactor Operator,Per 10CFR50.74 1990-09-18
[Table view] |
Text
P SNUPPS Stenderdised Nucleer Unit Power Plant System 5 Choke Chern Aced Nicholas A. Petrick Rockville, Meryland 20850 Executive Director (30 0 880401o January 25, 1985 SLNBC 85-4 FILE: 0543 SUBJ: Wolf Creek Technical Specifications Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory (bnmission Washington, D.C. 20555 Docket No. SIN 50-482 Refs: 1) KG3 (G. L. Koester) letter to NRC (H. R. Denton)', dated 12/10/84, Same Subject
- 2) NRC (D. G. Eisenhut) letter to KGE (G. L. Koester)~, dated 11/7/84, Same Subject
- 3) SINRC 85-2,1/18/85, Sane Subject
Dear Mr. Denton:
Reference 1 forwarded KGE's comments on the Final Draft version of Wolf Creek's Technical Specifications as issued by reference
- 2. Since reference I, several other changes have been identified which were forwarded with reference 3 and this letter. These changes were discussed with mernbers of your staff during meetings on rJanuary 17, 18, 24, and 25, 1985.
Very truly yours,
%<w Nicholas A. Petrick rJHR/bds/6a10 Attachnents cc: G. L.'Koester KGE
'J. M. Evans KCPL D. F. Schnell UE
'J. Neisler/B. Little USNRC/ CAL H. Bundy USNBC/WC W. L. Ebrney. USNRC/RIII D.'R. Hunter USNRC/RIV 8501290156 850125
{DRADOCK 05000482 PDR OO(
5
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l SOURCE RANGE RESPONSE TIME TESTING I
e During the review of Wolf Creek's Technical Specifications the NBC
- (Reactor Systems Branch) raised the question of why the Source j and Intermediate Range response times are "N/A" in Table 3.3-2.
These entries are also listed as "NA" in both revision 4 and draft E
revision 5 of the Westinghouse PWR Standard Technical Specifications.
E Investigation with Westinghouse revealed that these times are "N/A"
! because the Source and Intemediate Range instrments are not credited
[ in any safety analysis for protection during accident conditions.
Westinghouse safety analyses assmes only the Power Range instrmen-
! tation for protection.
! Historically, the NBC has accepted the argument that since the Source j Range instrmentation is required to be operable in mdes 3, 4, and 5 m and since the reactor trip frm the Source Range would occur earlier y than the trip from the Power Range, reliance on the Source Range
[. trip was acceptable. Operability of Power Range instrmentation was
[ therefore limited to mdes 1 and 2. W Source Range response times g were requested nor supplied.
ll l The NRC has requested that either the Power Range operability be E extended to modes 3, 4, and 5 or a response time for the Source Range trip be supplied to assure reactor protection in these Modes.
{
, It is KG&E's position that this is a generic issue since Westinghouse has perfomed similar safety analyses for other plants and the 'Ibchnical I
specifications for these plants, and the Standard Technical Specifi--
cations, have no requirements for Source Range response time or Power
- Range operability in Modes 3, 4, and 5. In order to ensure that the r solution to this question is carefully fomulated with full mder-s standing of all its implications and reprocussions, the question should
[ be resolved in an Owners Group form with participation by Westinghouse, the affected utilities, and the NRC.
{
In the interini, KGE's recent preoperational testirg progran has per-
? formed Source Range response time testirg and the results obtained show 6 response times less than that required for the Power Range. This 7 envelopes the situation of concern since the Source Range trip occurs at
{ a lower neutron flux level.
In addition KGE will support the Westinghouse Owners Group's efforts to pursue this and other issues identified in NUREG 1024 with the NFC Staff .
=
on a generic basis.
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'JHR/bds/6a25 2 . . . . . . .
8, CONTAINMENT SYSTEMS i
HYDROGEN MIXING SYSTEM LIMITING CONDITION FOR OPERATION 1
1 3.6.4.3 Two independent hydrogen mixing systems shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTION:
lWith one independent hydrogen mixing system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
-SURVEILLANCE REQUIREMENTS 4.6.4.3 Each independent hydrogen mixing system shall be demonstra-ted OPERABLE:
- a. At least once per 92 days on a STAGGERED TEST BASIS by t starting each non-operating system from the control room L and verifying that the system operates for at least 15 minutes.
! b. At least once per 18 months by verifying that on a Safety Injection test signal, the systems start in slow speed or, if operating, shif t to slow speed.
1 E
3/4 6-33 JHR/bds/6all
i FINAL DMFT BASES 7
SPRAY ADDITIVE SYSTEM (Continued) 5 solution recirculated within containment after a LOCA. This pH band minimizes
- the evolution of iodine and minimizes the effect of chloride and caustpic stress corrosion on mechanical systems and components. The contained solution f volume limitline discharge includes an or location allowance for solution other physical not usable because of tank characteristics. The educator flow test of 52 gpm with RWST water is equivalent to 40 gpm NaOH solution. These assumptions are consistent with the iodine removal efficiency assumed in the safety analyses.
' 3/4.6.2.3 CONTAINMENT COOLING SYSTEM g
The OPERABILITY of the Containment Cooling System ensures that: (1) the t
g containment air temperature will be maintained within limits during normal
= operation, and (2) adequate heat removal capacity is available when operated
{ in con, Junction with the Containment Spray Systems during post-LOCA conditions.
p The Containment Cooling System and the Containment Spray System are redundant to each other in providing post accident cooling of the containment atmosphere. As a result of this redundancy in cooling capaDility, the allowable out of-service time requirements for the Containment Cooling System have been i=
appropriately adjusted. However, the allowable out-of-service time require-ments for the Containment Spray System have been maintained consistent with i
that assigned other inoperable ESF equipment since the Containment Spray y System also pr.ovides a mech,anism for removing iodine from the containment i atmosphere.
[
{ 3/4.6.3 CONTAINMENT ISOLATION VALVES
- The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the 5 event of a release of radioactive material to the containment atmosphere or g pressurization of tne containment and is consistent with the requirements of GDC54 thru 57 of Appendix A to 10 CFR Part 50. Containment isolation within i the time limits specified for those isolation valves designed to close auto-t matically ensures that the release of radioactive material to the environment s will be consistent with the assumptions used in the analyses for a LOCA. -
3/4.6.4 COMBUSTIBLE GAS CONTROL p The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to
' maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. Either recombiner unit (or the Purge
[ System) is capable of controlling the expected hydrogen generati'on associated f
with: (1) zirconium water reactions, (2) radiolytic decomposition of water, and (3) c:rros un of me fis wi;nin can.;.i..r.en.. D.a ... r: gen Farge Suosysts g discharges directly to the Emergency Exnaust System. . Operation of the Emergency L Exhaust System with the heaters operating for at least 10 continuous hours in a i 31-day period is sufficient to reduce the buildup of moisture on the adsorbers t and HEPA filters. These Hydrogen Control Systems are consistent with the
$ recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concen-trations in Containment Following a Loss-of-Coolant Accident," Revision 2, November 1978.
p: A
N WOLF CREEK - UNIT 1 8 3/4 6-4 ,
k , ,
L',r. I
e l
I A. The Hydrogen Mixing Systems are provided to easiure adequate mixing of the containment atmosphere following a LOCA. This mixing action will prevent localized accumulations of hydrogen from exceeding the flamable limit.
- , - - - - ----..-ww.--- , , - , - . . , , - - - - - - - , , , -
e Specification 3/4.6.4.3 Page 3/4 6-33 Justification: '
- l. Deletion of the f an flow rate from STS surveillance requirement 4.6.4.3.b is done for consistency with the containment air cooler surveillance requirement 4.6.2.3.b which has no air flow measure-ment requirements.
In addition, the H, Mixing Fans are two-speed f ans (full and one-half speed) . The -normal operating flow requirenents (full speed) were established based on a nonnal ventilation requirement of 85,000 cfm each. This produces a half-speed flow rate of 42,500 cfm.
The design _ hydrogen mixing requirements (half speed) were estab-lished based on maintaining an air exchange rate of 5 changes per hour for the containment volume below the operating level. This
~r esulted in a required flow rate of 12,500 cfm for each of two fans.
Therefore, since the required flow rate of 12,500 cfm is so much smaller than the actual flow rate of 42,500 cfm, it is not nec-essary to verify flow rates, only that the f ans are operating properly.
It should also be noted that the H mixing f ans post LOCA operation is supplemented by the exp ed containment post-LOCA air flow patterns. Both the containment coolers and the con-tainment sprays cool the containment atmosphere causing it' to drop to the lower cor.tainment elevations where the containment heat load and the H7 mixing f ans then cause it to rise to the upper regions of the containment.
JHR/bds/6a6 i
w _ _ _
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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 3) Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day tark, ts %o 4- voo - Lt ao LIcitb
- 4) Verifying the diesel starts from ambie t condition and accelerate f.o at least 514 rpm in less than or eq al to 12 seconds.* TJe' generator voltage and frequency shall 4000 _ 320 vcit g nd 60 + 1.2 Hz within 12 seconds
- after the start signal. The diesel generator shall be started for this test by using one of the following signals:
a) Manual, or b) Simulated loss-of offsite power by itself, or c) Safety Injection test signal.
- 5) Verifying the generator is synchronized, loaded to greater than or equal to 6201 kW in less than or equal to 60 seconds,* operates with a load greater than or equal to 6201 kW for at least 60 minutes, and
- 6) Verifying the diesel generator is aligned to provide standby power to the associated emergency busses,
- b. At least once per 31 days and after each operation of the diesel where the period of operation was greater than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by checking for and removing accumulated water from the day tanks;
- c. At least once per 31 days by checking for and removing accumulated water from the fuel oil storage tanks;
- d. By sampling new fuel oil in accordance with ASTM 04057 prior to addition to storage tanks and:
(1) By verifying in accordance with the tests specified in ASTM 0975-81 prior to addition to the storage tanks that the sample has:
(a) An API Gravity of within 0.3 degrees at 60 F or a specific gravity of within 0.0016 at 60/60 F, when compared to the supplier's certificate or an absolute specific gravity at 60/60*F of greater than or equal to 0.83 but less than or equal to 0.89 or an API gravity of greater than or equal to 27 degrees but less than or equal to 39 degrees;
- These diesel generator starts from ambient conditions shall be performed only once per 184 days in these surveillance tests and all other engine starts for the purpose of this surveillance testing shall be preceded by an engine prelube period and/or other_ warmup procedures recommended'by the manufacturer so that the mechanical stress and wear on the diesel engine is minimizRd WOLF CREEK - UNIT 1 3/4 8-3
ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
(b) A kinematic viscosity at 40 C of greater than or equal to 1.9 centistokes, but les.s than or equal to 4.1 centistokes, if gravity was not determined by comparison with the sup-plier's certification; (c) A flash point equal to or greater than 125 F; and (d) A clear and bright appearance with proper color when tested in accordance with ASTM 04176-82.
(2) By verifying within 30 days of obtaining the sample that the ~
other properties specified in Table 1 of ASTM 0975-81 are met when tested in accordance with ASTM 0975-81 except that the analysis for sulfur may be performed in accordance with AST D1552-79 or ASTM 02622-82.
- e. At least once every 31 days by obtaining a sample of fuel oil in accordance with ASTM D2276-78, and verifying that total particulate contamination is less than 10 mg/ liter when Checked in accordance with ASTM 02276-78, Method A.
- f. At least once car 15 men ns. cur; ; s =:::c e t.
a _, Suojec.in; ne ciesel :c an insoect'on in accercance c :-
croceceres ore:are ir. conjunc:icn with its manufactureds recommendations for tnis class of s.andby service,
- 2) Verifying the diesel generator capability to reject a load of greater than or_ -equal'.o 1352 kW (ESW pump) while maintaining voltage 4000 _,320 v ts anc frequency at 60 + 5.4 Hz, asuo ruso -aqo
- 3) Verifying tne aiese r rator capability to reject a load of 6201 kW without tripping. The generator voltage shall not exceed 4784 volts during and following the load rejection,
- 4) Simulating a loss-of-offsite power by itself, and:
a) Verifying deenergization of the emergency busses and load shedding from the emergency busses, and b) Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 12 seconds, energizes the auto-connected shutdown loads through the shutdown sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization, the steady-state voltage and f equen f the emergency busses shall be maintained a 4000 -320- olts and 60 + 1.2 Hz during this test. q[g 4%
WOLF CREEK - UNIT 1 3/4 8-4
e ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 5) Verifying that on a Safety Injection test signal without loss-of-offsite power, the diesel generator starts on the auto start signal and operates on standby for greater than or equal to 5 minutes; and the offsite power source energizes the auto-
'onnected emergency (accident) load through t e t0CA-sqquencer.
The generator voltage and frequency shall be '000 ; 3 M \ volts
- and 60 1 1.2 Hz within 12 seconds after the to-start st nal; the generr. tor steady-state generator voltag and frequency all be maintained within these limits during t q test; N 4 # 4so HW W 0 0
- 6) Simulating a loss-of offsite power in conjunction with a%Tety Injection test signal, and a) Verifying deenergization of the emergency busses and load shedding from the emergency busses; b) Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 12 seconds, energizes the auto connected emergency (accident) loads through the LOCA sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with emergency loads. After energization, the steady-state voltage and fyequency %
the emergency busses shall be maintained a[4000 ; 320 v 'ts and 60 1 1.2 Hz during this test; and eoww-no c) Verifying that all automatic diesel generator trips, except high jacket coolant temperature, engine overspeed, low IL %
oil pressure, high crankcase pressure, start failure relay, and generator differential, are automatically bypassed upon loss of voltage on the emergency bus concurrent with a Safety Injection Actuation signal.
- 7) Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel generator shall be loaded to greater than or equal to 6821 kW and during the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the diesel generator shall be loaded to greater than or epc8TTtri kW. The generator voltage and frequency shall bp 1000-+-320- olts and 60 + 1.2 Hz,
- 3 Hz within 12 seconds after the start ignal; the steady-state 7eneqator voltage and fr quency sha 1 be maintained within unco t:6e Mao 40001320 volts and 60 1 1. z during th test. Within 5 minut W after completing s 24-hour test, erform Specifica-tion 4.8.1.1.2f.6)b)*;
4 tbo + 16e Wao v
- If Specification 4.8.1.1.2f.6)b) is not satisfactorily completed, it is not necessary to repeat the preceding 24-hour test. Instead, the diesel generator may be operated at 6201 kW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or until operating temperature has stabilized.
WOLF CREEK - UNIT 1 3/4 8-5
a g, b
REFUELING OPERATIONS FINAL BRAFT l
SURVEILLANCE REQUIREMENTS (Continued) 2)
Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Pcsition C.6.a of Regulatory Gyide 1.52, Revisison less than March 1978, for a methyl iodif l# penetration-of and -+ J, - o % .+ a u au W G- .
- 3) 5 me4y C;Na VerifyingYsystem flow rate of 9000 cfmMduring system operation when tested in accordance with ANSI N510-19 E 1980.
c.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%;
- d. At least once per 18 months by: or epal 40 71
- 1) Verifying that the pressure drop across the com ined HEPA filters and charcoal adsorber banks is less than inches Water Gauge while operating the system at a flow rate of 9000 cfm( -1GD +3 -M
- 2) Verifying that on a%.a h Wat.)
5 p,. . a. f a . 3T M Gaseous Radioactivity-High I
test signal, the system automatically starts (unless already operating) and directs its exhaust flow through the HEPA filters and charcoal adsorber banks and isolates the normal fuel building exhaust flow to the auxiliary / fuel building exhaust fan; 3)
Verifying that the system maintains the Fuel Building at a negative pressure of greater than or equal to 1/4 inches Water Gauge and relative to the outside atmosphere during system operation;
- 4) Verifying that the heaters dissipate 37 2 3 kW when tested in accordance with ANSI N510-1975.
fe. After each complete or partial replacement of a HEPA filter bank, by I
verifying that the cleanup system satisfies the in place penetration gpc,E and bypass leakage testing acceptance criteria of less than 1% in g.,g accordance with ANSI N510-1975 for a 00P test aerosol while operating the system at a flow rate of 9000 cfm i 10%; and k
W ed , f.
After each complete or partial replacement of a charcoal adsorber
-p LeM
} bank, by verifying that the cleanup system satisfies the in place-l penetration and bypass leakage testing acceptance criteria cf less l ( than 1% in accordance with ANSI N510-1975 for a halogenated
< hydrocarbon refrigerant test gas while operating the system at a flow rate of 9000 cfm i 10%.
WOLF CREEK - UNIT 1 3/4 9-18
~
%~ -
R ML Mf5T 3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.1 ACCUMUltitf The OPERABILITY of each Reactor Coolant System (RCS) accumulator ensures that a sufficient volume of borated water will be immediately forced into the core through each of the cold legs in the event the RCS pressure falls below the pressure of the accumulators. This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.
The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the safety analysis are met.
The accumulator power operated isolation valves are considered to be
" operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met. In addition, as these accumulator isolation valves fail to meet single failure criteria, removal of power to the valves is required.
The limits for operation with an accumulator inoperable for any reason except an isolation valve closed minimizes the time exposure of the plant to a LOCA event occurring concurrent with failure of an additional accumulator which may result in unacceptable peak cladding temperatures. If a closed isolation valve cannot be immediately opened, the full capability of one accumulator is not available and prompt action is required to place the reactor in a mode where this capability is not required.
na reouirement to verify accumulator isolation valves shut with nm r removed from the ralve ep r2+nr when the preun*42 r i =vila ensures the accumlators will not infact s tor ano ca h a p e "ra transient when the Da20tc. Cuviant System is on solid plant pressure control. ~
3/4.5.2, 3/4.5.3, and 3/4.5.4 ECCS SUBSYSTEMS The OPERABILITY of two independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.
Either subsystem operating in conjuncticn with the accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward. In addition, each ECCS subsystem provides long-term core cooling capability in the recirculation mode during the accident recovery period.
With the RCS temperature below 350'F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
WOLF CREEK - UNIT 1 B 3/4 5-1 !
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