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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
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. November 30, 1989J
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.VM 89-0264 4, '
U. S. Nuclear Regulatory Coaunission ATTN: , Document Control Desk;
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Subjects.--Docket No.150-482: Revision to Technical Specifications.
- 3.4.1~.4.2,.3.5.4, 4.9.8.1, and 4.9.8.2 - Residual Heat
! Removal Flow Rate and Safety Injection Pump Availability: s M Gentlemen:-
Tlie~ purpose: of- this letter is-to' transmit ~an application for amendment:to Facility . Operating 1.icense No. . NPF-42 for, Wolf Creek Generating Stationt
- (WCGS),:- _ ' Unit ' ~ No . -- /1.x This-license _ amendment request proposes revisingt Technical Specification 3.4.1.4.'2 to change a note ate the bottom? of page J3/4.4-6 to. add the additional criterion of ensuring the reactor vessel water: 1 ilevel is1above the vessel flange before the-running Residual.- Heat Removal (RHR) ' pump can-be stopped while in. Mode 5 with the, rector coolant loops not '
1 filled.' "In addition,. .this amendment request proposes revising Technical
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' Specifications-4.9.8.1 and:4.9.8.2 to decrease the; required. flow rate of'the W runningL RHRipump. _ Finally, this amendment' request proposes revising the
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Technical- _ Specification ;3.5.4 mode-' applicability. to have 'the' Safety y :Injec.tlon Pumps immediately available to>the' Operators should RHR-cooling be l, ~ lost ~ when' the Reactori Coolant' level: is below the vessel' flange'.
[ Additionally technical ; specification changes related to the removal of the l RHRLautoclosure interlock.are planned for' future submittal by Wolf Creek ;
'NucleariCperation Corporation. These changes will further enhance the safe l operation of WCGS during' shutdown conditions.'
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, h'h. ALcomplete. Safety . Evaluation and No Significant Hazards Consideration- '!
determination are provided' as Attachments I and II, respectively. The .;
proposed changes to .the Technical' Specifications are provided as :
H pgg (Attachment'III. Wolf Creek Nuclear Operating Corporation requests that this !
b8 Technical: Specification amendment request be approved by March 1, 1990 to '
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I facilitate itsuse during the fourth refueling outage at WCGS scheduled to begin on March 15,,1990.
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In accordance with 10 CFR 50.91, a copy of this application, with L, y attachments, is being provided to the designated Kansas State official.
L 'g m Thio proposed revision to the WCGS Tebhnical Specifications will be fully implemented within 30 days of formal Nuclear Regulatory Commission approval.
OD P.O. Box 411/ Burangton, KS 86830 / Phone: (316) 364-8831
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R' ;WH 89-0264 Page,2 of 2' !
. November 30, 1989-lf- ,
R _If ;you' have ,any' questions concerning this' matter, pleaseicentact me-or' 7
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Mr.y.0'. L. Maynard of my.: staff.
Very truly.yours, y
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'Bart D. Withers President and
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Attachments:' I - Safety Evaluation !
II . Addressing ~The Standarde In 10~CFR'50.92 III - Proposed Technical Specification Changes :
cca 'G. W. Allen (KDHE), w/a
- l. .B. L. Bartlett (NRC), w/a
! . E.-. J. Holler . (NRC) , w/a
'R. D.' Martin (NRC)..w/a 'y
.D. V. Pickett.(NRC), w/a L .
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i Bart D. Wit'hers, of lawful age. - being first duly sworn upon oath says that c- _helis President and Chief Executive Officer of Wolf Creek Nuclear Operating Corporations. that he has read the foregoing document and knows the content thereof that he has executed that same for and on- behalf of said -j
- Corporation with full power 'and authority to do so and that the facts !
therein- stated' are' true and correct- to the best of his knowledge, information'and belief.
By Bart b. Withers President and Chief Executive Officer I
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. SUBSCRIBED and sworn to before me this 3 o day of M M 1989.
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Expiration Date ^/ /990
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ATTAcalENT I SAFETY EVALUATION-o l ?
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- Attachment I to WH 89-0264 i Page 'l of 4 q SAFE N EVALUATION 1
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Description of Channes ,
n Technical Specifications 4.9.8.1 and 4.9.8.2 currently requires ' a flow of greater than 2800 gpm from at least one Residual Heat' Removal (RHR) pump.
Technical Specification 3.5.4 requires.both safety injection pumps to be inoperable, when the plant is in H0DE 5 or in AODE 6 with the reactor vessel ;l head on. The note at the bottom'of the page for LCO 3.4.1.4.2 allows 'the )
running RHR pump to be-stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, while-in MODE 5 with the-reactor coolant loops not filled, provided nothing is done that would allow
-a dilution and core outlet . temperature remains at- least 100F- below saturation temperature. ;
A The proposed changes to 4.9.8.1 and 4.9.8.2, decreases the required flow rate of the running RHR pump from t 2800 gpm to t_1000'gpm and: sufficient to y maintain the RCS temperature at 5 1400F. The proposed change to '3.5.4- H changes th,e APPLICABILITY from MODE 5 and MODE 6 with'the reactor vessel j head on, to MODE 5 and MODE 6 (with the reactor vessel head on)_with water 1 .'
level 'above the reactor vessel flange. The proposed change to the note at the_ bottom of the page-to LCO 3.4.1.4.2 adds the additional criteria of j ensuring the reactor' vessel water level is above the vess'el flange before- 1
-the running RHR pump can be stopped while in HODE 5 with'the reactor coolant loops not filled. .The' Bases to 3/4.5.4 and 3/4.9.8 are alsor being changed
. to-reflect these proposed changes.
,Baskaround NRC Generic Letter 88-17 reco:mmended several program enhancements that each nuclear unit should consider. Among these recommendations, _ was the following
" Technical Specifications that restrict or limit the safety benefit of the actions ' identified- in this letter should be identified and appropriate changes should be submitted."
Wolf Creek Nuclear Operating Corporation (WCNOC) has identified these changes as enhancements to the present Wolf Creek Generating Station (VCGS)
Technical Specifications.
The flow requirements for 3/4.9.8.1 and 3/4.9.8.2 ensures that; (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the Reactor Vessel below 1400 F as required during the refueling mode,- and (2) sufficient coolant circulation is maintained through the core ,
to minimize the effect.of a boron dilution incident and prevent boron I stratification.
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Attachment I to WM 89-0264 Page 2~of 4 The requirement'to have no operable Safety Injection Pumps in MODE S or 6 with. the reactor vessel head on, provides assurance that a mass addition.
pressure transient can be relieved by the operation of a single Power Operated Relief ~' Valve (PORV) or RHR suction relief valve. The proposed-change to 3.5.4 will allow the safety injection pumps to be' immediately available to the operators, should RHR cooling be lost. 'when the reactor coolant level is below the vessel flange. As technical specifications are currently written, both safety injection pumps must be safety tagged out of servi'ce with their breakers racked down in MODES -5 and 6 whenever the reactor vessel head is in' place. For the operators to use a safety injection pump after a loss of.RHR they must remove the safety tags and rack up the breaker prior to running the pump. It is estimated that it will take approximately 15 to 20 minutes to get a pump running. With the proposed change, the operators could have a safety injection pump running in approximately one minute.
The note at the bottom of the page for Technical Specification Limiting condition for Operation (LCO) 3.4.1.4.2, presently allows the running RHR pump to be stopped for up to I hour with the reactor coolant loops not filled in MODE 5. The two criteria that must be met when the RHR pump is i stopped prevent stratification of the coolant boron concentration and j prevent . core boiling. The proposed change to reduce the RHR minimum flow j rate in MODE 6, while maintaining decay heat removal requirements, reduces I potential problems due to vortexing and subsequent loss-of the RHR system. l
~The'added restriction'to the Technical Specification 3.4.1.4.2 footnote is '
proposed so that the operating RHR pump cannot be intentionally deenergized for one hour when reactor vessel water level is below the vessel flange.-
Thiv- will ensure that -the operating pump will not be intentionally deenergized during operation with the RCS loops partially filled.
Evaluation i A reduction of RHR flow in the shutdown cooling mode could potentially l affect the decay heat removal rate, boron stratification, and the boron 7 dilution accident analysis. The present Bases for Technical Specification 3/4.9.8 specifies that at least one RHR train be in operation to ensure
, thats (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140 0F as required during the refueling mode, and (2) sufficient coolant circulation is maintained through l the core to minimize the effect of a boron dilution incident and prevent l boron stratification.
The WCGS Technical Specifications do not contain provisions to minimize the potential for vortering and air entrainment in the RHR system which may occur during Reactor Coolant System (RCS) operation under certain conditions. Although the current requirement for a minimum 2800 gpm flowrate is conservative for decay heat removal and uniform boron mixing, it is clear that minimizing the potential for vortexing was not considered when i the minimum flow rate requirement was established. I l
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Attachment I to WM 89-0264
= Page= 3 of 4-Operation with the RCS partially drained in MODES 5 and 6 ise.necessary for required inspection and maintenance on RCS components such as reactor coolant pumps and steam 1,enerators.- A reduced RHR flow rate would provide a greater margin- to vortexing and preclude an inadvertent loss of decay heat removal capability due f.o air entrainment and cavitation of the RHR. pumps.
The likelihood of vortering at the auction of the RHR' pumps could be lowered by' reducing the RHR firsw rate.
As the time.after plant shutdown increases decay heat removal requirements:
for the RHR system flow are reduced since decay heat decreases'as a function of time after initial reactor shutdown. However, continuous de ay heat removal- capability is still required. Since the consequences'of a loss of decay heat removal during the RCS partial drain conditions can be severe, the RHR system flow rate should not only meet decay heat removal.and uniform coolant boron mixing requirements, but should also consider minimizing, the potential' for loss of RER flow by vortexing and air'entrainment at the RHR pump suction.
I Revisions to Technical Specifications 4.9.8.1 and 4.9.8.2 are proposed so !!
that RER system flow rate may be reduced to the greater of the, flow required j to maintain the water in the' reactor vessel below. 1400F or' 1000 . gpn . R Although a reduced flow rate is not required for: prevention of-vortexing and air.entrainment for water levels above the . reactor vessel flange greater than 23 feet (Technicel Specification 4.9.8.1)..-this change is being made j for consistency to minimize operator confusion and human factors-problems. -1 i
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'The added restriction to the Technical Specification 3.4.1.4.2 footnote is
- proposed.so that the operating RER pump cannot be intentionally deenergized for one, hour when teactor vessel water level is below the vessel flange. i This will ensure that the operating pump will not be intentionally deenergized-during operation with the RCS loops partially filled.
An evaluation of boron dilution and boron stratification at RHR flow rates of 1000 gpm has been performed. The'results of this evaluation indicate ;
that the minimum required RHR flow rate is established at 1000 gpm for these I two concerns. .
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Attachment I to WH 89-0264
-Page: 4 of 4 Allowing the Safety Injection Pumps to be operable affects the~ cold over-pressure. analysis. Whenever the reactor coolant level is below the vessel flange, there is a minimum empty volume of approximately ,17,000 gallons. These pumps would only be used in an emergency situation, while attempting to return an RHR pump to. service. This empty space will. allow
.the- operators- sufficient. room to provide cooling to the core and still not completely fill the reactor coolant system.
Based on the above discussions and the considerations- presented in-Attachment II, the proposed revision to the WCGS Technical Specifications does not increase the probability of occurrence or the consequences of an accident .or malfunction of equipment important to safety previously evaluated in the safety analysis reports or create a possibility for- an accident or malfunction of a'different. type than any previously' evaluated in the safety analysis report lor reduce the margin of safety as defined in the. basis for any technical specification. Therefore, the proposed revision.
doesinot adversely affect or endanger the health or safety of the general public'or involve a significant safety hazard.
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ATTACBIENT II-d > j' q i
ADDRESSING THE STaunantut IN 10 'CFR'50.92 -- ;
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anmen8ING THE STAlmanns IN 10 CFR 50.92 The' proposed changes revise Technical Specification 3.4.1.4.2 to change a note at1 the bottom of page 3/4.4-6 to add the additional' criterion of ensuring the reactor vessel water level is above the vessel flange before .i the running Residual Heat Removal (RHR) pump can be stopped in MODE 5 with l the reactor coolant loops not filled. In. addition, the proposed changes' !
would revise Technical Specifications 4.9.8.1 and 4.9.8.2 to decrease the j required flow rate of the running RHR pump. Finally,- the proposed: change would revise Technical Specification.3.5.4, changing the mode applicability so-that the safety injection pumps would be immediately available to the operators should RHR cooling be lost when the reactor coolant level is below the vessel flange. The following sections discuss the proposed _ changes i
- under the three 10 CFR 50.92 standards:
Standard 1 - Involve a Significant Increase in the Probability' or Consequences of an Accident Previously Evaluated These changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. The change to the RHR
-flow rate reduces the probability of a loss of decay heat removal .due to. ,
- vortexing-and~ cavitation, while the probability of accidents analyzed in the
' Updated Safety Analysis Report (USAR) are unaffected. A reduction of RHR flow could potentially affect decay heat-removal rate, boron stratification. '
and the boron dilution accident analysis. An evaluation concluded that the consequences of these accidents are not increased. Allowing the-safety injection pumps to be operable affects the cold over-pressure analysis.
Whenever _the rector coolant level is below the vessel flange, there is'a minimum; empty volume of approximately 17,000 gallons. .These pumps would ,
only be used in an emergency. situation, while attempting to return an RHR
' pump to service. This empty space-will allow the operators sufficient room to provide cooling to the core and still not completely fill the reactor coolant system.
Standard 2 - Create the Possibility of a New or Different Kind of Accident Frosa any Accident Previously Evaluated These changes do not create the possibility of a new or different kind of g
accident from any accident previously evt.luated. The WCGS Technical Specifications do not contain provisions to minimize the potential for vortexing and air entrainment in the RHR system which may occur during RCS operation under certain conditions. Although the current requirements for a minimwn 2800 gpm flow rate is conservative for decay heat removal and uniform boron mixing, it is clear that minimizing the potential for vortexing was not considered when the minimwn flow rate requirement was established.
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L Attachment II to WM 89-0264
', Page 2 of 2-1 0 -Revisions to Technical Specifications 4.9.8.1 and 4.9.8.2 are proposed so
.that RHR system. flow rate may be reduced to the greater of the flow required to maintain the water in the reactor vessel. below 140 0 F or 1000 gpm.
Although a reduced flow rate is not required for prevention of vo'!texing and-
- air'entrainment for water level above the reactor flange greater than 23 feet (Technical' Specification 4.9.8.1), this change is being made for -l consistency to minimize operator confusion _and human factors problems. -l Allowing the Safety Injection Pumps to be operable gives the operators added flexibility in providing cooling to the core whenever- RHR cis lost. The requirement that the reactor coolant 1cvel be below the vessel flange prior to making the pumps operable.- provides a sufficient empty volume to not 1 completely fill the reactor coolant system, i Standard 3 - Involve a Significant Reduction in a Margin of Safety 1
These changes do not involve a significant reduction in a margin or safety.
- Operation with the RCS partially drained in MODES 5 and 6 is necessary for I required inspection and maintenance on RCS components such as reactor coolant pumps and steam generators. A reduced RHR flow rate would provide a greater margin sto vortexing and preclude an-inadvertent loss of decay heat removal capability due to air entrainment and cavitation _of_the RHR. pumps.
- The. likelihood of vortexing at the suction of the RHR pumps could be lowered by reducing.the RHR flow rate.
The proposed minimum flow rate of 1000 gpm and ensures a sufficient. flow rate as assumed in the boron dilution and boron stratification evaluations.
Having reactor coolant level below the vessel flange prior to making tha safety injection pumps operable provides sufficient empty volume in the ,
reactor coolant system, to where cold over-pressure concerns are negligible.
The' change that adds the restriction to the Technical Specification
. 3.4.1.4.2 footnote will ensure that the operating pump will not be
-intentionally deenergized during operation with the RCS loops partially filled.
, . Based on the above discussions and those presented in Attachment I, it has been detennined that the requested Technical Specification revisions do not involve a significant increase in the probability or consequences of an accident or other adverse condition over previous evaluations or create the possibility of a new or different kind of accident over previous evaluations; or involve a significant reduction in a margin of safety.
Therefore, the requested changes do not involve a significant hazards consideration.
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