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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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s Wi#LF CREEK NUCLEAR OPERATING CORPORATION John A. saney VW Proddent
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- MirCh 22,1988 ET 88-0043 U.S. Nuclear Regulatory Commission AT7N: Document Control Desk Washington, D.C. 20555 Subj: Docket No. 50-482: Request for Relief from Certain Requirements Delineated in ASME Section XI Gentlemen The purpose of this letter is to transmit two reqtasts for relief from certain requirements delineated in Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. The first request concerns a case in which a code required N-2 Manufacturers Data Form is missing for a Reactor Coolant Pump Seal Water Injection Throttle Valve.
The second request concerns material which does not fully meet ASME code requirements which was used to manufacture the packing box for a pressurizer spray valve which does, not meet code requirements. These requests would allow continued operation until the next outage of sufficient duration at proper plant conditions to replace these components. The details of the relief requests have been discussed with Mr. Paul O'Connor and other members of the Nuclear Regulatory Commission Staff.
Enclosed is a check (No. 1018) for $150.00 application fee required by 10 CFR 170.21. If you have any questions concerning this matter, please contact me or Mr. O. L. Maynard of my staff.
Very Truly Yours, J/,a a 8803300167 000322 2 John A. Bailey PDR ADOCK 050 j P Vice President Engineering and Technical Services JAB /jad Attachment )
Enclosure ,
cci P. W. O'Connor (NRC), 2 w/a ,
d' [50 R. D. Martin (NRC), w/a g B. L. Bartlett (NRC), w/a P0. Box 411/ Burtington, KS 66839 / Phone: (316) 364 8831 (Of An Equal opsortney Ernpooyer nAF tCVET
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i Attachment 1 to WM 88-0043 F
Attachment 1 to ET 88-0043 Page 1 of 2 March 22, 1988 Component Valve BG V200 (ASHE Code Class 2) - Reactor Coolant Pump 'C' Seal Water Injection Throttle Valve Description The reactor coolant pump seal water injection is part of the Chemical and Volume Control system which continuously supplies filtered water to each of the reactor coolant pump seals. Seal water flow is throttled to approximately 8-12 gpm per pump by valves BG-Vl98, Vl99, V200, and V201. In addition, these valves serve a flow-limiting function to prevent run-out of the safety injection / centrifugal charging pumps and to limit flow to an affected loop following a LOCA. During Refuel II. valve BG-V200 had the stem / disc asseebly replaced (these items are pressure retaining per definition of the ASME Code).
After the resumption of power operation, it was discovered that the N-2 Manufacturers Partial Data Report does not exist for these parts as required by the ASKE code.
Reauested Relief Article IWA-7210 of ASME Section XI states, in part, "Replacements shall meet the requirements of the edition of the Construction Code to which the original component or part was constructed...". This valve was originally constructed to ASME Section III which in Article NA 3130 (f) requires, 'the Manufacturer or the Installar shall be responsible for code compliance of the completed item or installation including code symbol stamping and providing the Data Report Form is properly executed and countersigned by the Inspector".
10 CFR 50.55a (g)(5)(iii) states that, "If the licensee has determined that l
conformance with certain code requirements is impractical for its facility, i the licensee shall notify the commission and submit, as specified in l paragraph 50.4, information to support the determinations'. Wolf Creek Nuclear Operating Corporation (WCNOC) has determined that the code requirement i to have the Data Report Form is impractical since this form does not exist for this valve. The Commission was notified on March 18, 1988, via telephone, of l
i this situation and information to support the determination is provided below.
Basis for Relief Upon discovery of the code noncompliance, a detailed review of the documentation provided with the stem / disc assembly was performed. This review l
revealed that the design requirements for the stem / disc assembly are correct and the material met the code requirements. In addition, the documentation showed that the welds were NDE examined and accepted.
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Attachment 1 to ET 88-0043 Page 2 of 2 March 22, 1988 This failure to meet the code requirements is considered to be a documentation problem and WCNOC does not have any technical concerns with this issue. As such, continued operation of the plant is considered acceptable with relief from this code requirement. However, to restore this component to compliance with the ASME code requirements, the stem / disc assembly shall be replaced at the next outage of sufficient duration at proper plant conditions. In any case, this assembly will be replaced no later than startup following the next refueling outage.
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I Attachment 2 to lof 88-0043 h
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Att: chm:nt 2 to ET 88-0043 Page 1 of 7 March 22, 1988 COMPONENT Valve BB PCV 455B American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code Class 1) - Pressurizer Spray Valve DESCRIPTION Component Description and Operatina History Valve BB PCV 455B is one of two 4 inch pressurizer spray valves. It is an ASME Code Section III Class 1 air-operated ball valve built by Fisher Contrels and supplied by Westinghouse. The packing box assembly consists of the packing box and attached leakoff pipe nipple. The packing box assembly is the structural interface between the valve body and the actuator assembly and forms part of the valve pressure boundary. It carries the weight and other operational loadings imposed by the actuator assembly. The packing box contains the packing seal between the shaft and packing box.
This valve has performed satisfactorily since initial installation except as noted below. During plant operations it has been subjected to routine operational function tests, leakage tests and normal preventative maintenance.
On January 9, 1987, a body-to-packing box leak was discovered. The packing box-to-body bolting was torqued to vendor specifications, 220 ft-lbs, without stopping the leakage. The decision was made to temporarily seal the valve by leak-seal compound injection. This was successfully completed on January 19, 1987. A replacement packing box assembly was ordered and installed during the Refuel II Outage on October 9, 1987. Post maintenance testing was completed on December 28, 1987, prior to plant start-up.
Procurement and Installation of Replacement Part Upon determination that replacement of the subject valve's packing box l assembly was required, WCNOC Purchase Order No. 521144 was issued on August 3 I 1987. This safety-related P.O. directed Westinghouse to procure two each of the packing box assemblies in accordance with their ' Renewal Parts Procurement and Supply System," OPR 405-5. Westinghouse is qualified by WCNOC to procure i
replacement parts using this system and when invoked, it is intended to l provide parts of the same quality as the originals.
l l In the case of the packing box assemblies, Westinghouse inadvertently ordered l the items from the manufacturer (Fisher Control) at a lower quality level than the original parts. As a result, the manufacturer fabricated the packing box l assemblies at a non-nuclear facility using available stock, Type 316 stainless j steel bar material.
l The two packing box assemblies and manufacturer's Certification of I Conformance were received at Wolf Creek on August 19, 1987. Using the l Westinghouse Purchase Order (No. HN76817D) to Fisher control as criteria, i Quality Control inspectors verified that the proper documentation had been l
received. However, because the Westinghouse P.O. was in error, the inspectors l
' AttachmInt 2 to ET 08-0043 Page 2 of 7 March 22, 1988 verified only the receipt of the Certificate of Conformance, rather than the more comprehensive ASME Code data package which would have includsd an N-2 code data form, material test reports and non-destructive examination repotts.
One of the two packing box assemblies was installed on the subject valve on October 9, 1987. This installation was controlled in accordance with the WCNOC ASME Section XI Repair and Replacement program. This included in process QC inspections and a VT-2 visual examination for leakage at nominal system pressure. These inspections were completed on December 28, 1987, with no adverse results.
During a completion review it was discovered that the required vendor documentation was not in the package for the new packing b o x .. Upon investigation by station personnel, it was discovered on March 17, 1988, that the ASME Code required documentation could not be provided and that only the Fisher Controls ' Manufacturers Certification" was available. The ANII determined that this package was deficient because it did not contain the ASME Code required documentation, specifically the Code Data Report, Material Test Reports and NDE reports. This nonconformance has been documented on Corrective Work Request No. 1285-88 REQUESTED RELIEF Article IVA-7210 of ASME Section XI states, in part, "Replacements shall meet the requirements of the edition of the Construction Code to which the original component or part was constructed ... '. Valve BB PCV 455B is an ASME Section III Clase 1 valve manufactured to the 1974 Edition through Summer 1975 Addenda (Subsection NB). In accordance with Fisher Controls drawing Number 54A0202 Rev. G, the packing box is required to be ASME Section III SA-182-F316 material. This is a forged product form with chemical and physical requirements as specified in SA-182-F316 and additional examination requirements as specified in Section III paragraphs NB-2510(b) and NB-2541.
Certified Material Test Reports, in accordance with paragraph NB-2130, and a Code Data Report (Form N-2) for welding performed on the part, in accordance with NA-3130(f), are required to be supplied.
Contrary to these requirements, WCNOC was provided two packing box assemblies as listed below:
- a. Packing box material has been determined to be ASTM A-276 type 316 SS bar instead of ASME SA-182-F316 forging.
- b. There was no NDE performed on the completed packing box assembly either volumetric or surface examination. The equipment specification for the Class 1 component required both types of inspection the ASME Code allows an MT or PT in lieu of volumetric for forged valves of up to four inches.
There was no surface non-destructive examination performed on the pipe nipple to packing box weld.
- c. Pipe nipple material utilized for the leakoff connection is not known to be in compliance with the material requirements (i.e., SA 312 TP 316).
Attschm:nt 2 to ET 88-0043 Page 3 of 7 March 22, 1988
- d. ASME Code N-2 Data Report for the packing box assembly was not
- supplied.
It should be noted that the code compliance issue is restricted only to the replacement packing box assembly. All other aspects of the valve are in compliance with applicable ASME Code requirements.
Because the packing box on this valve does not meet the ASME Section XI Code requirements as mentioned above. WCNOC is hereby requesting relief from the code pursuant to 10 CFR 50.55a(g)(6)(i) which states, 'The Commission will evaluate determinations under paragraph (g)(5) of this section that code requirements are impractical.'. Paragraph (g)(5)(lii) of 10 CFR 50.55a states, "If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit ... Information to support the determinations.'. On March 18, 1988 WCNOC notified the Commission, via telephone, of this situation due to the inability to replace the affected part during power operation. Information to support this determination is provided below.
BASIS FOR RELIEF Ouality Analysis Because packing box assemblies were intended to be ASME Code pressure boundary parts, they should have been classified and procured by Westinghouse as 'QA
! Code A.* Instead. Westinghouse incorrectly designated the procurement as 'QA Code D." This ultimately resulted in the incorrect parts being provided to WCNOC.
WCNOC has dispatched two Supplier Quality Representatives to Westinghouse to investigate this programmatic issue and ensure that adequate corrective actions are taken. This will include determination of extent of the problem, root cause analysis and appropriate remedial and preventative actions.
On March 19, 1988, a WCNOC Supplier Quality Representative was dispatched to i the Fisher Valve, Mansfield, Ohio facility. This is the non-nuclear facility that fabricated the replacement packing box assemblies. On-site investigation there has determined that both packing box assemblies received at Wolf Creek i
were fabricated from the same heat of Type 316 SS annealed material manufactured by Carpenter Technology Corporation. Discussions with Carpenter Technology on March 21, 1988, provided three additional pieces of information:
- 1) although not stated on the Carpenter CMTR, the material meets AST); A-276,
- 2) the 8 1/2' diameter round bar was made from a billet which was rotary forged and then rough turned and, 3) non-nuclear work is processed through the
! Carpenter facility in the same way as nuclear work, except for the retention of documentation. Further investigation at Fisher's Mansfield facility revealed the follcaing:
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- a. The replacement packing box assemblies were machined using the same i drawing used by Ficher's Marshalltown, Iowa, nuclear facility (original manufacturer of the nuclear valve), thereby providing interchangeability of the parts.
' Attachmznt 2 to ET 88-0043 Page 4 of 7 March 22, 1988
- b. Welding of the pipe nipple to the packing box was performed using welding procedures qualified by Fisher Marshalltown in accordance with ASME Section IX.
- c. Welding was performed by a welder who was originally qualified to ASME Section IX, but for whom reoufred documentation has not been kept to.show current compliance witt Section IX. Subsequent review of the welder's qualification test report also shows he was not specifically qualified for the diameter of pipe weld required for this work since he qualified on a larger diameter pipe.
On March 18, 1988, the second packing box assembly, which was in the WCNOC warehouse, was sent to METLAB Testing Laboratories in Tulsa, Oklahoma. METLAB is qualified by WCNOC to perform testing and analysis services. This packing box assembly was destructively tested by METLAB to determine conformance with ASME SA-182-F316. Chemical analysis, mechanical testing, and metalurgical analysis were performed on a section removed from the packing box assembly.
Since the material was thought to be bar stock instead of a forging, mechanical tests were performed parallel and transverse to the longitudinal axis of the original bar stock. Results of this testing and analysis are presented in the engineering evaluation section.
METLAB also performed chemical analysis of the pipe nipple welded to the packing box. The chemical analysis was in conformance with the ASME SA-312-TP316 required by the valve design drawing. Mechanical tests could not be performed due to the small diameter and thickness of the pipe.
On March 21, 1988, the installed valve was closed and allowed to cool down.
An ASME Section XI VT-1 visual examination was completed on March 22, 1988, and found acceptable and is being submitted as an alternative to the Section III required surface examination of the packing box and pipe nipple to packing box weld. In addition, an ultrasonic examination of the flange connecting the packing box to the valve body will be performed and will provide an additional alternative to the required surface examination.
< Engineerinn Evaluation The packing box contains the packing seal between the shaf t and packing box.
The connecting weld between the leakoff nipple and the packing box is required to be of Class 1 construction because of its connection to a Class 1 component. However, it is not a part of the pressure boundary of the valve.
Therefore, the lack of Code documentation and specific welder qualification is not a technical issue.
As noted in the Quality Analysis section, testing of the second packing box was performed at HETLAB. Chemical analysis and mechanical tests performed parallel and transverse to the longitudinal axis of the original bar stock l
indicate that the actual material properties of the two replacement packing 4 boxes, including the one currently in service, exceed the minimum specified
! mechanical properties and meets the specified chemical properties of
" Attachmint 2 to ET 88-0043 Page 5 of 7 March 22, 1988 SA-182 F316, with the exception of the transverse elongation (44 percent actual versus 45 percent minimum specified) which is deemed to be inconsequential. In addition, Charpy V-notch tests indicate a fracture toughness similar to that of the SA-182 material.
The metalurgical analysis of photomicrographs of the material indicated that it was difficult to determine if the material was a forging or a bar.
Although there was some indication of directionality, distinct grain orientation expected from a bar stock was not observed. (Distinct grain orientation parallel to the longitudinal axis of the bar may result in reduced strength of the material in a direction transverse to the longitudinal axis of the bar.) The metalurgical analysis therefore provided consistent results with the mechanical tests which were performed in the transverse direction.
As a result of the testing performed on this second packing box assembly, which was from the same heat and same piece of material as the packing box assembly installed in the plant, it is therefore expected that the installed packing box would be capable of functioning in a similar fashion to a part fabricated from a forged SA-182 F316 material.
The requirements for the installed part are similar to the requirements for the ASHE Coded part. The parts are interchangeable with respect to fit and function as presented in the Quality Analysis.
The packing box was designed to ANSI B16.34 for the pressure / temperature conditions applicable to this component. These are the sam 9 pressure / temperature requirements for Class 1 valves of four inches and below, as NB-3513 references B16.34 for pressure / temperature ratings.
Since the packing box was originally designed using the rules of ANSI B16.34, there was no specific stress analysis for the packing box. A conservative analysis to determine the stress levels present in the packing box has been performed in accordance with ASME III Subsection NB. The analytical techniques employed classical formulas of stress analysis. The stresses due to internal pressure were determined using formulas for a thickwalled cylinder subjected to internal pressure. Beam bending and torsion theory were used to calculate the stresses due to seismic and deadweight loads. The stresses resulting from the bolt preload were determined using formulas for bending of flat plates. The maximum primary plus secondary stress intensity at the hub to flange juncture due to these loads was determined to be acceptable to the allowable values for SA 182 F316 material.
In addition to the stress analyses, a fracture mechanics evaluation has been performed, using a conservatively selected fracture criterion. Appropriate loading conditions, such as normal operating and seismic, have been considered. Two aspects of the valve packing box were evaluated.
- 1. F: an estimated surface bending stress of 49,000 psi, an assumed f.aw 0.3 inches deep at the flange to packing box body juncture and completely around the flange was shown to be stable.
- 2. Circumferential through wall flaws were assumed to exist in the cylindrical portion of the valve packing box. Norms 1 operating loads
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' Attachment 2 to ET 88-0043 Page 6 of 7 March 22, 1988 were not sufficiently large to produce a calculable leak rate. Also, thin wall flaws up to 4 inches long were shown to be stable under combined pressure and seismic loadings.
The valve packing box has thus been shown to be stable under severely assumed flawed conditions. Significant margins against conservative cr?.teria have been demonstrated. The packing box should satisfy its service requirements without incident.
In addition to the above, an analyses on the packing box based on the procedures of ASME Section III Subsection NB and Appendix XI was performed.
The resulting stresses show that the Code stress requirements have been met.
In addition, Fisher Controls has also done a finite element analysis of the packing box which confirms that the stresses are acceptable.
Operations Evaluation Continued operation of WCGS with the incorrect packing box assembly for Valve
- BB PCV 455B poses no inordinate hazards to plant operation. Valve BB PCV 455C is still available for normal pressurizer spray flow as needed and to aid in the event of a steam generator tube rupture.
Were the part to fail in such a manner as to induce a Reactor Coolant System leak, the symptoms would be that of a vapor space break, i.e., the RCS pressure would lower, the pressurizer level would increase, and the levels on the particulate, gaseous, and iodine monitors in the containment atmosphere would increase. In an earlier pressurizer spray bypass valve packing leak, i the containment monitors were a very good indicator of the problem. A lowering RCS pressure would ultimately trip the plant at pressurizer pressure equal to 1875 psig with a further safety injection (SI) and reactor trip at
! 1830 psig. The operator would proceed to Plant Emergency Procedure E-02 for either cases and would follow the procedure to "reactor trip response' if pressure stabilized, or would go on to the proper Loss of Coolant procedure E-1 as a result of an SI. If the pressure did not stabilize, the SI could not be terminated, as one of the criterion for reset is RCS pressure stable or increasing. Along with the cr.iteria is the need for subcooling to be maintained. Either one or both of these would override the increasing pressurizer level because all criteria must be met to terminate an SI, not just inventory.
If the valve itself failed open, the reactor would trip on low pressure or at the safety injection setpoint. In any case, the reactor would be tripped so the affected RCP (PBB01A) could be turned off. At powers less than 48 percent, the affected Reactor Coolant Pump would be tripped with orderly shutdown to HOT STANDBY as required by Technical Specification 3.4.1.
A preliminary safety assessment of the effect of a catastrophic failure of the pressurizer spray valve packing box was performed. The complete failure of the packing box represents a small break LOCA with fluid discharge reaching the break from the pressurizer and the cold leg. Although this scenario is not analyzed in the WCNOC USAR, analyses using the NOTRUMP small break LOCA ECCS Evaluation Model indicates that this event is bounded by a small break LOCA in the cold leg. Westinghouse and the Westinghouse Ownar's Groups examined a scenario similar to this using the current Westinghouse small break LOCA ECCS Evaluation Model incorporating the NOTRUMP analysis methodology in
Attachmtnt 2 to ET 88-0043 Page 7 of 7 MLrch 22, 1988 WCAP-10054. Analyses of a plant similar in design to Wolf Creek and using the NOTRUMP small break LOCA ECCS Evaluation Model show that the reactor core is not expected to be uncovered in the unlikely event that there is a catastrophic failure of the pressurizer spray flow control valve packing box.
For non-LOCA events, normal reactor control system and engineered safety systems are not required to function in 'the ultimate mitigation of the consequences from accidents. However, in the analysis of the Chapter 15 events, control system action is considered if that action results in more severe consequences. For some events, the analysis is performed both with and without control system operation to determine the worst case.
The Turbine Trip event is analyzed with and without pressurizer spray actuation. The consequences are acceptable without pressurizer spray. All other events are not impacted by not having pressurizer spray available.
CONCLUSION Based upon the above information, WCNOC considers the use of the packing box currently installed on the Pressurizer Spray Valve BB PCV 455B to be acceptable and continued operation is justified. In order to be assured that the valve does not degrade, a peric';c visual inspection will be performed until the packing box assembly is replaced. The replacement of the packing box will be performed during the next outage of sufficient duration and appropriate plant conditions. In any case, this assembly will be replaced no later than the next refueling outage.
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