Letter Sequence Approval |
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MONTHYEARML20127J5681985-06-14014 June 1985 Forwards Safety Evaluation Approving New Small Break LOCA Model Notrump for TMI Item II.K.3.30,per WCAP-10079 & WCAP-10054.Plant-specific Analysis Due within 1 Yr,Per Item II.K.3.31,if Notrump Used in LOCA Small Break Analysis Project stage: Approval ML20211K6981986-06-26026 June 1986 Informs That WCAP-11145 Will Be Ref in plant-specific Analysis in Order to Satisfy Requirements of Action Item Ii.K 3.31,per Generic Ltr 83-35 Project stage: Other ML20214A3871986-11-17017 November 1986 Forwards Reactor Sys Branch Supplemental Safety Evaluation Supporting Util 860629 Submittal.Fsar Analysis of Small Break LOCA Conservative in Comparison W/Notrump Model & Satisfies NUREG-0737,Item II.K.3.31 & 10CFR50.46 Project stage: Approval 1986-11-17
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Category:CORRESPONDENCE-LETTERS
MONTHYEAR05000482/LER-1999-002, Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl 05000482/LER-1994-014, Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl1999-10-15015 October 1999 Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl ML20217F7481999-10-14014 October 1999 Informs That Based on Approval of Core Assessment Damage Guidance in WCAP-14696,rev 1 for Westinghouse Nuclear Power Plants,Licensee May Use WCAP-14696,rev 1 at Wolf Creek Generating Station ML20217F8701999-10-13013 October 1999 Provides Summary of Meeting on 991007 with Representatives of Wolf Creek Nuclear Station in Burlington,Kansas Re Status of Licensee Radiation Protection Program.List of Meeting Attendees & Licensee Presentation Encl ML20217C1721999-10-0707 October 1999 Forwards Insp Rept 50-482/99-09 on 990830-0903.No Violations Noted.Purpose of Insp to Perform Routine Operational Status Insp of Emergency Preparedness Program & to Resolve Questions Re Revised Emergency Plan ML20217A4881999-09-29029 September 1999 Forwards Changes to Plant Data Point Library,Iaw 10CFR50,App E,Section VI.3.a.ERDS Point Affected Is RDS0001 ML20216H9291999-09-29029 September 1999 Informs That Licensee Responses to GL 97-06, Degradation of Steam Generator Internals Acceptable & Did Not Identify Any New Concerns with Condition of SG Intervals at Plant ML20212G1681999-09-24024 September 1999 Notifies NRC of Change in Status of Licensed Individual at Plant,Per 10CFR50.74.RL Acree Holds License OP-42654 at Plant,But Has Been Permanently Reassigned from Position for Which Plant Has Certified Need for RO License ML20216F9591999-09-22022 September 1999 Forwards Withdrawal of Amend Request Re Ultimate Heat Sink Temp for Wolf Creek Generating Station ML20212G5641999-09-20020 September 1999 Forwards Insp Rept 50-482/99-13 on 990725-0904.Three Violations Being Treated as Noncited Violations 05000482/LER-1999-011, Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I1999-09-17017 September 1999 Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I 05000482/LER-1999-010, Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util1999-09-16016 September 1999 Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util ML20212D9381999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of WCGS on 990818.Areas of EP & Engineering Warranted Increase in NRC Action.Nrc Plan to Conduct Add Insp Beyond Core Insp Program Over Next 7 Months to Address Listed Questions 05000482/LER-1999-006, Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl1999-09-15015 September 1999 Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl ML20212C9211999-09-15015 September 1999 Forwards NRC Form 536, Operating Licensing Examination Data, in Response to NRC Administrative Ltr 99-03 ML20216F1641999-09-14014 September 1999 Forwards Insp Rept 50-482/99-12 on 990816-20.No Violation Noted.Determined That Solid Radwaste Mgt & Radioactive Matls Transportation Programs Were Properly Implemented 05000482/LER-1999-009, Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER1999-09-10010 September 1999 Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER ML20212A5651999-09-10010 September 1999 Informs of Completion of Review of & Encl Objectives for Wolf Creek Generating Station 1999 Emergency Preparedness Exercise Scheduled for 991117.Determined Exercise Objectives Appropriate to Meet EP Requirements 05000482/LER-1999-008, Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER1999-09-0303 September 1999 Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER ML20211M7151999-09-0303 September 1999 Forwards Changes to Wolf Creek Generating Station Data Point Library.Emergency Response Data Sys Points Affected Are EJL0007 & EJL0008 ML20211N0081999-09-0202 September 1999 Informs That NRC Staff Has Reviewed Submittals & Concluded Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20211K8301999-09-0202 September 1999 Forwards marked-up TS Page Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band,Per 990708 Application to Amend License NPF-42 ML20211K1941999-08-31031 August 1999 Forwards Rev 31 to WCGS Physical Security Plan,Safeguards Contingency Plan & Training & Qualification Plan,Iaw 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20211H1491999-08-26026 August 1999 Forwards Insp Rept 50-482/99-16 on 990809-13.No Violations Noted.Insp Focused on Low as Is Reasonably Achievable Program,Training Program for Contract Radiation Protection Personnel & Radiation Protection QA Program ML20211A8581999-08-18018 August 1999 Forwards Insp Rept 50-482/99-08 on 990316-0724.One Violation Being Treated as Noncited Violation ML20211G2201999-08-17017 August 1999 Forwards Exam Rept 50-482/99-301 on 990726-29.Exam Evaluated Six Applicants for SO Licenses & Three Applicants for RO Licenses ML20210U0991999-08-13013 August 1999 Forwards Insp Rept 50-482/99-11 on 990712-16.No Violations Noted.Insp Was to Review Radiological Environ Monitoring Program ML20210U9751999-08-13013 August 1999 Informs That Licensee Identified That Answer Key for One Question on 990720 Written Exam & Event Classification for on Job Performance Measure Required Mod.Description & Justification for Proposed Mod,Including Technical Ref,Encl ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210R5621999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Revised Repts for Apr,May & June 1999,correcting Number of Hours Reactor Critical,Encl ML20210P7491999-08-0909 August 1999 Ack Receipt of ,Which Transmitted Wolf Creek Radiological Emergency Response Plan 06-002,Rev 0,under Provisions of 10CFR50,App E,Section V ML20210N0061999-08-0303 August 1999 Forwards Response to NRC 990401 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Motor-Operated Gate Valves ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210H2551999-07-29029 July 1999 Provides 180-day Response to NRC Request for Info Re GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210J1371999-07-29029 July 1999 Requests NRC Approval of Methodology for Determining RCS Pressure & Temp & Overpressure Mitigation Sys PORV Limits. Attachment I Provides Proposed Changes to Improved TS ML20210F5931999-07-27027 July 1999 Forwards semi-annual Fitness for Duty Performance Data Rept for Wcnoc,Per 10CFR26.71(d).Rept Covers Period of 990101- 0630 ML20210F5881999-07-23023 July 1999 Submits Response to Administrative Ltr 99-02, Operator Reactor Licensing Action Estimates, ML20210B8191999-07-20020 July 1999 Ack Receipt of ,Which Transmitted Wolf Creek EP Implementing Procedure 06-005,Rev 1.Implementation of Changes Will Be Subj to Insp to Confirm That Changes Does Not Decrease Effectiveness of EP ML20209H5411999-07-15015 July 1999 Forwards Insp Rept 50-482/99-07 on 990614-18.No Violations Noted.Insp Focused on Radiation Program During Normal Operating Conditions ML20209H0441999-07-14014 July 1999 Forwards Response to NRC 990326 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. Summary of Util Commitments Provided in Attachment 2 ML20209H0751999-07-14014 July 1999 Forwards Monthly Operating Rept for June 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Max Dependable Capacity Has Been Updated from 1163 to 1170,as Determined by Calculations Based on Capacity Test Results of July 1998 ML20209G9871999-07-14014 July 1999 Informs of Changes Affecting Wolf Creek Security Plan,Per 10CFR50.54(p)(2).Encl Provides Description of Changes & Justification for Changes ML20209E3581999-07-12012 July 1999 Discusses Util 980925 Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Wolf Creek Generating Station ML20209E0611999-07-0808 July 1999 Forwards Addl Pages to Rev 12 of USAR & Commitment Changes, Inadvertently Omitted from 990311 Submittal ML20196K8231999-07-0606 July 1999 Submits Kansas Electric Power Cooperative,Inc Ltr Pursuant to Commission Direction in Memo & Order CLI-99-19.Addresses Disposition of Existing Antitrust Conditions Attached to License for Wolf Creek Unit 1 Re Proposed License Transfer ML20209C6031999-07-0606 July 1999 Provides Applicants View as Result of 990618 Memo & Order Directing Parties to Address Proper Disposition of Existing Antitrust License Condition Attached to OL for Facility Due to Planned Changes in Ownership of Facility.With Svc List ML20196K0501999-07-0202 July 1999 Forwards Insp Rept 50-482/99-06 on 990502-0612.Three Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20209B7131999-07-0101 July 1999 Submits Response to NRC Request for Info Re GL 98-01, Suppl 1, Y2K Readiness of Computer Sys at Npps. Response on Status of Facility Y2K Readiness Was Requested by 990701.Disclosure Encl ML20209A7461999-06-29029 June 1999 Informs of Changes in Project Mgt Staff Assigned to Wcgs. Effective 990628,J Donohew Will Assume PM Responsibilities ML20209B5151999-06-29029 June 1999 Informs That Util Completed Analyses & Modifications to Address Items Discussed in GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions 1999-09-03
[Table view] Category:NRC TO UTILITY
MONTHYEARIR 05000482/19900261990-11-14014 November 1990 Ack Receipt of Responding to NRC Requesting Addl Info Concerning 900731 Notice of Violation from Insp Rept 50-482/90-26 IR 05000482/19900341990-11-0909 November 1990 Forwards Notice of Violation Re Insp Rept 50-482/90-34 & Summary of Enforcement Conference on 901106 ML20058D7601990-11-0101 November 1990 Forwards Summary of Staff Understanding of Current Status Re GSIs Remaining Unimplemented at Facility,Per GL-90-04 ML20058E1391990-10-26026 October 1990 Forwards Final SALP Rept 50-482/90-14 on 900401-0630 ML20058B2831990-10-23023 October 1990 Forwards Insp Rept 50-482/90-34 on 900926-1005.Violations Noted ML20062C9971990-10-19019 October 1990 Forwards Insp Rept 50-482/90-31 on 900801-0914 & Notice of Violation ML20058A3621990-10-18018 October 1990 Advises That Util 900925 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2, Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20059P0671990-10-15015 October 1990 Ack Receipt of Requesting Withdrawal of Request for Relief Re Procurement of ASME Section III Matls ML20062B3081990-10-0505 October 1990 Forwards Insp Rept 50-482/90-30 on 900730-0810.Violations Noted But Not Cited.Four Open Items Identified ML20059N3091990-10-0101 October 1990 Forwards Insp Rept 50-482/90-28 on 900701-31 & Notice of Violation ML20059M6851990-09-28028 September 1990 Ack Receipt of 900830 Response to Violations Noted in Insp Rept 50-482/90-26.Addl Info Re Troubleshooting Required ML20059M0451990-09-27027 September 1990 Requests Addl Info Re Seismic Design Consideration for safety-related Vertical Steel Tanks.Info Needed within 90 Days Following Receipt of Ltr ML20059J3541990-09-11011 September 1990 Forwards Initial SALP Rept 50-482/90-14 for Apr 1989 - June 1990.Areas of Operations,Radiological Controls,Maint/ Surveillance & Engineering/Technical Support Rated Category 2,while Area of Security & Emergency Remained Category 1 ML20059C4171990-08-23023 August 1990 Accepts Util 890531 Response to NRC Bulletin 88-011 Re Surge Line Stratifiction.Nrc Topical Rept Evaluation Encl ML20059A7431990-08-14014 August 1990 Ack 900808 Visit to Region IV & Info Re Status of Actions on Recent Kansas City Power & Light Co Offer to Purchase Kansas Gas & Electric Co.Util Assurance That Offer to Purchase Will Have No Effect on Safety Operations of Importance to NRC ML20058P2581990-08-14014 August 1990 Ack Receipt of Transmitting Scenario for Upcoming Annual Exercise.Nrc Understands That Util Taking Actions to Resolve Concerns Expressed in FEMA 900727 Memo ML20058P2421990-08-13013 August 1990 Forwards Insp Rept 50-482/90-23 on 900507-11 & 0629-0703 & Notice of Violation.No Response to Violation Required Due to Corrective Action Implemented Prior to Inspectors Departure IR 05000482/19900241990-08-0606 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-24.Responses to Training Violation & Unresolved Item Re Min Protective Action Recommendations Responsive to Insp Rept Concerns ML20055J4891990-07-31031 July 1990 Advises That NRC Form 474, Simulation Facility Certification, Submitted on 900110,complete & Requires No Further Info.Simulation Facility Acceptable for Purposes of 10CFR55.31(a)(4) Based on Certification of Facility ML20055J4881990-07-31031 July 1990 Discusses Util 891226 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20056A2851990-07-31031 July 1990 Forwards Insp Rept 50-482/90-26 on 900601-30 & Notice of Violation.Violation Re Failure to Update Info Into Updated FSAR Noted But Not Cited ML20056A1731990-07-30030 July 1990 Advises That Requalification Program Evaluation Scheduled at Plant Site During Wks of 901022 & 29.Util Requested to Furnish Approved Items Listed in Encl 1.Failure to Supply Ref Matl May Result in Postponement of Exam ML20058L3311990-07-27027 July 1990 Summarizes 900724 Meeting W/Util in Region IV Ofc Re Changes to Operator Licensing Program.Meeting Agenda,Attendance List & Viewgraphs Encl ML20055J3971990-07-24024 July 1990 Requests Addl Info Re Steam Generator Tube Rupture Operator Action Times for Plant.Response Requested within 30 Days of Receipt of Ltr IR 05000482/19900171990-07-19019 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-17 ML20059N8021990-07-10010 July 1990 Ack Receipt of Transmitting Objective & Guidelines for Upcoming Emergency Preparedness Exercise. Util Exercise Scenario,Submitted on 900628,currently Under Review ML20055F6251990-07-0909 July 1990 Forwards Summary of 900626 Meeting W/Util in Region IV Ofc Re Licensee Performance During Latest Refueling Outage. Attendance List Encl ML20055D9881990-07-0505 July 1990 Forwards Insp Rept 50-482/90-25 on 900611-15.No Violations or Deviations Noted.One Unresolved Item Noted ML20055D9531990-07-0505 July 1990 Forwards Insp Rept 50-482/90-22 on 900501-31.Noncited Violation Noted.One Unresolved Item Identified IR 05000482/19900051990-07-0505 July 1990 Ack Receipt of 900629 & 0413 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-05 ML20058K3611990-06-26026 June 1990 Forwards Insp Rept 50-482/90-24 on 900514-18 & Notice of Violation.Unresolved Items Noted Re Discrepancy Between Emergency Plan & Emergency Plan Implementing Procedures Re Min Protective Action Recommendations During Emergency IR 05000482/19900161990-06-26026 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-16 ML20055C7671990-06-18018 June 1990 Forwards Insp Rept 50-482/90-27 on 900604-08.No Violations or Deviations Noted ML20059M9091990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248C6401989-09-27027 September 1989 Forwards Insp Rept 50-482/89-25 on 890911-25.No Violations Noted or Deviations Identified ML20248E7801989-09-21021 September 1989 Forwards Amend 4 to Indemnity Agreement B-99.Amend Increases Primary Nuclear Energy Liability Insurance.Util Requested to Submit Signed Amend to Signify Acceptance ML20247N1671989-09-20020 September 1989 Forwards Safety Evaluation Re Plant First 10-yr Inservice Testing Program & Requests for Relief Re Reclassification of 16 Valves from Passive to Active & Clarification of Cold Shutdown Justification ML20247M9531989-09-19019 September 1989 Forwards Insp Rept 50-482/89-22 on 890828-0901.No Violations Noted ML20247K0501989-09-14014 September 1989 Forwards Insp Rept 50-482/89-23 on 890801-31.No Citation for Violation Described in Paragraph 3 Issued,Per Section V.G.1 of NRC Enforcement Policy IR 05000482/19890051989-09-0606 September 1989 Ack Receipt of 890531 & 0831 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/89-05 ML20247B1931989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executives Meeting on 890818 in Arlington,Tx.Topics Discussed Included, Improving Communications,Salp Process in Region IV & Enforcement.List of Attendees & Agenda Encl ML20246F9131989-08-21021 August 1989 Forwards Request for Addl Info Re 880620 Proposed Revs to Tech Specs 3/4.4.9.1 & 3/4.4 9.3, RCS Pressure/Temp Limits & Overpressure Protection Sys, Respectively ML20246D6441989-08-17017 August 1989 Informs That Request to Withdraw Application for Amend to License NPF-42 Granted ML20245J6031989-08-14014 August 1989 Advises That Licensing Exams Scheduled for Wk of 891120.Ref Matl Listed on Encl Should Be Provided by 890920. Procedures for Administration of Written Exams Also Encl ML20245H2921989-08-0808 August 1989 Forwards Insp Rept 50-482/89-21 on 890701-31.No Violations or Deviations Noted ML20248A2171989-07-31031 July 1989 Forwards Summary of 890623 Meeting at Facility to Discuss SALP for Apr 1988 - Mar 1989 & Util 890721 Response to SALP Rept.Viewgraphs Also Encl ML20247N7251989-07-31031 July 1989 Concurs That Requirements of License Condition 2.C.(7), Attachment 3,Item (2) Re Emergency Response Capabilities Have Been Met,Based on Review of Util & on Past Emergency Preparedness Insps 1990-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F7481999-10-14014 October 1999 Informs That Based on Approval of Core Assessment Damage Guidance in WCAP-14696,rev 1 for Westinghouse Nuclear Power Plants,Licensee May Use WCAP-14696,rev 1 at Wolf Creek Generating Station ML20217F8701999-10-13013 October 1999 Provides Summary of Meeting on 991007 with Representatives of Wolf Creek Nuclear Station in Burlington,Kansas Re Status of Licensee Radiation Protection Program.List of Meeting Attendees & Licensee Presentation Encl ML20217C1721999-10-0707 October 1999 Forwards Insp Rept 50-482/99-09 on 990830-0903.No Violations Noted.Purpose of Insp to Perform Routine Operational Status Insp of Emergency Preparedness Program & to Resolve Questions Re Revised Emergency Plan ML20216H9291999-09-29029 September 1999 Informs That Licensee Responses to GL 97-06, Degradation of Steam Generator Internals Acceptable & Did Not Identify Any New Concerns with Condition of SG Intervals at Plant ML20216F9591999-09-22022 September 1999 Forwards Withdrawal of Amend Request Re Ultimate Heat Sink Temp for Wolf Creek Generating Station ML20212G5641999-09-20020 September 1999 Forwards Insp Rept 50-482/99-13 on 990725-0904.Three Violations Being Treated as Noncited Violations ML20212D9381999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of WCGS on 990818.Areas of EP & Engineering Warranted Increase in NRC Action.Nrc Plan to Conduct Add Insp Beyond Core Insp Program Over Next 7 Months to Address Listed Questions ML20216F1641999-09-14014 September 1999 Forwards Insp Rept 50-482/99-12 on 990816-20.No Violation Noted.Determined That Solid Radwaste Mgt & Radioactive Matls Transportation Programs Were Properly Implemented ML20212A5651999-09-10010 September 1999 Informs of Completion of Review of & Encl Objectives for Wolf Creek Generating Station 1999 Emergency Preparedness Exercise Scheduled for 991117.Determined Exercise Objectives Appropriate to Meet EP Requirements ML20211N0081999-09-0202 September 1999 Informs That NRC Staff Has Reviewed Submittals & Concluded Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20211H1491999-08-26026 August 1999 Forwards Insp Rept 50-482/99-16 on 990809-13.No Violations Noted.Insp Focused on Low as Is Reasonably Achievable Program,Training Program for Contract Radiation Protection Personnel & Radiation Protection QA Program ML20211A8581999-08-18018 August 1999 Forwards Insp Rept 50-482/99-08 on 990316-0724.One Violation Being Treated as Noncited Violation ML20211G2201999-08-17017 August 1999 Forwards Exam Rept 50-482/99-301 on 990726-29.Exam Evaluated Six Applicants for SO Licenses & Three Applicants for RO Licenses ML20210U0991999-08-13013 August 1999 Forwards Insp Rept 50-482/99-11 on 990712-16.No Violations Noted.Insp Was to Review Radiological Environ Monitoring Program ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210P7491999-08-0909 August 1999 Ack Receipt of ,Which Transmitted Wolf Creek Radiological Emergency Response Plan 06-002,Rev 0,under Provisions of 10CFR50,App E,Section V ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210B8191999-07-20020 July 1999 Ack Receipt of ,Which Transmitted Wolf Creek EP Implementing Procedure 06-005,Rev 1.Implementation of Changes Will Be Subj to Insp to Confirm That Changes Does Not Decrease Effectiveness of EP ML20209H5411999-07-15015 July 1999 Forwards Insp Rept 50-482/99-07 on 990614-18.No Violations Noted.Insp Focused on Radiation Program During Normal Operating Conditions ML20209E3581999-07-12012 July 1999 Discusses Util 980925 Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Wolf Creek Generating Station ML20196K0501999-07-0202 July 1999 Forwards Insp Rept 50-482/99-06 on 990502-0612.Three Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20209A7461999-06-29029 June 1999 Informs of Changes in Project Mgt Staff Assigned to Wcgs. Effective 990628,J Donohew Will Assume PM Responsibilities ML20195G3451999-06-0909 June 1999 Ack Receipt of Ltr Dtd 990105,which Transmitted Wolf Creek Emergency Plan Form Apf 06-002-01 Emergency Action Levels, Rev 0,dtd 990105,under Provisions of 10CFR50,App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20195D5111999-06-0202 June 1999 Forwards Safety Evaluation Authorizing Inservice Inspection Program Alternative for Limited Reactor Vessel Shell Weld Exam & Relief Request from Requirements of ASME Code,Section XI for Wolf Creek Generating Station ML20207E2791999-05-25025 May 1999 Announces Corrective Action Program Insp at Wolf Creek Reactor Facility,Scheduled for 990816-20.Insp Will Evaluate Effectiveness of Activities for Identifying,Resolving & Preventing Issues That Degrade Quality of Plant Operations ML20207A8681999-05-25025 May 1999 Informs That NRC Ofc of NRR Reorganized Effective 990328. as Part of Reorganization,Division of Licensing Project Mgt Created ML20207A3491999-05-21021 May 1999 Forwards Insp Rept 50-482/99-03 on 990321-0501.Four NCVs Noted ML20206H3901999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamentals Exam Section of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However Copy of Master Exam with Answer Key Encl for Info.Without Encl ML20206H5941999-05-0505 May 1999 Forwards Insp Rept 50-482/99-04 on 990405-09.No Violations Noted.Scope of Inspection Included Review of Implementation of Licensee Inservice Insp Program for Wolf Creek Facility Refueling Outage 10 ML20206H2891999-04-30030 April 1999 Forwards Exemption from Requirements of 10CFR50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation, for Wcgs.Exemption Related to Application ML20205L8541999-04-0909 April 1999 Forwards Insp Rept 50-482/99-02 on 990207-0320.Five Violations Identified & Being Treated as Noncited Violations ML20205J3371999-04-0606 April 1999 Forwards Request for Addl Info Re Wolf Creek Generating Station IPEEE & 971208 Response to RAI from NRC Re Ipeee. RAI & Schedule for Response Were Discussed with T Harris on 990405 ML20205K4451999-04-0303 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/98-05 & of Need for Larger Scope of Review for Planned C/As for Violation 50-482/98-05,which Requires Extending Completion Time ML20205H7091999-04-0202 April 1999 Discusses 990325 Meeting at Plant in Burlington,Ks to Discuss Results of PPR Completed on 990211 ML20205G5851999-04-0101 April 1999 Forwards RAI Re Licensee 960214 Submittal of 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant. Response Requested within 120 Days of Receipt of Ltr ML20205C2101999-03-26026 March 1999 Informs That NRC Staff Reviewed WCNOC 960918,970317 & 980429 Responses to GL 96-05, Periodic Verification of Design- Basis Capability of Safety-Related Movs. Forwards RAI Re MOV Program Implemented at Wolf Creek Generating Station ML20204H7571999-03-23023 March 1999 Discusses WCNOC 990202 Proposed Rev to Response to GL 81-07, Control of Heavy Loads, for Wcgs.Rev Would Make Reactor Building Analyses Consistent with TS & Change Commitment Not to Allow Polar Crane Hook Over Open Rv.Revs Approved ML20205A4221999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from Wolf Creek Plant Performance Review for Period 980419-990125. Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl ML20207L5941999-03-0404 March 1999 Informs That Staff Accepts Util 981210 Requested Approval for Use of ASME Code,Section III Code Case N-611, Use of Stress Limits as Alternative to Pressure Limits,Section III, Div 1,Subsection NC/ND-3500, for Certain Valve Components ML20207F3121999-03-0303 March 1999 Informs That Info Provided in Entitled, Addl Info Requested for Topics Discussed During Oct 14-15 Meeting, from Wcnoc,Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20207F4491999-03-0303 March 1999 Forwards Signed Copy of Updated Computer Access & Operating Agreement Between NRC & Wcnoc,Per ML20207F0411999-02-26026 February 1999 Informs That KM Thomas Will Resume Project Mgt Responsibilities for Wcngs,Effective 990301 ML20206U6131999-02-0202 February 1999 Forwards Draft SER on Proposed Conversion of Current TSs for Wolf Creek Generating Station to Improved Tss.Encl Draft SER Being Provided for Review to Verify Accuracy & to Prepare Certified Improved TSs ML20202B7391999-01-26026 January 1999 Forwards Insp Rept 50-482/99-01 on 990111-14.No Violations Noted.Nrc Understands That During 990114 Exit Meeting,Vice President,Operations/Chief Operating Officer Stated That Util Would Revise Security Plan ML20199H4671999-01-15015 January 1999 Forwards Insp Rept 50-482/98-20 on 981115-1226.No Violations Noted.Conduct at Wolf Creek Generally Characterized by safety-conscious Operations & Sound Maintenance Activities ML20199B0591999-01-11011 January 1999 Forwards Y2K Readiness Audit Rept for Wolf Creek Nuclear Generating Station.Purpose of Audit Was to Assess Effectiveness of Wolf Creek Nuclear Operating Corp Programs for Achieving Y2K Readiness ML20199A0991998-12-29029 December 1998 Informs That on 981202,NRC Staff Completed Insp Planning Review (Ipr) of WCGS & Advises of Planned Insp Effort Resulting from Ipr.Forwards Historical Listing of Plant Issues,Referred to Plant Issues Matrix IR 05000482/19980121998-12-18018 December 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/98-12.NRC Have Withdrawn Violation 50-482/98-12-02 for First Example Re Procedure AP 05-0001 ML20198B2701998-12-16016 December 1998 Informs That Staff Has Incorporated Rev of Bases for TS 3/4.7.1.2, Afs Into WCGS Tss,Per 981108 Request.Rev Specifies Essential SWS Requirements for turbine-driven Afs. Overleaf Pages Provided to Maintain Document Completeness ML20196K0321998-12-0808 December 1998 Informs That Staff Has Incorporated Rev of Bases for TS 3/4.4.4, Relief Valves, Requested by .Rev Clarifies Bases to Be Consistent with Amend 63 to Wolf Creek TSs .Rev Acceptable.Bases Page Encl 1999-09-29
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. y JUN 141985 Docket No.: STN 50-482 Mr. Glenn L. Koester Vice President - Nuclear Kansas Gas and Electric Company 201 North Market Street P. O. Box 208 Wichita, Kansas 67201
Dear Mr. Glen L. Koester:
On May 21 1985, the NRC approved the new Westinghouse small break LOCA model, NOTRUMP, for use in satisfying the TMI Action Item II.K.3.30. The Westinghouse model was documented in the two Topical Reports, WCAP-10079 and WCAP-10054. The Westinghouse Owners Group (WOG) references NOTRUMP as the:f r new licensing small break LOCA model to satisfy the requirements of TMI Action Item II.K.3.30. Our Safety Evaluation of II.K.3.30 for the members of WOG is enclosed.
It is our understanding that you are a member of the WOG and that NOTRUMP is to be used in the small break LOCA analysis for the Wolf Creek Generating Station. If this is correct, this completes the TMI Action Item II.K.3.30 for your plant and in accordance with the TMI Action Item II.K.3.31, your plant specific analysis is due within one year of receipt of this letter.
Please advise this office within 60 days if this is not correct and provide your plans and schedule for completing II.K.3.30 and II.K.3.31.
On November 2,1983 in Generic Letter No. 83-35, the NRC provided clarifica-tion and proposed a generic resolution of TMI Action Item II.K.3.31. That is, resolution of II.K.3.31 may be accomplished by generic analysis to demonstrate that the previous analyses performed with WFLASH were conservative. Future plant specific analysis performed for your plant by Westinghouse for reloads or Technical Specification amendments (those beyond 90 days of the date of this letter) should be calculated with the new code, NOTRUMP.
Sincerely, B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing
Enclosure:
As stated cc: See next page DISTRIBUTION:
Ipoetet File . MRushbrook EJordan P0'Connor DWigginton NRC PDR~
Local PDR OELD PRC System ACRS (16)
NSIC JPartlow LB#1 R/F BGrimes LB#1/DL M LB#
P0'Connor/mac BJYi 1 lood 06/p/85 06/ .
8506260694 850614 PDR ADOCK 0500 2
%, UNITED STATES y,8 p, NUCLEAR REGULATORY COMMISSION D j WASHINGTON, D. C. 20555
%, . . . . . .o# JUN 14 25 Docket No.: STN 50-482 Mr. Glenn L. Koester Vice President - Nuclear Kansas Gas and Electric Company 201 North Market Street P. O. Box 208 Wichita, Kansas 67201
Dear Mr. Glen L. Koester:
On May 21 1985, the NRC approved the new Westinghouse small break LOCA model, NOTRUMP, for use in satisfying the TMI Action Item II.K.3.30. The Westinghouse model was documented in the two Topical Reports, WCAP-10079 and WCAP-10054. The Westinghouse Owners Group (WOG) references NOTRUMP as their new licensing small break LOCA model to satisfy the requirements of TMI Action Item II.K.3.30. Our Safety Evaluation of II.K.3.30 for the members of WOG is enclosed.
It is our understanding that you are a member of the WOG and that NOTRUMP is to be used in the small break LOCA analysis for the Wolf Creek Generating Station. If this is correct, this completes the TMI Action Item II.K.3.30 for your plant and in accordance with the TMI Action Item II.K.3.31, your plant specific analysis is due within one year of receipt of this letter.
Please advise this office within 60 days if thie is not correct and provide your plans and schedule for completing II.K.3.5; and II.K.3.31.
On November 2,1983 in Generic Letter No. 83-35, the NRC provided clarifica-tion and proposed a generic resolution of TMI Action Item II.K.3.31. That is, resolution of II.K.3.31 may be accomplished by generic analysis to demonstrate that the previous analyses performed with WFLASH were conservative. Future plant specific analysis performed for your plant by Westinghouse for reloads or Technical Specification amendments (those beyond 90 days of the date of this letter) should be calculated with the new code, NOTRUMP.
Sinc e y, l i
~, /
- 3. J. oungbl od, Chief Life ing Br nch No. 1 Di' vision of Licensing
Enclosure:
As stated cc: See next page
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JUN 141985 WOLF CREEK Mr. Glenn L. Koester Vice President - Nuclear Kansas Gas and Electric Company 201 North Market Street Post Office Box 208 Wichita, Kansas 67201 cc: Mr. Nicholas A. Petrick Ms. Wanda Christy Executive Director, SNUPPS 515 N. 1st Street 5 Choke Cherry Road Burlington, Kansas Rockville, Maryland 20850 l C. Edward Peterson, Esq.
Jay Silberg, Esq. Legal Division Shaw, Pittman, Potts & Trowbridge Kansas Corporation Commission 1800 M Street, N. W. State Office Building, Fourth Floor Washington, D. C. 20036 Topeka, Kansas 66612 Mr. Donald T. McPhee John M. Simpson, Esq.
l Vice President - Production Attorney for Intervenors l Kansas City Power & Light Company 4350 Johnson Drive, Suite 120 l 1330 Baltimore Avenue Shawnee Mission, Kansas 66205 l Kansas City, Missouri 64141 l Regional Administrator l Ms. Mary Ellen Salava U. S. NRC, Region IV Route 1, Box 56 611 Ryan Plaza j Burlington, Kansas 66839 Suite 1000
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Arlington, Texas 76011 A. Scott Cauger Assistant General Counsel Mr. Allan Mee Public Service Commission Project Coordinator P. O. Box 360 Kansas Electric Power Cooperative, Inc.
Jefferson City, Missouri 65101 Post Office Box 4877 Gage Center Station Mr. Howard Bundy Topeka, Kansas 66604 Resident Inspector / Wolf Creek NPS c/o U.S.N.R.C Regional Administrator Post Office Box 311 U.S.N.R.C. - Region III Burlington, Kansas 66839 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Robert M. Fillmore State Corporation Commission Brian P. Cassidy, Regional Counsel State of Kansas Federal Emergency Management Agency Fourth Floor, State Office Bldg. Region I Topeka, Kansas 66612 J. W. McCormack POCH Boston, Massachusetts 02109
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WOLF CREEK cc: Terri Sculley, Director Special Projects Division Kansas Corporation Commission State Office Building, Fourth Floor Topeka, Kansas 66612 Mr. Gerald Allen Public Health Physicist Bureau of Air Quality & Radiation Control Division of Environment Kansas Dept. of Health & Environment Forbes Field Bldg. 321 Topeka, Kansas 66620 Mr. Bruce Bartlett Resident Inspector / Wolf Creek NPS c/o U.S.N.R.C Post Office Box 311 Burlington, Kansas 66839 l
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Enclosurs SAFETY EVALUATION TMI ACTION ITEM II.K.3.30 FOR WESTINGHOUSE PLANTS NUREG-0737 is a report transmitted by a letter from D. G. Eisenhut, Director of the Division of Licensing, NRR, to licensees of operating power reactors and applicants for operating reactor licenses forwarding TMI Action Plan requirements which have been approved by the Commission for implementa-tion.Section II.K.3.30 of Enclosure 3 to NUREG-0737 outlines the Commission requirements for the industry to demonstrate its small break loss of coolant accident (SBLOCA) methods continue to comply with the requirements of Appendix K to 10 CFR Part 50.
The technical issues to be addressed were outlined in NUREG-0611, " Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in Westinghouse-Designed Operating Plants." In addition to the concerns listed in NUREG-0611, the staff requested licensees with U-tube steam generators to assess their computer codes with the Semiscale S-UT-08 experimental results.
This request was made to validate the code's ability to calculate the core coolant level depression as influenced by the steam generators prior T.o loop seal clearing.
~ In response to TMI Action Item II.K.3.30, the Westinghouse Owners Group (WOG) has elected to reference the Westinghoue NOTRUMP code as their new licensing small break LOCA model. Referencing the new computer code did not imply deficiencies in WFLASH to meet the Appendix K requirements. ,The decision was based on desires of the industry to perform licensing evaluatio'ns with a computer program specifically designed to calculate small break LOCAs with greater phenomenological accuracy than capable by WFLASH.
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The following documents our evaluation of the WOG response to TMI Action Item II.K.3.30 confirmatory items.
II.
SUMMARY
OF REQUIREMENTS NUREG-0611 required licensees and applicants with Westinghouse NSSS designs to address the following concerns:
A. Provide confirmatory validation of the small break LOCA model to adequately calculate the core heat transfer and two phase coolant level during core uncovery conditions.
B. Validate the adequacy of modeling the primary side of the steam generators as a homogeneous mixture.
C. Validate the condensation heat transfer model and affects of non-condensible gases.
D. Demonstrate, through noding studies, the adequacy of the SBLOCA model to calculate flashing during system depressurization.
E. Validate the polytropic expansion coefficient applied in the accumu-lator model, and F. Validate the SBLOCA model with LOFT tests L3-1 and L3-7. In addition, validate the model with the Semiscale S-UT-08 experimental data.
Detailed responses to the above items are documented in WCAP-10054,
" Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code."
III. EVALUATION The following is the staff's evaluation of the TMI Action Ite'm require-ments outlined above.
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! A. Core Heat Transfer Models
. The Westinghouse Owners Group (WOG) referenced the NOTRUMP computer code as their new computer program for small break loss of coolant accident (SBLOCA) evaluation. NOTRUMP was benchmarked against~ core uncovery experiments conducted at the Oak Ridge National Laboratory (ORNL). These tests were performed under NRC sponsorship. The good agreement between the calculations and the data confirmed the adequacy of the drift flux model used for core hydraulics as well as the core heat transfer models of clad temperature predictions.
The staff finds the core thermal-hydraulic models in NOTRUMP accept-able. This item is resolved.
B. Steam Generator Mixture Level Model
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NUREG-0611 requested licensees and applicants with Westinghouse
$ designed NSSSs to justify the adequacy of modeling the primary system of the steam generators as a homogeneous mixture. This question was l directed to the WFLASH code. NOTRUMP, the new SBLOCA licensing code j models phase separation and incorporates flow regime maps within the steam generator tubes. The adequacy of this model was demonstrated through benchmark analyses with integral experiments, in particular with Semiscale test S-UT-08.
The staff finds the steam generator model in NOTRUMP acceptable.
This item is resolved.
C. Noncondensible Affects On Condensation Heat Transfer NUREG-0611 requested validation of the condensation heat transfe.-
correlations in ',he Westinghouse SBLOCA model and an assessment cf 3
e-the consequences of noncondensible gases in the primary coolant.
The condensation heat transfer model used in NOTRUMP is based on steam experiments performed by Westinghouse on a 16-tube PWR steam generator model. For two phase conditions, an empirical correlation developed by Shah is applied.
The staff finds the condensation heat transfer correlation in NOTRUMP acceptable.
, The influences of noncondensible gases on the condensation heat transfer was demonstrated by degrading the heat transfer coefficient in the steam generators. The heat transfer degradation was calculated using a boundary layer approach. For this calculation, the noncon-densible gases generated within the primary coolant system were col-1ected and deposited on the surface of the steam generator tubes.
The sources of noncondensibles considered were:
(i) Air dissolved in the RWST.
(ii) Hydrogen dissolved in the primary system.
(iii) Hydrogen in the pressurizer vapor space.
(iv) Radiolytic decomposition of water.
With a degradation factor on the heat transfer coefficient, the limiting SBLOCA was reanalyzed for a typical PWR. The WOG, thereby, concluded that formation of noncondensible gases in quantities that may reasonably be expected for a 4-inch cold leg break LOCA presents no serious detriment on the PWR system response in terms of core uncovery or system pressure. What perturbation was observed was minor in nature.
The staff finds acceptable the Westinghouse submittal on the influences of noncondensible gases on design bases SBLOCA events. Our ccnclusion is based on the limited amount of noncondensible gases available dur-ing a design basis SBLOCA event, as well as results obtained from Semi-scale experiments which reached similar conclusions while injecting noncondensible gases in excess amount expected during a SBLOCA design basis event. This item is resolved.
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D. Nodalization Studies For Flashing During Depressurization As a consequence of the staff's experience with modeling SBLOCA events with NRC developed computer codes (in particular the THI-2 accident), the staff questioned the adequacy of the nodalization in the licensing model to calculate the depressurization of the primary system. The staff therefore requested validation of the Westinghouse Evaluation Model to properly calculate the depressurization expected during a SBLOCA event.
Through nodalization. studies and validation of the NOTRUMP licensing model with integral experiments (e.g., LOFT and Semiscale), Westing-house demonstrated the acceptability of the nodalization and nonequi-librium models.
The staff finds the W estinghouse model acceptable for calculating depressurization during SBLOCA events. This item is resolved.
l E. Accumulator Model WFLASH, the previous Westinghouse small break loss of coolant accident (SBLOCA) analysis code, applied a polytropic gas expansion coefficient of 1.4 to the nitrogen in the accumulators. The WOG was requested to validate this accumulator model in light of data obtained through the LOFT experimental programs for SBLOCAs. Westinghouse reviewed the f applicable LOFT data and determined the need to perform full scale i
accumulator tests. Based upon these tests, Westinghouse modified the polytropic expansion coefficient to a more realistic value. Of inter-est is Westinghouse's conclusion that the selection of either a high or low expansion coefficient had negligible effect on the calculated peak clad temperature (PCT). This insensitivity is only appropriate to NOTRUMP, with its nonequilibrium assumptions.
t The staff finds acceptable the polytropic expansion coefficient in
- the NOTRUMP code. This item is resolved.
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F. Code Validation Following the Taree Mile Island event of 1979, staff analyses with NRC developed computer codes led to concerns that detailed nodali-zation was required to simulate realistic systems responses to postu-lated SBLOCAs. As a consequence, licensees and applicants with Westing-house plants were requested to validate their licensing tools with integral experiments. In specific, the NRC requested that the computer codes be validated with the LOFT L3-1 and L3-7 experimental data. In addition, the staff also requested that the code be benchmarked with the Semiscale S-UT-08 experimental data.
- Westinghouse performed the above benchmark analyses. For the LOFT tests, Westinghouse showed good agreement between the NOTRUMP calcu-lations and the experimental data. For the S-UT-08 test, Westinghouse demonstrated that NOTRUMP did a reasonable job calculating the experi-mental data. However, this required a more detailed nodalization of the steam generators then used in the licensing model. With the less detailed licensing nodalization, the pre-loop-seal-clearing core level depression phenomenon, as observed in the S-UT-08 data, was not con-servatively calculated for very small breaks. However, the calculated peak clad temperature was demonstrated to be higher (more conservative)
! with the coarse nodalization. The staff, therefore, finds acceptable the NOTRUMP computer code and the associated nodalization for SBLOCA i design basis evaluation.
This item is resolved.
IV. CONCLUSION The Westinghouse Owners Group (WOG), by referencing WCAP-10079,and WCAP-10054, have identified NOTRUMP as their new thermal-hydraulic c'omputer program for calculating small break loss of coolant accidents (SBLOCAs). The staff finds acceptable the use of NOTRUMP as the new Westinghouse licensing tool for calculating SBLOCAs for Westinghouse NSSS designs.
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The responses to NUREG-0611 concerns, as evaluated within this SER, have also been found acceptable.
This SER completes the requirements of TMI Action Item II.K.3.30 for licensees and applicants with Westinghouse NSSS designs who were members of the WOG and referenced WCAP-10079 and WCAP-10054 as their response to this item.
Within one year of receiving this SER, the licensees and applicants with Westinghouse NSSS designs are required to submit plant specific analyses with NOTRUMP, as required by TMI Action Item II.K.3.31. Per generic letter 83-35, compliance with Action Item II.K.3.31 may be submitted generically. We require that the generic submittal include validation that the limiting break location has not shifted away from the cold legs to the hot or pump suction legs.
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