Letter Sequence RAI |
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MONTHYEARML20151C9781988-04-0707 April 1988 Forwards Request for Addl Info Re Topical Rept WCAP-10988, COBRA-NC,Analysis for Main Steam Line Break in Ice Condenser Containment. Response Requested within 45 Days from Ltr Date Project stage: RAI ML20246L2741989-05-11011 May 1989 Forwards Anl Draft Rept Re Main Steam Line Breaks in Plants Ice Condenser,Per Util 880613,0907 & 1012 Ltrs & WCAP-10988 & WCAP-10986P,for Review & Comments within 60 Days.W/O Encl Project stage: Draft Other 1988-04-07
[Table View] |
Forwards Request for Addl Info Re Topical Rept WCAP-10988, COBRA-NC,Analysis for Main Steam Line Break in Ice Condenser Containment. Response Requested within 45 Days from Ltr DateML20151C978 |
Person / Time |
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Site: |
Mcguire, Catawba, McGuire, 05000000 |
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Issue date: |
04/07/1988 |
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From: |
Jabbour K Office of Nuclear Reactor Regulation |
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To: |
Tucker H DUKE POWER CO. |
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References |
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IEIN-84-90, TAC-60973, TAC-67767, TAC-67768, TAC-67803, NUDOCS 8804130309 |
Download: ML20151C978 (6) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058J1251990-11-13013 November 1990 Advises That Re Martin Recently Assigned as Project Manager for Facility ML20058H4551990-11-0707 November 1990 Forwards Insp Repts 50-369/90-20 & 50-370/90-20 on 901001-05 & 1101.No Violations or Deviations Noted ML20058F6161990-10-26026 October 1990 Forwards Insp Repts 50-413/90-28 & 50-414/90-28 on 901001-04.Violation Re Corrective Actions Which Appear to Be Ineffective in Preventing Recurrence of Similar Violation Noted.Enforcement Conference Scheduled for 901105 ML20058F0891990-10-22022 October 1990 Confirms 901031-1102 & 12-16 & 26-30 as Dates for Maint Team Insp of Plant Per 901011 Telcon IR 05000369/19900141990-10-17017 October 1990 Ack Receipt of 900928 Response Re Violations Noted in Insp Repts 50-369/90-14 & 50-370/90-14 ML20058B4551990-10-17017 October 1990 Forwards Insp Repts 50-413/90-25 & 50-414/90-25 on 900924-28.No Violations or Deviations Noted ML20058B9631990-10-12012 October 1990 Advises That Liquid Samples,Spiked W/Radionuclides,Will Be Sent to Facilities for Radiochemical Analyses for Tritium, Fe-55,Sr-89 & Sr-90.Analyses Should Be Completed within 60 Days ML20062B7051990-10-12012 October 1990 Requests Completion of Analysis of Liquid Samples Spiked W/ Radionuclides within 60 Days of Receipt of Ltr ML20058A2931990-10-10010 October 1990 Forwards Insp Repts 50-369/90-19 & 50-370/90-19 on 900924-28.No Violations or Deviations Noted ML20062A0951990-10-0303 October 1990 Forwards Insp Repts 50-413/90-24 & 50-414/90-24 on 900803- 0905 & Notice of Violation ML20059M8081990-09-25025 September 1990 Approves 900820 Revised Relief Request 89-02 to Replace 20- Inch Carbon Steel Elbow W/Stainless Steel Pipe ML20059K4451990-09-17017 September 1990 Advises That Ta Reed Assigned as Project Manager for Plant ML20059L4141990-09-14014 September 1990 Forwards Insp Repts 50-413/90-23 & 50-414/90-23 on 900730-0803.No Violations or Deviations Noted ML20059L5611990-09-13013 September 1990 Forwards Insp Repts 50-369/90-17 & 50-370/90-17 on 900726-0828.Violations Noted But Not Cited ML20059K6671990-09-10010 September 1990 Forwards Insp Repts 50-369/90-15 & 50-370/90-15 on 900813- 17.Violation Noted But Not Cited ML20059K0051990-09-0505 September 1990 Forwards Exam Rept 50-369/OL-90-02 Administered on 900730- 0802 ML20059L5241990-09-0505 September 1990 Ack Receipt of 900810 Supplemental Response to Violations Noted in Insp Repts 50-413/90-09 & 50-414/90-09 IR 05000413/19900151990-09-0505 September 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/90-15 & 50-414/90-15 IR 05000369/19900111990-09-0505 September 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-369/90-11 & 50-370/90-11 ML20059H0121990-08-31031 August 1990 Forwards Insp Repts 50-413/90-19 & 50-414/90-19 on 900624- 0802 & Notice of Violation.Util Should Detail Measures to Be Taken to Place Addl Emphasis on Compensatory Actions Program ML20059E3121990-08-30030 August 1990 Advises That Util Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Further NRC Review,If Any,Will Be Performed Either by Insp or Audit ML20059G6171990-08-28028 August 1990 Forwards Insp Repts 50-413/90-20 & 50-414/90-20 on 900724-26.Unresolved Item Identified Re Procedure of Equating self-referral to Employee Assistance Program as First Positive Drug Test ML20058N7901990-08-0909 August 1990 Forwards Safety Evaluation Supporting Util 890213 Relief Request 89-01 Re ASME Code Section XI Hydrostatic Testing Requirements ML20058P8381990-08-0303 August 1990 Discusses 900731 Enforcement Conference Re 900626 Event at Facility Involving Inoperability of Both Emergency Generators.List of Attendees & Supporting Info Encl ML20056A5571990-08-0202 August 1990 Requests Addl Info Re DPC-NE-2004, Core Thermal-Hydraulic Methodology Using VIPRE-01 for McGuire & Catawba. Requests Response Expeditiously IR 05000413/19900111990-08-0101 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/90-11 & 50-414/90-11 ML20058P8761990-07-31031 July 1990 Forwards Insp Repts 50-413/90-22 & 50-414/90-22 on 900709-13.No Violations or Deviations Noted IR 05000369/19900091990-07-30030 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-369/90-09 & 50-370/90-09 ML20055H9131990-07-27027 July 1990 Forwards Safety Evaluation Accepting Actions Taken to Resolve NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML20056A5171990-07-24024 July 1990 Confirms Arrangements for 900731 Enforcement Conference in Region II Ofc to Discuss Util Recent Problems Re Inoperability of Both Unit 1 Emergency Diesel Generators for Approx 26 H ML20056A5811990-07-24024 July 1990 Forwards Insp Repts 50-369/90-11 & 50-370/90-11 on 900522-0625 & Notice of Violation.Util Requested to Include in Response,Any Mgt Actions to Be Taken to Prevent Subj Event from Recurring ML20055J2931990-07-23023 July 1990 Forwards Request for Addl Info Re Util 900315 Submittal of General Relief Request for Pumps in Inservice Testing Program.Addl Info Re Certain Areas That Deviate from OM-6, Identified in Encl,Required to Complete NRC Review IR 05000413/19900171990-07-23023 July 1990 Discusses Insp Repts 50-413/90-17 & 50-414/90-17 on 900611- 19 & Forwards Notice of Violation.Insp Included Review of Actions Re 900611 Inadvertent Transfer of Reactor Coolant Water to Refueling Water Storage Tank at Unit 1 ML20056A5071990-07-20020 July 1990 Forwards Insp Repts 50-413/90-15 & 50-414/90-15 on 900527-0623 & Notice of Violation.Violations,Refs Pertinent to Requirements & Elements to Be Included in Response Presented in Encl Notice of Violation ML20055H4191990-07-19019 July 1990 Forwards Insp Repts 50-413/90-21 & 50-414/90-21 on 900627-29.No Violations or Deviations Noted ML20055H4101990-07-18018 July 1990 Forwards Summary of Enforcement Conference on 900712 Re Unit 1 Inadvertent Diversion of Higher Pressure Reactor Coolant Water to Refueling Water Storage Tank on 900611,per Insp Repts 50-413/90-17 & 50-414/90-17.Handouts Also Encl ML20055H5881990-07-13013 July 1990 Forwards Insp Repts 50-413/90-16 & 50-414/90-16 on 900611-15.Violations Noted But Not Cited ML20055H4811990-07-13013 July 1990 Forwards Insp Repts 50-369/90-14 & 50-370/90-14 on 900626-0705.Violations Noted.Enforcement Conference Scheduled for 900731 to Discuss Violations ML20058M9361990-07-13013 July 1990 Forwards Insp Repts 50-413/90-18 & 50-414/90-18 on 900625-29.No Violations or Deviations Noted ML20055H3601990-07-10010 July 1990 Advises That Reactor Operator & Senior Operator Licensing Exams Scheduled for Wk of 901015.Encl Ref Matls Requested by 900806 ML20055E3711990-07-0909 July 1990 Ack Receipt of Re Payment of Civil Penalties in Amount of $100,000,per NRC ML20055H4721990-07-0303 July 1990 Ack Receipt of 900522 & 0621 Ltrs Forwarding Objectives & Scenario Package for Emergency Preparedness Exercise Scheduled for Wk of 900813 ML20055H4411990-07-0202 July 1990 Ack Receipt of 900607 Response to Violations Noted in Insp Repts 50-413/90-09 & 50-414/90-09.Implementation of Corrective Actions Will Be Examined During Future Insp ML20055C9911990-06-27027 June 1990 Confirms Region II Insp of fitness-for-duty Program on 900724-26.Brief Itinerary to Expedite Util Support of Program Encl ML20059M9241990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C8421990-06-13013 June 1990 Forwards Insp Repts 50-413/90-14 & 50-414/90-14 on 900521-25.No Violations or Deviations Noted ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20248J3891989-10-16016 October 1989 Forwards Insp Repts 50-413/89-28 & 50-414/89-28 on 890911-15.Violations Noted ML20248D2921989-09-28028 September 1989 Discusses Util Response to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Boundary Components in PWR Plants ML20248B6881989-09-25025 September 1989 Forwards Insp Repts 50-413/89-25 & 50-414/89-25 on 890801-28 & 0912-15.No Notice of Violation Issued for Violations Identified.Enforcement Conference to Discuss Violations Scheduled for 890928 1990-09-05
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20210V0321999-08-13013 August 1999 Forwards Insp Repts 50-413/99-04 & 50-414/99-04 on 990606- 0717.Six Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210V0171999-08-13013 August 1999 Confirms Conversation Between M Cash & M Franovich on 990806 Re Mgt Meeting,Scheduled for 990917 to Present self- Assessment of Plant Performance.Meeting Will Be Held in Atlanta,Ga ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam ML20210Q3701999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date in Order to Register Individuals to Take Exam IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 ML20210H7691999-07-21021 July 1999 Submits Summary of 990715 Meeting at Facility Re Presentation of Results of Most Recent Periodic Ppr.List of Meeting Attendees Encl ML20217G5241999-07-20020 July 1999 Forwards Exam Repts 50-413/99-301 & 50-414/99-301 on 990524- 27,0603,07-10 & 16.Of Fourteen SRO & RO Applicants Who Received Written Exams & Operating Tests,Eight Applicants Passed & Six Failed Exam ML20210E1931999-07-13013 July 1999 Forwards Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20209E2701999-07-0101 July 1999 Forwards Insp Repts 50-413/99-03 & 50-414/99-03 on 990425- 0605.Six Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy IR 05000413/19990031999-07-0101 July 1999 Discusses Insp Repts 50-413/99-03 & 50-414/99-03 Completed on 990605 & Transmitted by Ltr .Results of Delibrations for Violation Re Discovery of Potentially More Limiting Single Failure Affecting SGTS Analysis Provided ML20196J4381999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid Version 2 ML20209E3931999-06-28028 June 1999 Informs of 990618 Meeting Conducted at Facility to Present Results of Most Recent Periodic Plant Performance Review for Plant.List of Attendees Encl ML20196G8861999-06-24024 June 1999 Discusses GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structrual Integrity 950816 & 960729 Responses.Rvid,Version 2 Released as Result of Review.Rvid Should Be Reviewed & Comments Should Be Received by 990901 If Not Acceptable for Plant ML20196G6541999-06-17017 June 1999 Confirms 990614 Telephone Conversation Re Rescheduling of Two Predecisional Enforcement Conferences Originally Scheduled for 990623.SSS Conference Rescheduled for 990712 & Ice Condenser Conference Rescheduled for 990720 ML20196A5781999-06-14014 June 1999 Discusses Notice of Enforcement Discretion for Duke Energy Corp Re Catawba Nuclear Station Unit 1 TSs 3.5.2 & 3.7.12 ML20195E9171999-06-0303 June 1999 Confirms Conversation with Bradshaw on 990526 Re Rescheduling 990607 Predecisional Enforcement Conference to Discuss Apparent Violation in Insp Repts 50-413/99-10 & 50-414/99-10.Conference Will Be on 990623 in Atlanta,Ga ML20195F4141999-06-0202 June 1999 Forwards Insp Repts 50-413/99-11 & 50-414/99-11 on 990422-23 & 0503.Apparent Violation Identified & Being Considered for Escalated Enforcement Action.Violation Involved Failure to Maintain Unit 1 Ice Condenser Lower Inlet Door Operable ML20195F1851999-06-0202 June 1999 Forwards Insp Repts 50-369/99-03 & 50-370/99-03 on 990328- 0508.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20195E8771999-06-0202 June 1999 Confirms Telcon with M Cash on 990524 Re Public Meeting for 990715.Purpose of Meeting to Discuss Results of NRC Most Recent PPR ML20207D0521999-05-21021 May 1999 Informs That in Telcon on 990519 Between a Orton & Rf Aiello Arrangements Made for Administration of Initial Written Exam for McGuire Nuclear Station on 990603.Exam Will Be Administered at Catawba Simultaneously with Written Exam ML20207C8721999-05-20020 May 1999 Forwards Insp Repts 50-413/99-02 & 50-414/99-02 on 990314-0424.Three Violations Occurred & Being Treated as non-cited Violations.Activities Generally Characterized by Safety Conscious Operations & Sound Engineering & Maint ML20207D0671999-05-20020 May 1999 Informs That During Meeting on 990512,arrangements Modified for Administration of Licensing Exams at Catawba Nuclear Station During Weeks of 990524 & 0607,respectively ML20207C8061999-05-19019 May 1999 Confirms 990510 Telcon with R Jones Re Predecisional Enforcement Conference Requested by NRC & Scheduled for 990607 in Atlanta,Ga to Discuss Apparent Violation Associated with Potential Inoperability of SSS 1999-09-24
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. April 7,1988 Docket Nos.: 50-413/414 DISTRIBUTION:
and 50-369/370 [DoctetFjJey~ K. Jabbour hkC PDR D. Hood Local PDR E. Jordan Mr. H. B. Tucker, Vice President PDll-3 Reading 0GC-WF Nuclear Production Departnent Catawba Reading J. Partlow Duke Power Company McGuire Reading ACRS(10) 422 South Church Street S. Varga C. Li Charlotte, North Carolina 28242 G. Lainas J. Wermiel M. Rood J. Craig
Dear Mr. Tucker:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON WCAP-10988, HAIN STEAM LINE BREAK IN ICE CONDENSER PLANTS - CATAWBA AND MCGUIRE NUCi. EAR STATIONS, UNITS 1 AND 2 (TACS 60973/67803 and 67767/67768)
Westinghouse Topical Report WCAP-10988, "COBRA-NC, Analysis for a Main Steam-line Break in the Catawba Unit 1 ' Ice Condenser Containment," was submitted to support modification of the LOTIC-3 computer code. The LOTIC-3 code was used by Westinghouse to reanalyze the ice condenser containment thermal response following a main steam line break (M3LB) with superheated steam releases as described in IE Information Notice No. 84-90, "Main Steam Line Break Effect on Environmental Qualification of Equipment." As a part of NRC staff review, Argonne National Laboratory (ANL) is currently performing an independent confirmatory analysis of a MSLB in the ice condenser containment.
Responses to the enclosed request for additional information are requ' 2d in order to allow ANL to complete its confirmatory analysis. '
t The concern regarding containment temperature following superheated steam releases was addressed and identified as an unresolved issue in the Catawba l SER and SSERs 2, 4, 5 and 6. The McGuire plant is also affected due to the design )
j similarity of the ice condenser containments in Catawba and McGuire. '
Your responses to the enclosure are requested within 45 days from the date of this letter. Pleasecontactmeat(301)492-1496, or D. Hood at (301) 492-1442, if you have questions regarding the enclosure or are unable to meet the requested response date.
The reporting and/or recordkeeping requirements contained in this letter affect fewer that 10 respondents; therefore, OMB clearance is not required under P.L.
96 51.
Sincerely, l
Original signed by:
l Kahtan N. Jabbour, Project Manager l$k41$0$$$!O00369 Project Directorate 11-3 p PDR Division of Reactor Projects, I/II Enr.losure:
As stated cc: See next page ./
LA:Q) PM:PUII-3 PM:PDII-3 PD:PDII-3 MM65 {-3 KJabbour:pw DHood Acting PD j/ /88 g/}/88 t r / 7/88 y/7/88
- l Mr. " a i ckert l Duke e mpany Catawba Nuclear .C' "an CC' A.V. Carr, Esq. North Carolina Q .tric Membership Duke Power Ccapany Corp.
422 South Church Street 3400 Sumner Boulevard i Charlotte, North Carolina 28242 P.O. Box 27306 1 Raleigh, North Carolina 27611
- J. Michael McGarry, III, Esq.
- Bishop, Liberman, Cook, Purcell Saluda River Electric Cooperative, ,
and Reynolds Inc. -
I 1200 Seventeenth Street, N.W. P.O. 80x 929 :
Wasitington, D. C. 20036 Laurens, South Carolina 29360 i North Carolina MPA-1 Senior Resident inspector i Suite 600 Route 2, Box 179N '
3100 Smoketree Ct. York, South Carolina 29745 P.O. Bcx 29513 l Raleigh, North Carolina 27626-0513 Regional Administrator, Pegion II U.S. Nuclear Regulatory Comission, 1 S. S. Kilborn 101 Marietta Street, hW, Suite 2900 i Area Manager, Mid-South Area Atlanta, Georgia 30323 ESSD Projects Westinghouse Electric Corp. Mr. Heyward G. Shealy, Chief MNC West Tower - Day 239 Bureau of Radiological Health P.O. Box 355 South Carolina Department of Health Pittsburgh, Pennsylvania 15230 and Environmental Control l 2600 Bull Street l County Manager of York County Columbia, South Carolina 29201 1 York County Courthouse ;
York South Carolina 29745 Karen E. Long j Assistant Attorney General 1 Richard P. Wilson, Esq. N.C. Department of Justice Assistant Attorney General P.O. Box 629 S.C. Attorney General's Office Raleigh, North Carolina 27602 .
P.O. Box 11549 I Columbia, South Carolina 29211 Spence Perry, Esquire I General Counsel Piedmont Municipal Power Agency Federal Emergency Managenent Agency 100 Memorial Drive Room 840 Greer, South Carolina 29651 500 C Street Washington, D. C. 20472 Mr. Michael Hirsch Federal Emergency Management Agency Office of the General Counsel Room 840 500 C Street, S.W.
Washington, D. C. 20472 I Brian P. Cassidy, Regional Counsel Federal Emergency llanagement Agency, l
Region 1 l J. W. McCornach POCH Boston, Massachusetts 02109 1
. . - . . - . . . ._ . - _ _ __ _ =..-.
Mr. H. B. Tucker Duke Power Company McGuire Nuclear Station cc:
Mr. A.V. Carr, Esq. Dr. John it. Barry Duke Power Company Department of Environnental Health P. O. Box 33189 Mecklenburg County 422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 County Manager cf Mecklenburg County Mr. Dayne H. Brown, Chief 720 East fourth Street Radiation Protection Branch Charlotte, North Carolina 28202 Division of Facility Services Dcpartment of Human Resources 701 Barbour Drive Mr. Robert Gill Raleigh, North Carolina 27603-2008 Duke Power Company Nuclear Production Department P. O. Box 33189 Charlotte, Ncrth Carolina 28242 J. Michael McGarry, III, Esq.
Bishop, Liberman, Ccok, Purcell and Reynolds 1200 Seventeenth Street, N.W.
Washington, D. C. 20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Commissien Route 4, Box 529 Hunterville, North Carolina 28078 Regional Administrator, Regicn II U.S. Nur. lear Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 S. S. Kilborn Area Manager, Mid-South Area ESSD Projects Westinghouse Electric Corporation MHC West Tower - Bay 239 P. O. Box 355 Pi+tsburgh, Pennsylvania 15230
Enclosure REQUEST EOR ADDITIONAL INFORMATION i FOR THE REVIEW OF TOPICAL REPORT WCAP-10988, HAIN STEAM LINE BREAK IN ICE CONDENSER CONTAINMENTS PLANT SYSTEMS BRANCH Argonne National Laboratory (ANL) is performing an independent confirmatory analysis for the staff using the computer code COMMIX to calculate the resulting condition of a main steam line break in ice condenser containments. In WCAP-10988, Westinghouse used two mod 215, COBRA-NC/MODEL 2 and COBRA-NC/Mo di 3, to predict the temperature in the lower compartment of the ice condenser containment. The COBRA-NC/Model 3 uses a finer mesh model. In the preliminary calculatier.s, COMMIX will model the CATAWBA lower compartment with the same mesh sizes used in the COBRA-NC/Model 3 calculation. Provide the following information correspon-ding to COBRA-NC/Model 3 in order to permit ANL to perform the above analysis.
- 1. The values of or and 40 in generating the computational cells as shown in Fig. 2.10.
Page 15:"The interior of the lower containment is divided into three radini rings and eight sectors." provide the specific values of the radial (ar) and circumferential (AO) dimensions for each cell.
- 2. Describe how the hydraulic diameters listed in Table 5.2 were calculateo.
Page 75:"Nominal areas and wetted paraceters were normally based on the size of the subchannelt as shown in the plane views for each section. ;
Area and wetted parameter multipliers were then applied for each axial i elevatfon to account for equipment and structural changes."
Were the actual flow area and the wetter parameter for calculating the hydraulic diameter at each cell obtained from the above statement?
Are the area and wetted parameter multipliers only applicable in the axial direction for each computational cell? If not, there should be three
- j hydraulic diameters calculated from three sets of flow area and wetted ;
parameter for a particular cell since the flow is three-dimensional. How
- did COBRA-NC resolve this problem?
- 3. The actual flow area between cells.
In COMMIX, the volume porosity and surface permeability are introduced in the formulation of gova!rning equations. The volume porosity and surface permeability are defined as Volume porosity = Volume occupied by fluid in a control volume Total control surface Surface permeability = Area allowed for fluid flow through a control surface Total control surface The volume porosity for each cell in the COBRA-NC aodel is provided in Table 5.2, while the surface permeability is not available in the report, altnough the area multipliers and flow restricted area have been mentioned on page 75.
9 l
Provide the actual flow area between cells for every cell in Section A, Sec-tion B, and vessel enclosures of Section C of the COBRA-NC/Model 3.
- 4. The loss coefficients and other drag coefficients used in computing the pressure drop between cells.
1 On page 75:"Flow area restrictions were conservatively modeled ;
using sharp edge orif t::e loss coefficients, which would reduce the l flow between cells. Nominal flow areas were used for computing velocities." !
l What is the restricted area between cells? Is it related to the surface '
permeability as described in Item 3? Which correlation was used in calcu-lating the loss coefficient? If the correlation is based on the area i ratio and Reynolds number, what is the other area used besides the orifice area and how was the Reynolds number computed? Provide the loss coefficients
., and othsr drag coefficients used in the COBRA-NC/Model 3.
- 5. The location and dimension of the 8 foot high pipe tunnel underneath the spent fuel storage area.
On page 5:"An 8 ft. high pipe tunnel runa underneath the spent fuel ctorage region so that there fs flow communication around the full 360*
at this level."
Which cells are c9nnected to the pipe tunnel in the COBRA-NC model?
- 6. Material properties of heat conductors. l What values of thermal conductivity, heat capacity, and density of the heat conductors described in Table 5.1 are used in the COBRA-NC calcu-1ation?
Is the thermal resistance of paint on concrete and steel surfaces being '. l considered? If yes, what is the thickness of paint used in the calcula- !
tion and what is the material property? l
- 7. The tabulated mass. flowrate through the ice f.ondenser door as a function of time at each sector. l The COBRA-NC/Model 3 results show the ice condenser door vapor velocitie2 I in Figs. 6.57 through 6.59 for doors 32a, 326, and 32c. Where are these three doors located? Tabulate the mass flow rate through the doors,
- 8. The numerical values of the calculated drain mass flowrate and distribu-tion in COBRA-NC/Model 3.
(1) The calculated drain mass flowrate as shown in Figs. 6.61 and 6.62 on page 171 are difficult to read. Provide values of the drain flowrate as a function of time for Model 3.
l
. 4 l
l i
(2) How were drain flows distributed for the finer mesh channels in Model 3? Is the average value being used for the three subchannels?
If not, describe how it is used and provide the drain flow droplet l and film injection factors similar to Tables 4.3 through 4.15 for :
Model 3. l l
Correction or revision of the report.
9.
We have found some errors in the report; for example: l (1) Figure 2.10 and Fig. 5.4 are tlie same. There is no figure that descri5es the grid layout of Section B for the COBRA-NC/Model 2 in the report, while all data listed in Tables 5.2 and 5.3 is for
- Model 2.
(2) On page 162, the physical structure ire the middle figure is different from the other two.
(3) The description of the ice condenser doors in the last paragraph of :
page 134 is not consistent with Fig. 6.22. !
l Confirm the accuracy of the values in Tables 4.3 through 4.15 and Tables 5.1 through 5.3. The COMMIX code will use the current information as input.
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