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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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c %, UNITE 3 8TATES g a NUCLEAR REGULATORY COMMISSION s wAsHmGTON, D. C. 20666 10 JUN 1986 .
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Docket Nos.: 50-369, 50-370,
. 50-413, 50-414 l
Mr. H. B. Tucker, Vice President Nuclear Production Department
, Duke Power Company
, 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. . Tucker:
l
Subject:
TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps, Catawba and McGuire Nuclear Stations, Units 1 and 2 The NRC staff is reviewing your responses to Generic Letter 85-12 for Catawba 7 and McGuire Nuclear Stations regarding implementation of TMI Action Item II.K.3.5,
" Automatic Trip of Reactor Coolant Pumps." The enclosure describes our pre-liminary review results and contains several coments reflecting a need for clarifications and additional infomation. Although the enclosure is based upon McGuire, it also substantially applies to Catawba.
We recomend the following course of action with respect to completion of this review effort:
(1) That the enclosure serve as the basis for a telephone conference call prior to initiation of preparation of a response.
(2) That the NRC staff document results of the telephone conference, including our understanding of your responses, and forward to you.
(3) That you confirm the accuracy of our description of the responses, identify any appropriate changes, and provide any supplemental information needed to complete the review.
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Upon satisfactory completion of the above, the staff would complete its SERs.
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e60620o329 860610 9 PDR ADOCK OLOO P
N Mr. H. B. Tucker i}
An alternate approach for Item (1) above would be a meeting. An alternate to Items 1 through 3 would be your treatment of the enclosure as a fomal request j for additional information. In any event, because of the substantial similarity F.
between the McGuire and Catawba approaches for RCP trip, we recomend you con-sider a combined comunication covering both facilities.
1 Contact your Project Manager, Darl Hood at (301) 492-8060 or Kahtan Jabbour at j (301)492-7367 to arrange a conference call or meeting, to schedule your reply dates, or if you have questions regarding the enclosure. l
} Sincerely, I h M
! $ B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A, NRR
Enclosure:
As stated 7
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Mr. H. B.. Tucker I O JUN 1386 s
T An alternate approach for Item (1) above would be a meeting. An alternate to Items- 1 through 3 would be your treatment of the enclosure as a formal request for additional:infomation. In any event, because of the substantial similarity
. between the McGuire and Catawba approaches for RCP trip, we recomend you con-sider a combined comunication covering both facilities, e Contact you'r Project Manager, Darl Hood at (301) 492-8060 or Kahtan Jabbour at (301)492-7367 to arrange a conference call or meeting, to schedule your reply dates, or if you have questions regarding the enclosure.
Sincerely,
\6 \
B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A, NRR
Enclosure:
As stated
. cc: See next page DISTRIBUTION:
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, Mr. H. B. Tucker Duke Power Company McGuire Nuclear Station CC:
Mr. A. Carr Dr. John M. Barry Duke Power Company Department of Environmental Health
,- P. O. Box 33189 Mecklenburg County 422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 1
,i Mr. F. J.-Twogood County Manager of Mecklenburg County l Power Systems Division 720 East Fourth Street
! Westinghouse Electric Corp. Charlotte, North Carolina 28202 j P. O. Box 355 Pittsburgh, Pennsylvania 15230 Chainnan, North Carolina Utilities Commission 5 Mr. Robert Gill Dobbs Building Duke Power Company 430 North Salisbury Street l Nuclear Production Department Raleigh, North Carolina 27602 P. O. Box 33189 Charlotte, North Carolina 28242 Mr. Dayne H. Brown, Chief
. Radiation Protection Branch J. Michael McGarry, III, Esq. Division of Facility Services I Bishop Libennan, Cook, Purcell Department of Human Resources
)
and Reynolds P.O. Box 12200 -
) 1200 Seventeenth Street, N.W. Raleigh, North Carolina 27605 Washington, D. C. 20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Connission
- Route 4, Box 529 Hunterville, North Carolina 28078 .
i Regional Administrator, Region II l U.S. Nuclear Regulatory Commission, 3
101 Marietta Street, N.W., Suite 2900
. Atlanta, Georgia 30323 3- .
L. L. Williams Operating Plants Projects Regional Manager l Westin house Electric Corporation - R&D 701 P. O. ox 2728 Pittsburgh, Pennsylvania 15230
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- Mr. H. B. Tucker t
. Duke Power Company Catawba Nuclear Station cc:
William L. Porter, Esq. North Carolina Electric Membership Duke Power Company ' Corp.
P.O. Box 33189 3333 North Boulevard Charlotte, North Carnlina 28242 P.O. Box 27306
- Raleigh, North Carolina 27611 J. Michael McGarry, III, Esq.
Bishop, Liberman, Cook, Purcell Saluda River Electric Cooperative, and Reynolds Inc.
1200 Seventeenth Street, N.W. P.O. Box 929 Washi'ngton, D. C. 20036 Laurens, South Carolina 29360 North Carolina MPA-1 Senior Resident Inspector
. Suite 600 Route 2, Box 179N 3100 Smoketree Ct. York, South Carolina 29745 P.O. Box 29513
[ Raleigh, North Carolina 27626-0513 Regional Administrator, Region II U.S. Nuclear Regulatory Comission, Mr. C. D. Markham 101 Marietta Street, NW, Suite 2900 Power Systems Division Atlanta, Georgia 30323 t
f Westinghouse Electric Corp.
P.O. Box 355
! Pittsburgh, Pennsylvania 15230 Robert Guild,'Esq.
2759 Rosewood Drive i NUS Corporation Columbia, South Carolina 29205 2536 Countryside Boulevard i Clearwater, Florida 33515 Palmetto Alliance
! 2759 Rosewood Drive l Mr. Jesse L. Riley, President Columbia, South Carolina 29205 Carolina Environmental Study Group .
I 854 Henley Place Karen E. Long Charlotte, North Carolina 28208 Assistant Attorney General N.C. Department of Justice Richard P. Wilson, Esq. P.O. Box 629 4 Assistant Attorney General Raleigh, North Carolina 27602 S.C. Attorney General's Office
.J P.O. Box 11549 Spence Perry, Esquire
- Columbia, South Carolina 29211 Associate General Counsel Federal Emergency Management Agency Piedmont Municipal Power Agency Room 840 100 Memorial Drive 500 C Street
[ Greer, South Carolina 29651 Washington, D. C. 20472 Mark S. Calvert, Esq. Mr. Michael Hirsch Bishop, Liberman, Cook, Federal Emergency Management Agency Purcell & Reynolds Office of the General Counsel
. 1200 17th Street, N.W. Room 840 Washington, D. C. 20036 500 C Street S.W. .
Washington, D. C. 20472 Brian P. Cassidy, Regional Counsel Federal Emergency Management Agency, Region !
J, W. McCormach POCH Boston, Massachusetts 02109 ,
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Catawba (amendments) cc:
Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina. Department of Health and Environmental Control 2600.Bu11 Street-Columbia, South Carolina 29201 County Manager of York County York County Courthouse York. South Carolina 29745
. Attorney General P.O. Box 11549 Columbia, South Carolina 29211 T
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ENCLOSURE
. PRELIMINARY REVI.EW OF.
l REACTOR COOLANT PUMP (RCP) TRIP CRITERIA MCGUIRE UNITS 1 AND 2 RCP TRIP
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INTRODUCTION Listed.below ars the evaluation criteria the staff is applying to RCP trip review and our~ preliminary appraisal of whether sufficient information was
! provided for.the staff to complete its review. The organization of thi's g Enclosure is a staff provided guidance or evaluation criterion statement based-E upon Gener'ic Letter 85-12 (Ref. 1), generally'followed by a staff critique of
- the initial _ licensee submittal (Ref. 2).
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The staff plan to complete the review is to use this Enclosure as the basis for a telephone conference call prior to initiation of a significant response
-effort on the part of the licensee. The staff then plans to document the
< results of- the preliminary review and the telephone conference call, and to provide that documentation to the licensee. Then the licensee can provide a 1 written response regarding the accuracy of the staff perception of the telephone conference call, together with any desired corrections and i supplemental information. This should allow the staff to complete the review f and prepare a Safety Evaluation Repo'rt (SER). An alternate, if the licensee desires (and which is r4 presently' contemplated), is for the staff to prepare l"
w i formal-questions 4 r ' ice see consideration.
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N The submittal for McGuire is similar to that for Catawba (Ref. 3). Most of the staff response to Reference 3 is identical to that.of Reference 2. Since i many of the same points apply, the staff buggests the reviews be coordinated i to minimize time requirements, imposed upon both Duke and the staff.
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- OVERALL GUIDANCE PERTINENT TO RCP TRIP During a-small break accident in certain' break size ranges, there exists a window in time during which tripping RCPs will make the accident worse.
Therefore, in a small break situation, one must trip RCPs prior to entering the window. If one wishes to depend upon manual trip,'two criteria are applicable:
- 1. -One must show that at least 2 minutes exist within which to trip RCPs-following " receipt of a trip signal" using licensing calculations as a I basis.
- 2. One must show that at least 10 minutes exist within which to trip RCPs following " receipt of a trip signal" using best estimate calculations as a basis.
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If, for some reason, the RCPs have.not been tripped within 10 minutes of the time at which plant conditions indicate trip should be performed, they are to be left running until after the window is closed. Closure can be indicated by parameters such as regaining both adequate subcooling margin and pressurizer
- level after they have been lost.
Analyses are required to establish timing relative to items 1 and 2, as well as to establish the' dimensions of the window.
- -It-is desirable to leave pumps running for control purposes during other transients and accidents, including steam generator tube rupture accidents of l sizes up to one tube broken. Therefore, insofar as is practical, procedures
[ and criteria should be developed to attain this goal. Note that leaving pumps
.I running during "non-break" transients and accidents is not a 100% requirement, O as cuntrasted to the small break, where trip must be accomplished to remain in I compliance with the regulations. (Failure to trip as required could lead to i exceeding Appendix K specified temperatures.) For "non-break" transients and accidents, RCPs may be tripped when desirable. If in doubt, the small break i ~
criteria are to be applied.
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New plants coming on line should have dealt with RCP trip prior to power
,. operation.
Note much of the work pertinent to the above criteria has been done on a generic basis, and is applicable to individual plants., Where this is the' case, it is sufficient to establish applicability, and the generic work need not be repeated on a plant specific basis.
SPECIFIC EVALUATION CRITERIA AND COMENTS The evaluation criteria are generally those provided in Reference 1, including the Safety Evaluation and its appendices, which were an enclosure to Reference 1.
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A. Determination of RCP Trip Criteria i
Demonstrate and justify that proposed RCP-trip setpoints are adequate for small-break LOCAs but will not cause RCP trip for other non-LOCA transients and accidents such as SGTRs. This is to include performance
?- of safety analyses to prove the adequacy of the setpoints.
Consider using partial or staggered RCP-trip schemes.
Staff Evaluation. Duke has selected Reactor Coolant System (RCS) subcooling as the criterion for tripping the Reactor Coolant Pumps (RCP).
The subcooling option was previously identified by the staff as the j second choice of the three options described by the Westinghouse Owners f Group (WOG) in their evaluation of RCP trip. It is also a choice that i few other plants are making. This is an acceptable selection if sufficiently justified. Therefore, the staff requests information pertinent to this selection.
The quantitative value associated with subcooling that is to be used as the trip criterion is not identified. Are the RCPs to be tripped on loss L
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of subcooling or of subcooling margin and, if the latter, what is the margin?
.A1. Identify the instrumentation to be used to determine the RCP trip set point, including the degree of redundance of each parameter signal needed for the criterion chosen. Establish the quality level for the instrumentation, identify the basis for the sensing-instruments' design features, and identify the basis for the degree of redundance.
Staff Evaluation. Duke has elected to use subcooling as determined by
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the plant computer as the primary indicator of the need to trip the RCPs.
If the plant computer is not available, they will use instrumentation readings available to the operator on control room indicators, and will apply graphs containing pressure and temperature information to determine
! the subcooling.
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p Input to the plant computer consists of wide and low range RCS pressure,
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j , a hot leg temperature from each of the hot legs, and core exit thermocouples. Low range pressure is used, if valid, since this is stated to have a smaller uncertainty than wide range. If unavailable, then wide range pressure is used. (The wording is such that the staff is 1
not clear on whether wide range pressure is the same as pressurizer l pressure.) If this is unavailable, then pressurizer pressure is used.
l The highest five valid thermocouple readings are used to determine an average. This average is compared with the four loop wide range temperatures, and the highest valid indication from this comparison is
- used as the temperature input.
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I The quality level and bases for these pressures and temperatures are not identified, nor are the specific instruments. In the case of the core exit thermocouples, the identity is obvious, and no further information t
t is necessary. Are the hot leg temperatures RTD readings from manifolds which are connected to the hot legs? Where are the pressure i determinations made (i.e. , are they pressurizer connections or
[ connections to some other part of the RCS pressure boundary)? -
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Yhat constitutes a " valid" reading and how is validity determined? How is the influence of adverse conditions factored into the decisions?
A2. Identify the instrumentation uncertainties for both normal and adverse containment conditions. Describe the basis for the selection of the adverse containment parameters. Address, as appropriate, local conditions, such as fluid jets or pipe whip, which might influence instrumentation reliability.
Staff Evaluation. Instrumentation uncertainty for normal and adverse environmental conditions is listed as follows:
Instrument Normal Adverse Conditions Conditions p RCS Wide Range Pressure 63 213
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RCS Low Range Pressure 29 125 Loop Wide Range Hot Leg Temperature, F 8.1 8.5 Core Exit Thermocouple Temperature, F 7.2 8.5 where the core exit temperature error increases with temperature, the error shown is for 530 F, and this error is assumed applicable below 530 F. ,
A value of 3 psig .is used as the basis for selection of adverse 4 containment parameters. This approximately corresponds to the high-high containment pressure setpoint.
Local conditions which might influence instrument reliability are stated as addressed in the McGuire response to NUREG-0588. It would be helpful if this were summarized with respect to RCP trip, including consideration of conditions outside of containment that may influence un. certainty. For example, has Duke surveyed the wiring and connections between the pressure transmitters and the control room to assure that a steam line 5
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- Q break inside or outside of containment will not introduce problems with the pressure readings in the control room?
Are any of the pressure transmitters located outside containment, and, if so, what is the instrument response time?
! A3. In addressing criterion selection, provide consideration of uncertainties associated with the WOG supplied analyses values. These uncertainties are to include uncertainties in computer program results and uncertainties resulting from plant specific features not representative of the generic data group.
If a licensee (or applicant) determines that the WOG alternative criteria are marginal for preventing unneeded RCP trip, it is recommended that a f .
more discriminating plant-specific procedure be developed. Licensees (or l f' applicants) should take credit for all equipment (instrumentation) f~
available to the operators for which the licensee (or applicant) has sufficient confidence that it will be operable during the expected
- conditions.
Staff Evaluation. Calculations of instrument uncertainties are
. summarized, and comparisons are discussed between plant data and calculations in the Westingliouse Owners Group (WOG) information. Duke states that the calculated overall uncertainty for McGuire is from -10 F I to +10 F for the subcooling trip point.
The licensed Westinghouse LOFTRAN computer code is referenced for l
1 performance of the non-LOCA analyses. The computer program result uncertainties evaluation is based on the assumption of no changes-in initial plant conditions (such as full power, pressurizer level, all Safety Injection (SI) pumps running,-and all Auxiliary Feed Water (AFW) pumps running). The major contributors to uncertainty are stated to be
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- . break flow rate, SI flow rate, decay heat generation rate, and AFW flow h rate. Parametric studies are summarized in which the major uncertainties
[ are stated to be due to the break flow model and SI flow inputs.
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l~' Duke has not directly addressed such topics as the accuracy of the i numerical solution scheme or of nodalization. Further, there is no determination of the influence of equipment or operational failures.
Information pertinent to the former result from comparisons of the LOFTRAN code to operational and experimental data, and as a result will
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! have been included in the uncertainty number. Determination of equipment
.or operational failures is not a necessity as long as the expected configuration of the plant is addressed since the objective of RCP trip is to provide reasonable assurance of not tripping for transients for which a trip is undesirable. It is not necessary to establish that one l will never trip since the plant is capable of being safely controlled if an unnecessary trip does occur. Thus, no additional information is needed for the staff to complete review of this item.
. B. Potential Reactor Coolant Pump Problems T
Bl. Assure that containment isolation, including inadvertent isolation, will
. not cause problems if it occurs for non-LOCA transients and accidents.
Demonstrate that, if water services needed for RCP operations are terminated, they can be restored fast enough once a non-LOCA situation is confirmed to prevent seal damage or failure. Confirm that' containment isolation with continued pump operation will not lead to seal or pump damage.or failure.
Staff Evaluation. The Duke response is essentially that either seal injection or thermal barrier cooling will continue regardless of the status of containment isolation, and therefore, there is not problem with h seal damage. Component Cooling Water (CCW) and service water are
,i . isolated on Phase B isolation (high-high containment pressure). RCPs are tripped promptly under these conditions.
The staff requests additional information pertinent to these points. For j example, do the conditions which lead to containment isolation result in termination of any portion of the Chemical and Volume Control System 1 (CVCS) and is there an indirect effect upon RCP seal injection? If CCW I
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pump operation is terminated, how long does it take for the pump to be restarted and flow restored to the thermal barrier heat exchangers and other RCP associated components? What are the implications? Information should be provided pertinent to restart of RCPs following restoration of services leading to a trip. Items such as trip parameters, operator response and timing of operations should be identified. The staff does not need a large volume of material on these topics, but does need a brief mention with perhaps reference to procedures in a list provided with the submittal.
- 82. Identify the components required to trip the RCPs, including relays, power supplies and breakers. Assure that RCP trip, when necessary, will occur. Exclude extended RCP_ operation in a voided system where pump head is more .than 10% degraded unless analyses or tests can justify pump and
. pump-seal integrity when operating in voided systems. If necessary, as a f result of the location of any critical component, include the effects of
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H adverse containment conditions on RCP trip reliability. Describe the basis for the adverse containment parameters selected.
Staff Evaluation. The major ~ components associated with RCP trip are identified, as is their location.
. A brief consideration should be given to the potential for adverse conditions outside containment and the implications, if any. For example, can a steam line break outside of containment introduce difficulties with respect to the equipment of interest here?
The timing of operations associated with alternate operator actions required to trip the RCPs should be mentioned. For example, if the operator attempts a trip from the control room and fails, how long will it take to trip from an alternate location, including travel time? (See Item C1, below.)
RCP operation in a voided system is not mentioned. -
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l C. Operator Training and Procedures (RCP Trip)
C1. Describe the operator training program for RCP trip. Include the general philosophy regarding the need to trip pumps versus the desire to keep pumps running. Also cover priorities for actions after engineered safety features actuation. -
Assure that training and procedures provide direction for use of individual steam generators with and without operating RCPs.
Assume manual RCP trip does not occur earlier than two minutes after the RCP-trip set point is reached.
i Determine the time available to the operator to trip the RCPs for the limiting cases if manual RCP trip is proposed. Best Estimate p . calculational procedures should be used. Most probable plant conditions
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should be identified and justified by the licensee, although NRC will accept conservative estimates in the absence of justifiable most probable conditions.
Justify that the time available to trip the RCPs is acceptable if it is less than the Draft ANSI Standard N660. If this is the case, then address the consequences if RCP trip is delayed. Also develop contingency procedures and make them available for the operator to uss in l case the RCPs are not tripped in the preferred time frame.
Staff Evaluation. A discussion of training is presented, but the background philosophy is not clearly described, and some of the above points are not addressed. For example, what is the general need to trip RCPs as contrasted to keeping them running? What is the RCP restart philosophy? If one has tripped RCPs, and desires to restart them for control purposes and to aid in plant cooldown, what requirements must be met?
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. C2. Identify those procedures which include RCP trip related operation:
(a) RCP trip using WOG alternate criteria (b) RCP restart (c) Decay heat removal-by natural circulation (d) Primary system void removal (e) Use of steam generators with and without RCPs operating (f) RCP trip for other reasons Ensure that emergency operating procedures exist for the timely restart of the RCPs when conditions warrant.
f Staff Evaluation. Duke has presented a listing of selected procedures and provides discussions which address these topics.
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l REFERENCES -
- 1. Thompson, Hugh L. Jr. , " Implementation of TMI Action Item II.K.3.5,
' Automatic Trip of Reactor Coolant Pumps' (Generic Letter No. 85-12)",
NRC Letter Addressed to All Applicants and Licensees with Westinghouse g ) Designed Nuclear Steam Supply Systems (NSSSs), Jun. 28, 1985.
- 2. Tucker, Hal B., "McGuire Nuclear Station, Docket Nos. 50-377 and 50-370, Generic Letter 85-12," Letter to Hugh L. Thompson, Jr. , NRC, from Duke Power Company, August 22, 1985.
- 3. Tucker, Hal B., " Catawba Nuclear Station, Docket Nos. 50-413 and 50-414, Generic Letter 85-12," Letter to Hugh L. Thompson, Jr. , NRC, from Duke Power Company, August 22, 1985.
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