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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 SEp 06 d Docket Nos. 50-369, 50-370 50-413, 50-414 License Nos. NPF-9, NPF-17 NPF-35, NPF-52 Duke Power Company ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:
SUBJECT:
MEETING
SUMMARY
- CATAWBA - DOCKET NOS. 50-413 AND 414; AND, MCGUIRE - DOCKET NOS. 50-369 AND 50-370 This letter refers to the meetinC conducted at your request in the NRC Region !! office on August 10, 1988. This was a management meeting to discuss your plant performance and improvement programs. A list of attendees, a brief suntiary and a copy of your handout are enclosed.
It is our opinion that this meeting was beneficial, and provided for a better understanding of overall plant performance and your plans for the future at Catawba and McGuire, in accordance with Section 2.790 of de NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
Should you have any questions concerning this matter, we will be pleased to discuss them.
Sincerely, Q,uc>, dU L W
Luis A. Reyes, Director Division of Reactor Projects
Enclosures:
@*^ I' s- E ^" b
- 1. Meeting Summary
- 2. Meeting Attendees -
- 3. Duke Power Company Handout - McGuira Nuclear Station 4 Duke Power Company Handout - Cetawba Nuclear Station cc w/encis: (See page 2) h 91901 m 800 06 i hp ADOCK O5000369 I I PNu _ ,
3 L- Y >
Duke Power Company 2 0 48 cc w/encis:
T. B. Owen, Station Manager, Catawba T. L. McConnell, Station Manager, McGuire bec w/encls:
NRC Resident Inspectors DRS, Technical Assistant D. Hood, NRR K. Jabbour, NRR Document Control Desk State of South Carolina Ri! e R!l RII ser h es VBr lee
."p/A/88 4
/1./88 j/ g/88
ENCLOSURE 1 MEETING
SUMMARY
Licensee: Duke Power Company Facilities: Catawba and McGuire Docket Nos.: 50-413, 50-414, 50-369 and 50-370 A management meeting was held in the NRC Region 11 office on August 10, 1988, to discuss recent events, overall plant performance and improvement programs.
J. Nelson Grace discussed the NRC desire to know how Duke perceived their overall performance at Catawba and McGuire and what their future plans are to enhance performance.
H. B. Tucker discussed how they intended to be open in their discussion of their self evaluation and that the plant managers would do the briefing for their respective site.
T. L. McConnell addressed the McGuire site's strengths and their concerns and initiatives in the areas of plant operations, radiological controls, maintenance / surveillance, emergency preparedness, security, engineer-ing/ technical support, and operator training and safety assessment /qualitj ,
verification, t T. B. Owen addressed the Catawba site's concerns, the counterpoints of the concerns and their strengths and initiatives in the arcas of plant operations, radiological controls, maintenance / surveillance, emergency preparedness, security, engineerir.9/ technical support and safety assessment / quality .
veiif, cation.
The NRC staff acknowledged the extensive resources and capabilities of Duke and that they have recognized many areas for improvement and that they are implementing corrective actions and developing program enhancements. The NRC expects their licensees to promptly evaluate and correct problems and we appreciated your frank discussion of your programs to accomplish these ends. ,
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ENCLOSURE 2 MEETING ATTENDEES W. T. Orders, Nuclear Regulatory Commission (NRC), Senior Resident, McGuire P. K. VanDoorn, NRC, Senior Resident Inspector, Catawba M. S. Lesser, NRC, Resident Inspector, Catawba T. A. Peebles, NRC, Section Chief V. L. Brownlee, Branch Chief, DRP, RI!
C. W. Hehl, Deputy Director Division cf Reactor Projects J. Nelson Grace, Regional Administrator G. C. Lainas, NRC/NRR, DRP E. W. Merschoff, Director, Division of Reactor Safety D. B. Matthews, Director. PDII-3, NRR D. Hood, Project Manager, PDII-3, NRR K. N. Jabbour, Catawba Project Manager, NRR J.P.Stohr, Director,DivisionofReactorSafetyandSafeguards(DRSS)
F. Jape, Technical Support Staf, DRS T. Owen, Catawba, Station Manager, Duke Power Coinpany (DPC)
H. B. Tucker, Vice president Nuclear Production, DPC T. McConnell, McGuire, Station Mar.ager, DPC
' 6 o UNITED STATES
- [p2 Clo ,#'o,* NUCLEAR REGULATORY COMMISSION
$' R EGl*N 11 a' * #f. o 101 MARIETTA STREET N.W.
- ATL ANTA. GEORGI A 30323 t,;*s.s
,/
SEP 00 8)a8 Docket Nos. 50-369, 50-370 50-413, 50-414 License Nos. NPF-9, NPF-17 NPF-35, NPF-52 Duke Power Company ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:
SUBJECT:
MEFTING
SUMMARY
< CATAWBA - DOCKET NOS. 50-413 AND 414; AND, MCOUIRE - DOCKET NOS. 50-369 AND 50-370 This letter refers to the meeting conducted at your request in the NRC Region !! Office on August 10, 1988. This was a management meeting to discuss your plant performance and improvement programs. A list of attendees, a brief summary and a copy of your handout are enclosed.
it is our opinion that this meeting was beneficial, and piovided for a better understanding of overall plant performance and your plans for the future at Catawba and McGuire.
In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10. Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the MC Public Document Room.
Should ycu have any questions concerning this matter, we will be pleased to discuss them.
Sincerely,
/ SG Luis A. Reyes, Director Division of Reactor Projects
Enclosures:
- 1. Meeting Sumary
- 2. Meeting Attendees -
- 3. Duke Power Company Handout - McGuire Nuclear Station 4 Duke Power Company Handout - Catawba Nuclear Station cc w/encis: (See page 2)
V
, 6 O
Duke Power Company 2 SEP v 9 ..
cc w/encls:
T. B. Owen, Station Manager, Catawba T. L. McConnell, Station Manager, McGuire r
O.
ENCLOSURE 1 MEETING
SUMMARY
Licensee: Duke Power Company Facilities: Catawba and McGuire Docket Nos.: 50-413, 50-414, 50-369 and 50-370 A management meeting was held in the NRC Region !! office on August 10, 1988, to discuss recent events, overall plant performance and improvement programs.
J. Nelson Grace discussed the NRC desire to know how Duke perceived their overall performance at Catawba and McGuire and what their future plans are to enhance performance.
H. B. Tucker discussed how they intended to be open in their discussion of their self evaluation and that the plant managers would do the briefing for their respective site.
T. L. McConnell addressed the McGuire site's strengths and their concerns and initiatives in the areas of plant operations, radiological controls, maintenance / surveillance, emergency preparedness, security, engineer-ing/ technical support, and operator training and safety assessment / quality verification.
T. B. Owen addressed the Catawba site's concerns, the counterpoints of the concerns and their strengths and initiatives in the areas of plant operations, radiological controls, maintenance / surveillance, m rgency preperedness, security, engineering / technical support and safety assessment / quality verification.
The NRC staff acknowledged the extensive resources and capabilities of Duke and that they have recognized many areas for improvement and that they are implementing corrective actions and developing program enhancements. The NRC expects their licensees to promptly evaluate and correct problems and we appreciated your frank discussion of your programs to accomplish these ends.
ENCLOSURE 2 MEETING ATTENDEES l W. T. Orders, Nuclear Regulatory Commission (NRC), Senior Resident, McGuire P. K. VanDoorn, NRC, Senior Resident Inspector, Catawba M. S. Lesser, NRC, Resident Inspector, Catawba T. A. Peebles, NRC, Section Chief V. L. Brownlee, Branch Chief DRP, RII l C. W. Hehl Deputy Director Division of Reactor Projects J. Nelson Grace, Regional Aduinistrator G. C. Lainas, NRC/NRR, DRP E. W. Merschoff, Director, Division of Reactor Safety D. B. Matthews, Director, PDII-3, NRR D. Hood, Project Manager, PDII-3, NRR K. N. Jabbour, Catawba Project Manager, NRR J. P. Stohr, Director, Division of Reactor Safety and Safeguards (DRSS)
F. Jape. Technical Support Staf, DRS T. Owen, Catawba, Station Manager Duke Power Company (DPC) 1 H. B. Tucker, Vice president Nuclear Production, DPC T. McConnell, McGuire, Station Manager, DPC
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ENCLOSURE 3 DUKE POWER COMPANY HANDOUT MCGUIRE NUCLEAR STATION 1
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McGUlRE NUCLEAR STATION
- 1. PLANT OPERATIONS STRENGTHS:
- Longer runs and improved capacity factors
- Use of SRO in integrated Scheduling to minimize operability conflicts e improved daily operating schedules
- Daily management plant status meetir.2s ;
- Decreased number of violations from 9 Level 4 in previous ,
SALP period to 1 Level 3 and 1 Level 4 in most recent SALP period
- No operator error induced reactor trips in 3 years e implemented tagging / labeling program for equipment and components - noticeable absence of wrong unit / wrong train ,
events in 1988 (
- Improved housekeeping / cleanliness in all areas
- Control room upgrade in progress - will improve working conJitions and standardize control room indications ;
- Control of materials / loose objects in containment l
- Use of plant deficiency tags to identify deficiencies and follow up actions
- Developed McGuire Management Council ;
- Developing international interface (Russia / Cuba / France) !
FIRE PROTECTION:
- Reliability enhancements to fire protection procedures i
- Ongol:tg review / upgrade of fire protection equipment pts l
- Improved organization / training of plant fire brigade
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- Thorough, technical Duka Power QA fire protection audits have been performed and Identified items for improvement that have been completed CONCERNS /lNITIATIVES:
x Operations / Maintenance work control practices and plant status knowledge needs improvement Project /2 schedule improvement allows every work activity to be updated daily. It produces individual crew schedules to allow better planning and prioritization of work. This provides a more accurate status of work completion and ensures controlled entry into various T. S. modes.
Plant management emphasis on improving root cause analysis of all plant events should improve our performance here. We are pressing accountability for this analysis to lower levels in the organizational and to less significant events.
X Unplanned reactor trips and associated ESF actuations are trending upward.
Two-thirds of all recent reactor trips are caused by equipment failures. When a piece of equipment falls when tested, it is trended and analyzed under the new Test Failure Analysis Program. This program includes an equipment history review and a root cause analysis.
System Experts are begl~nning to analyze equipment failures not associated with test failures, in addition a PM-2 program for predictive maintenance is being i utilized more extensively now.
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- Increased number of violations due to procedural non-compliance Violations are occurring due to inadequate procedures and a lack of strict adherence to procedures. Measures which have been taken which should improve our performance here:
(A) Clarified Independent Verification procedure and covered it in requal training.
(B) Clarified Tagout/ Removal and Restoration procedure and covered it in requal training.
(C) All sections are pursuing procedure upgrade programs.
(D) Line/ staff communications were held with station personnel to emphasize procedural adherence / procedural adequacy.
(E) Superintendents stress procedural adherence through section head meetings to maintain a heightened awareness.
(F) A station newsletter article, "Procedures are not Suggestions or Guidelines" by the Station Manage. was recently issued to employees (Refer to Attachment A).
(G) G.O. Licensing Group reviewed all incidents dealing with personnel error for trends, it was recommended that supervisors need to follow up on personnel errors to determine contributing factors or extenuating circumstances, if any, for the error.
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Emphasis on better root cause analysis should help resolve thin (Refer to Attachment B). l (H) The Operating Excerience Management and Analysis (OEMA) function in our General Office was recently requested to review incidents from the past two years dealing with procedural adherence to determine any underlying causes for deviation. It was determined that corrective actions for past incidents may have been too confined to a specific work group and that administrative deficiencies associated with procedural adherence should be better identified in the investigations. The report is currently under review (Refer to Attachment C).
(1) McGuire Operations personnel recently participated in the development of an Operations' "Commitment to Excellence" which is a professional code of conduct (Refer to Attachment 0).
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- 11. RADIOLOGICAL CONTROLS STRENGTHS
- Catch / containment leak control program has reduced leaks and contamination
- Improved outage support due to improved job pre-planning and more efficient use of technicians
- Reduction in personnel contaminations
- Eliminated contract HP techs for routine work
- Dosimetry system accredited by the National Voluntary 4 Accreditation Program
- Reduction in number of NRC violations from 8 in previous l
SALP period to 1 in most recent SALP period
- 94% free access to the Auxiliary Sullding CONCERNS / INITIATIVES X Radwaste volume generated exceeds national average i
} A trash segregating and sorting system was implemented i
in December to reduce the volume of compacted clean i trash.
- Radwaste volume reduction working group studied this concern, made recommendations to management and several j improvements have been or are being implemented.
Upgraded shredder / compactor equipment has been purchased which will further reduce radwaste volumes.
- Cumulative dose exposure exceeds national average i
There has been a reduction in cumulative dose for non-outage work. However, the major source of exposure i was work associated with refueling and maintenance l
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outages. A4 loop Westinghouse / ice condenser plant has more maintenance requirements than those used to calculate the national average. Efforts to increase S/G life and remove the RTO bypass system have resulted in high doses. All radiation exposure jobs were assigned to groups in the station for detailed ALARA planning, resulting in much more detailed ALARA plans. The initial results look good. A major management initiative has been taken to transfer more dose accountability to craft worker and supervision and away from HP.
Increased level of management involvement and membership l
on ALARA committee.
The accountabli of ALARA planning responsibilities
!, between HP and Maintenance Planning is being clarified.
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ll1. MAINTENANCE /SURVElLLANCE STRENGTHS:
- Increasing the use of system experts
- Valve quality group performs quality inspections on valve repairs to improve quality of work and level of experience in the field
- A self assessment of maintenance program against INPO criteria has identified items for improvement that are being completed on a priority basis.
- New vibration monitoring equipment has been purchased to expand our capacity to monitor vibration spectrum on rotating equipment
- Oil analysis program has been expanded to include many other pieces of equipment and allow for earlier detection :
1 of component wear / failure
- Developing technology to test actuators on pneumatic valves leading industry /NRC efforts to define a viable process.
!
- Implemented test failure analysis / root cause program
- Improved daily operating schedules l
- KC HX on line AP monitoring for enhanced operability monitoring CONCERNS / INITIATIVES:
l x increased number of violations due to procedural ;
non-compliance from 8 in previous SALP period to 11 in current period initiatives taken under the Plant Operations category were station wide and apply to this concern as well.
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4 I IV. EMERGENCY PREPAREDNESS STRENGTHS:
- Corrected siren activation problem with Mecklenburg County
- NRC unannounced inspection in March with no findings No violations during SALP period
- Successful annual exercises (only 2 IFI's)
- Developed new procedure for event classification to make more "user-friendly" CONCERNS / INITIATIVES:
e
" Current TSC facility is deficient j' Pursuing design / construction of new TSC facility to meet regulatory guidance criteria. Current schedule for completion is 1990. <
t V. SECURITY STRENGTHS:
- A dedicated lAE crew (CMD) to maintain security systems
- Upgrade of security barrier sizes and design
- Replacement of outdated explosion detectors and electric locks CONCERNS / INITIATIVES X Replacement / repair of CCTV cameras (A) CCTV cameras and monitors are belng replaced with state-of-art equipment.
4 (B) A temporary modification was implemented to correct the "wali effect". This was necessary due to the length of time required to design and upgrade the final modification which will be completed in mid-1989.
x Need to reduce the number of lost security badges and tailgating incidents.
Site management from all groups is working together to establish a statement of value of adherence to these requirements with a consistent corrective discipline policy throughout the company including vendors.
Daily updates are provided on the closed circuit TV system concerning numbers of security problems for tmployee awareness.
The General Employee Training video has been revised to stress the importance of security badge control.
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Data on events and groups involved is compiled, trended and provided to management for corrective action.
Neckstraps have been provided for more positive attachment of security badges.
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VI. ENGINEERING / TECHNICAL SUPPORT STRENGTHS:
- Placement of a Design Engineering office on site has l
resulted in (A) onsite problems resolution during installation of modifications i (8) onsite interpretation of design requirements / documents (C) Increased involvement in long term rotential i operability problems (i.e., NS HXs)
(D) Earlier DE involvement in station problems (i.e., '
resolution of errosion problems in S/G blowdown tank)
(E) More immediate design inspections for operating f
problems or modifications (i.e., damaged KC flex hose) ;
(F) Increased DE involvement and timeliness of ;
operability reviews i
e Topform program has increased quality of documentation and f design reviews I
- Topform program has increased the required interface with
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the station to assure a clearer understanding of station problems j
- Decreased unnecessary modification paperwork by an improved root cause analysis of problems ;
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- Very successful during last SALP period at planning l refuelings and meeting outage schedules l l
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Operator Trainina
- New site specific simulator with state-of-art technology
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- Increased simulator training time from 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> (1987) to I
40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> (1988) and then to 50-60 hours (1989) i
- Added designated simulator familiarization for non-licensed operators during requal training Implemented Training and Qualification guides and requal
, case studies
- On-shift SRO's are now rotated through training instructor slots (4 total) a
- Recent INPO re-accreditation only identified two concerns, lowest to date on eleven visits
] CONCERNS /lNITIATIVES:
x Temporary modification program has had no design review in i the past.
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modification program to provide a more thorough review of adherence to design basis and safety concerns are l being investigated and will be implemented.
X Rate of incidents and violations during refueling outages 1
is too high.
l j Corrective actions yet to be identified. Outage critique and folicw-ups will help resolve this concern.
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Vll. SAFETY ASSESSMENT / QUALITY VERIFICATION STRENGTHS:
- SITA audit on 0/G Auxiliary System
- Annual SITA audits on selected systems
- Thorough follow-up on known or potential safety concerns and industry events. Examples:
(A) Passive civil features design study (B) Fisher valve evaluation (C) Missing Missile Shield Bolts (D) Bulletin on Surry's containment sump suction line cleanliness INITIATIVE:
We are placing more emphasis and efforts in improving communications with all NRC personnel, it is our desire to be very open and responsive to all NRC concerns and provide timely and accurate information.
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0 ENCLOSURE 4 DUKE POWER COMPANY HANDOUT CATAWBA NUCLEAR STATION
o G .
- 1. PLANT OPERATIONS Concerns
- 1. Non-Conservative Approach to Tech Specs April 1987 Violation on Calibration of Power Range -
(Performance Group) (J. K. L. Q)
Pressurizer Safety Valve Position Indication -
(Individual Supervisor) (J. P. L)
Auxiliary Feedwater Flow Control Valves - Positioning Above 10% Power - (G.O. Licensing) (L. Q. K)
Channel Checks On Offscale Gauges - (Operations) (L.R)
Containment Integrity - ASME vs. Tech Spec Requirements -
(G.O. Licensing) (L. J. Q. K. S. T)
ECCS Pump Venting - Question of Interpretation -
(Industry Initiative To Remove This Spec Further Review By Ops & Station Manager.)
Counterpoints Several Tech Spec Changes Are In Tc Correct Non-Conservative Or Incorrect Data. (Licensee Identified) E.G., Airlock Testing Pressure Have Numerous Existing Interpretations And Are Working To Improve The Manual To Assist In Tech Spec Compliance.
l Catawba Is A Good Example Of A Non-Standard Plant Under Standard Tech Specs.
- 2. Back To Back Safety Iniections Unit 1 1-23-88 / Unit 2 2-9-E8 Personnel Error -
Failure To Follow Procedures (M. N. 0)
- 3. Recent Unit 2 Reactor Trips Six Unit 2 Trips In Late May-June, 1988 Counterpoint: Only : Of The o Involved Personnel Error Or i' Managenent Deficiency.
The other 4 Were Equipment Problems or Undetermined.
10 Trips on Unit 2 In This SALP:
5 Autenatic & 5 Manual 9 of The 10 Trips Involved Feedwater Transients 1 Of The 10 Trips Involved Personnel Error l t
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Plant Operations (Continued)
Strengths and Initiatives
- a. Long Unit 1 Run (144 Continuous Days) And > 90 % Capacity Factor At Start of Tube Leak Outage.
- b. NC Leakage Has Caused No Shutdowns In This SALP - Total Leakage Is Consistently < 1 GPM This Cycle - Each Unit.
- c. ESF's Reduced: 33 In This SALP Versus 47 In 8/86-7/87 Period.
- d. Total Trips Heduced: 11 In This SALP Versus 15 In 8/86-7/87 Period.
- e. Staff Developed A Professional Code of Conduct
- f. Unit 2 Steam Generator Level Modification in 1989 Refueling - Should Improve Situation On Teodwater Transients,
- g. Daily Management Plant Status Meeting
- h. Plant Labeling Program To Complete 6/89
- 1. Improved Plant Housekeeping - Particulary Unit 2 J. Involvement of Compliance in Operability Decisions
- k. Compliance Group Restructuring To Provide One or More SRO's In The Group
- 1. Pro Active Tech Spec Review / Training Using Senior Management Person.
- Ops Instructors
- SRO's
- Management -
Ops Audit
- m. Training By Section Heads To Supervisors And Crews Conducted In Operations. Performance.
Instrumentation And Electrical Construction Dept. On Procedure Use. IV. Personnel Error's,
- n. Station Manager Emphasizing The Need for Procedural Adherence And Understanding In Station Wide Letter. This Included IV.
- o. Station Management Emphasizing The Importance Of Supervisory Involvement In The Plant With His Crew.
e Plant Operations (Continued)
Strengths and initiativen
- p. Ops Supt. Or Station hgr. To Review All Compensatory Action Plans Before Iraplementation,
- q. Wider Review Of Proposed Tech Spec Interpretations ;
- r. Review Of OEP's With Training Services Management
- s. System Expert Review Of Tech Spec Interpretations
- t. Strengthening Of The G.O. As A Focal Point For NRC Communicction
- u. Prioritizing Tech Spec Change Submittals Through G.O.
Licensing To NRC I
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- 2. RADIOLOGICAL CONTROLS l
concerns ;
. Inadequate Frisking - 9/87 And 11/87 NRC Inspections !
Response /Followupt . Specific Training Provided To All t Personnel On The Problem And ,
. Single Point RCA Access Point l' Established - Monitored By HF
, . Hand And Foot Monitors !
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- . Whole Body Monitors !
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. HP Conducts Periodic Visual Surveillance l
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- Management Surveillance - Continuing l Program
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. Catawba Exposure Versus Industry Average l l .. 352 Person R M Per Unit Versus 3/1 Person Rem / Unit j i National Average }
j Strennth/ Initiatives (
) . Gansaa Spectroscopy Equipment Standardized j
. System Expert Established For MF's t t
] . Trending of Information Tor Management I
. HP Self Appraisals 1
. Solid Waste Reduction - 255 Cubic Meters is The Stations 1988 Goal. To Date. 39 Cubic Meters Have Been Generated. L r
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- 3. MAINTENANCE / SURVEILLANCE Concerns:
. Clam Incident (Programmatic)
. S/G Loose Parts - Reportability Timeliness
. Maintenance Rule Making / Maintenance Improvement c Strengths / Initiatives
- a. . Established Maintenance Engineering Services Group / Staffing (Technical Support Program)
. E.itablished System Expert Program And Have Used It For D/G Problem, trd Clam Incident.
.. P Ai.. Goals For Reducing Work Request Backlog And PM/CM Rat
_tatus"
~100 W.R.'s > 2 Years Old
~200 W.R.'s > 1 Year Old 48.2% of Outstanding W.R.'s Are < 3 Mo. Old
, Goala: 0 W.R.'s > 3 Month Old
- l < 300 Total Non-Outage Outstanding Work 1
(By 12-31-88) 2
. Recent Improvements In Violations Associated With Failuro To 1-Retest 1 Violation - 1985 1 Violation - 1986 3 Violation - 1987 1 Violation - 1988
, . Planning Organization - Traiaing, Single Pir ming Group Concept.
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, 7 4 EMERGENCY PREPAREDNESS
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Streneths/ Initiatives,
. No Violations In This SALP As Compared To 2 In Previous SALP
. Training Inprovements - Field Team Direction When In A Plume
, Uso Of Critical Parameters
- . Monthly Drills / Exercises - Since Mid 1987
- Allows Use Of Alternates
- Improves Response Skills
- Heightens Interest / Involvement
. Mado ihe TSC A "Dedicated" Facility On 8-20-87
- Allows Quicker Activation TSC Now Automatically Activated i t Alert And Site Assembly Conducted
- Cosmetic Improvements - Position Badges, Area Signs Enclosed Radio Area For HP
- Packup Radio To NC/SC
. Hoved The OSC To A Larger Facility on 6-21-88
- Located Near The Single Point Access To RCA
( - Facility Is Dedicated
- Addresses past NRC Concerns
. Emergency Vans - Now are Marked As such
- Are Under The Station Emergency Preparedness Coordinators Control
- Have Assigned Parking Near The Administration Building
- Emergency Kits On-Board At All Times
- $30,000 Upgrade In Air Monitors
. EAL Review - 3 Stations Reviewing For 4
Consistency In Classifying Eients
- Review Will Include other Utilities ,
EALs
. Additional Staffing - 1 Additional Member Added To The Station Emergency Preparedness Staff In July, 1987.
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S. SECURIT'l Concerns
. Lack Of Controls Over Safeguards Information
. Operations / Security Interface In Establishing SSF Degraded Mode
. Tailgating Strengths / Initiatives
. A Design Study Of The PAP Has Improved Badge Control
. Enhancements To The Vital Barrier Are Being Made Thru The NSM Process. HVAC Mods Are Incorporating Barriers In The Ductwork (5/8" Rebar).
. CCTV Upgrade In 1989 $300.000. Reconfiguration Of The Fence Line. More Cameras And New Orientation.
. Tactical Response Upgraded. Combat Training And Force In Force Issues To Be Addressed.
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6 ENGINEERING / TECHNICAL SUPPORT Strengths And Initiatives Desian Engineerina Onsite Design Engineering Hns On-Site Office Established April, 1988.
Use of TopForm During The Modification Program
- This Interface Is Being used For Involvement In Daily Operations Operator Training
- Onsite Simulator Operational January, 1988 Will Increase Operators Simulator Times 20 Hours / Year 1987 50 Hours / Year 1988
- On Shift SRO's Periodically Rotated Into One Of Four Training Insttvetor Slots NRC Exam Pass' Rate 9-86 And 9-87 100% Pass-Rate (26/26)
Initial Hot License 20/21 Passed Total Rate To Date 46/37 EP's Revised To Include Human Factors And Have Been Verified / Validated On The Simulator. Procedures Revised / Implemented 8-1-88.
Refuelina Activities A S Year Outage Plan Established January 1988
- Use of The Reactor Building Coordinator "P oject II" Computer Program Allows Rapid Development Of Ai, Outage Work Schedule. This Worked Well For The Present Unit 1 Tube Leak outage.
- Outage Logic Chart Improvements r
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~7. SAFETY ASSESSMENT / QUALITY VERIFICATION Concerns j i
- 1. Qualification Of The QA Staff
- 2. Quality Of Submittals Strengths / Initiatives
. Station Performance Indicator Program
.- Analysis Of ESF Events And Personnel Errors
. Followup On Bullentins, Generic Letters, f, : c .
- Fi her Valves
- West Jersey Materials
. Passive Civil Features Design Study
. Reduction In Outstanding NRC Commitments (129 8-1-88 Ver.=us 195 8-1-87.)