ML20214M310
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Letter Sequence Approval | |
|---|---|
Initiation
Administration Results Other: ML20135D986, ML20207R745, ML20210D696, ML20210T949, ML20210T980, ML20210U020, ML20210U168, ML20211G851, ML20214W928, ML20214W946, ML20215C373, ML20215C402, ML20215C422 | |
MONTHYEARML20210U1681984-04-0404 April 1984
[Table View]Changes 0 to 0 of PT/0/A/4150/11A, Control Rod Worth Measurement:Rod Swap Project stage: Other ML20210T9801984-04-26026 April 1984 Changes 0 to 3 of PT/0/A/4150/11, Control Rod Worth Measurement Project stage: Other ML20215C4021985-08-28028 August 1985 Forwards DPC-NE-1003, Rod Swap Methodology Rept for Startup Physics Testing Project stage: Other ML20215C4221985-08-31031 August 1985 Rod Swap Methodology Rept for Startup Physics Testing Project stage: Other ML20135D9861985-09-10010 September 1985 Forwards Summary of Review Criteria Evaluations,Per WCAP-9863-A, Rod Bank Worth Measurement Utilizing Bank Exchange & Ser.On 850626,measured 12.5% Below Predicted Value.No Safety Analysis Input Assumptions Effected Project stage: Other ML20210D6961986-09-15015 September 1986 Informs of Results of Cycle 3 Startup Physics Tests Conducted Using Method Described in, Rod Bank Worth Measurement Utilizing Bank Exchange. Ref Bank,Shutdown C, Worth Measured 14% Below Predicted Value Project stage: Other ML20215C3731986-10-0101 October 1986 Forwards Forwarding Rept Re Rod Swap Methodology, Which Was Never Docketed.Info Not Revised in Any Way, Submitted for Docketing Purposes Only Project stage: Other ML20197C6821986-10-30030 October 1986 Forwards Response to 860530 Request for Addl Info Necessary for Preparation of SER Supporting Plant Restart. Instrumentation & Control Sys & non-nuclear Instrumentation Schematic Drawings Will Be Sent Separately Project stage: Request ML20214W9281986-12-0404 December 1986 Forwards Rev 1 to DPC-NE-1003, Rod Swap Methodology Rept for Startup Physics Testing Project stage: Other ML20214W9461986-12-31031 December 1986 Rev 1 to DPC-NE-1003, Rod Swap Methodology Rept for Startup Physics Testing Project stage: Other ML20207N2931987-01-12012 January 1987 Forwards Request for Addl Info to Complete Review of DPC-NE-1103, Rod Swap Methodology Rept for Startup Physics Testing. Info Required within 30 Days to Meet Review Completion Prior to Approval of Plant Reloads Project stage: RAI ML20213A5551987-01-28028 January 1987 Requests Remittance of Application Fee for Review of Rod Swap Methodology Rept for Startup Physics Testing Project stage: Approval ML20210U0201987-01-29029 January 1987 Changes 0 to 5 of PT/0/A/4150/11A, Control Rod Worth Measurement:Rod Swap Project stage: Other ML20210T9491987-01-29029 January 1987 Changes 0 to 31 of PT/0/A/4150/21, Post-Refueling Controlling Procedure for Criticality,Zero Power Physics & Power Escalation Testing Project stage: Other ML20210T8691987-02-11011 February 1987 Forwards Response to NRC 870112 Request for Addl Info Re Determination of Rod Worth Using Rod Swap Methodology. Methodology Described in 861204 Submittal Will Be Used for 870501 Reloads of Plants Project stage: Request ML20211G8511987-02-16016 February 1987 Comments on D Hood Re 14.5% Discrepancy Between Predicted & Measured Worths of Ref Bank of Unit 2,Cycle 3. Caused by Shortcomings in Measurement Technique.Procedure Used to Measure Rod Worths Will Be Revised Project stage: Other ML20207R7451987-03-11011 March 1987 Forwards Revised Responses to Questions 6 & 7 Re Determination of Rod Worth Using Rod Swap Methodology,Per Ds Hood 870112 Request & 870219 & 0310 Telcons Between Ds Hood & SA Gewehr Project stage: Other ML20214M3101987-05-22022 May 1987 Forwards SER Based on Review of Rod Swap Methodology Rept for Startup Physics Testing & 870211 & 0311 Supplemental Info.Rod Swap Methodology Acceptable for Rod Worth Measurement of Reload Cores for Plants Project stage: Approval ML20214M3361987-05-22022 May 1987 Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics Testing Project stage: Approval 1986-12-04 |
| ML20214M310 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 05/22/1987 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| Shared Package | |
| ML20214M313 | List: |
| References | |
| TAC-62981, TAC-62982, TAC-62983, TAC-62984, NUDOCS 8706010265 | |
| Download: ML20214M310 (1) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H5811999-10-15015 October 1999
[Table view]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 Category:NRC TO UTILITY MONTHYEARML20058J1251990-11-13013 November 1990
[Table view]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 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217F8011999-10-13013 October 1999
[Table view]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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a 1 Docket Nos.: 50-369, 50-370 50-413, 50-414 i
i Mr. H. B. Tucker, Vice President j Nuclear Production Department i Duke Power Company MAY 2 2 W -
422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Tucker:
Subject:
R0D SWAP METHODOLOGY REPORT FOR STARTUP PHYSICS TESTING, l MCGUIRE AND CATAWBA NUCLEAR STATIONS, UNITS 1 AND 2 .
1
-(TACs62981,62982,62983,62984) i 1
By letter ' dated December 4,1986, you submitted a report titled " Rod Swap Methodology Report for Startup Physics Testing," and you submitted additional infonnation by letters dated February 11 and March 11, 1987. In addition, ,
j telephone discussions were held on May 1,1987 with members of your company
- regarding conditions associated with our approval.
j We have reviewed the material submitted and find the rod swap methodology as
! described to be acceptable for rod worth measurement of reloaded cores for
{ McGuire and Catawba Stations, Units 1 and 2. This approval recognizes your
{ prior agreement to certain conditions listed in our enclosed Safety Evaluation l Report.
I Should you have any questions regarding the enclosure, contact me at '
(301)492-8961 or K. Jabbour at (301) 492-7367. In any future correspondence !
4 regarding this approval, please include a reference to TACs 62981, 62982, 62983
) and 62984.
i j Sincerely, j Darl Hood, Project Manager Project Directorate II-3 Division of Reactor Projects I/II
Enclosure:
Safety Evaluation Report 1
I cc w/enci 60g g g j See next page
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