Letter Sequence Other |
---|
|
|
MONTHYEARML20128C2491993-01-28028 January 1993 Requests Addl Info Re Proposed Methodology for Analysis of Primary Coolant Loops at Plant for Steam Generator Replacement Project stage: Other 1993-01-28
[Table View] |
|
---|
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 ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 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 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 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 ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 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 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 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 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 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 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 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 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 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 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 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station 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 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 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 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 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 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 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 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 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:OUTGOING CORRESPONDENCE
MONTHYEARML20217F8231999-10-13013 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20207C7761999-05-19019 May 1999 Informs That on 990618,NRC Will Meet with Mgt of Duke Energy Corp to Discuss Performance of Catawba Facility & Extends Invitation to Attend Meeting as Observer 1999-09-24
[Table view] |
Text
- _ - - _ - - _ . - _ _ _ _ __ _ _____ -- --__ _ - _ _ _ _ _ - _ _ - _ _ _ _ _ - _ _--__. __-- ___ _ _ _ _ _ _ - _ - _ .
January 28, 1993
)
Docket Nos. 50-369, 50-370 2 and 50-413 4
Mr. D. L. Rehn l General Manager, Nuclear Services !
l Duke Power Company P. O. Box 1007 Charlotte, North Carolina 28201-1007 i
Dear Mr. Rehn:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - METHODOLOGY FOR ANALYSIS OF PRIMARY COOLANT LOOPS FOR STEAM GENERATOR REPLACEMENT FOR MCGUIRE UNITS 1 AND 2, AND CATAWBA UNIT I (TAC HOS. M84736/M84737/M84738)
The NRC staf f is reviewing Duke Power Company's sut,mittals of October 15 and November 13, 1992, regarding the proposed methodology for the analysis of the primary coolant loops at McGuire Units I and 2, and Catawba Unit I for steam generator replacement. We find that we need additional information in order to complete our review. Accordingly, please respond to the questions identified in the enclosure, if you have any questions concerning this request, please contact me at (301) 504-1479.
This request affects fewer than ten respondents and is, therefore, not subject to Office of Management & Budget review under P.L.96-511.
Sincerely,
/s/
Timothy A. Reed, Project Manager Project Directorate 11-3 Division of Reactor Projects-l/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure: DJ1TRIBU"10Ei RPichumani, 7H15-See next page IDocket e le a LVarga NRC & Local PDRs Glainas PDil-3 R/F EJordan, MNBB3701 McGuire R/F OGC, 15B18 Catawba R/F EMerschoff, RII LBerry DMatthews Treed RMartin K L_
0FC PDII-3:;t[L PQ h ii D:PKilk[
NAM LBerry k TRYebcw- DMaMe'ws DATE
(/N93_ l/h/93 JJ$/93
. DOCUMENT NAME: G:\MCGUIRE\84736.RAI n9002G
~ r
~' ~
yao2oaggg3%8hab A i i
-PDR PDR 'fdi 1 P ,
l
'9, UNITED STATES
((
g J
NUCLEAR REGULAT0l'Y COMMISSION W ASHINGTON, O. C. 30666
% January 28, 1993 Docket Nos. 50-369, 50-370 and 50-413 ,
Mr. D. L. Rehn General Manager, Nuclear Services ,
Duke Power Company .
P. O. Box 1007 '
Charlotte, North Carolina 28201-1007
Dear Mr. Rehn:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - METHODOLOGY FOR ANALYSIS OF PRIMARY COOLANT LOOPS FOR STEAM GENERATOR REPLACEMENT FOR MCGUIRE UNITS 1 AND 2, AND CATAWBA UNIT 1 (TAC NOS. M84736/M84737/M84738)-
The NRC staff is reviewing Duke Power Company's submittals of October 15 and November 13 1992,.regarding the proposed methodology for the analysis of the primary coolant loops .at McGuire jnits 1 and 2, and Catawba Unit l~ for steam generator replacement. We find that we need additional information in order to complete our review. Accordingly, please respond to the questions ,
identified in the enclosure, if you have any questions concerning this request, please contact me at (301) 504-1479.
This request affects fewer than ten respondents.and is, therefore, not subject to Office of Management & Budget review under P.L.96-511.
Sincerely, a
imothy A. Reed, Project Manager Project Directorate 11-3 Division of Reactor Projects-1/II Office of Nucisar Reactor Regulation- ,-
rnclosure:
Request for Additional Information cc w/ enclosure:
See next page 0 -
- a. :,
D Duke Power Company Catawba Nuclear Station McGuire Nuclear Station cc:
Mr. R. C. Futrell Mr. Alan R. Herdt, Chief Regulatory Compliance Manager Project Branch #3 Ouke Power Company V. S. Nuclear Regulatory Commission a800 Concord Road 101 Marietta Street, NW Suite 2900' York, South Carolina 29745 Atlanta, Georgia 30323 A. V. Carr, Esquire North Carolina Electric Membership Duke Power Company Corporation 422 South Church Street P. 0. Box 27306 Charlotte, North Carolina 28242 Raleigh, North Carolina 27611 J. Michael McGarry, !!!, Esquiro Saluda River Electric Cooperative, i Winston and Strawn Inc.
1400 L Street, NW. P. O. Box 929 Washington, DC 20005 Laurens, South Carolina 29360 North Carolina MPA-1 Senior Resident inspector Suite 600 Route 2 Box 179N P. O. Box 29513 York, South Carolina .29745 Raleigh, North Carolina 27626 ~
Regional Administrator,-Region !!
Mr. T. Richard Puryear U.S. Nuclear Regulatory Commission. 7 Nuclear Technical Services Manager 101 Marietta Street, NW Suite ?900 Carolinas District Atlanta, Georgia 30323 Westinghouse Electric Corporation P. O. Box 32817 Mr. Heyward G. Shealy, Chief Charlotte, North Carolina 28232 Bureau of Radiological Health South Carolina Department of Health-County Manager of York County and Environmental Control York County Courthouse 2600 Bull Street York, South Carolina 29745 Columbia,-South Carolina' 29201 Richard P. Wilson, Esquire Ms. Karen E. Long' Assistant Attorney General Assistant Attorney General' __
SC Attorney General's Office North Carolina Department of Justice P. O. Box 11549 P. O. Box 629~-
Columbia, South Carolina 29211- Raleigh,'. North Carolina 27602
- Piedmont Municipal Power Agency Mr. G. A. Copp-121 Village Drive Licensing --EC050 Greer, South Carolina 29651 Duke Power Company-P. 0 Box 1006 Charlotte, North Carolina 28201-1006- -
n 1 f w ~
w
r
/ J, e
Duke Power Compary Catawba Nuclear Station McGuire Nuclear Station Cc:
Dr. John M. Barry Mr. M. S. Tuckman Mecklenburg County Vice President, Catawba Site Department of Environmental Duke Power Company Protection 4800 Concord Road 700 N Tryon Street York, South Carolina 29745 Charlotte, North Carolina 29202 Mr. T. C. McHeekin County Manager of Mecklenburg County Vice President, McGuire Site 720 East Fourth Street Duke Power Company Charlotte, North Carolina 28202 12700 Hagers Ferry Road Huntersville, North Carolina 28078 Mr. Robert O. Sharp Compliance Duke Power Company McGuire Nuclear Site 12700 Hagers Ferry Road Huntersville, North Carolina 28078 Senior Resident inspector c/o U.S. Nuclear Regulatory Commission 12700 Hagers Ferry Road Huntersville, North Carolina 28078 Mr. Dayne H. Brown, Director Department of Environmental Health and Natural Resources Division of Radiation Protection P. O. Box 27607 Raleigh, North Carolina 27611
d i
, .f L .
ENCLOSURE Request for Additional Information McGuire 1/2 and Catawba 1 ,
Methodology for Analysis of Primary. Coolant Loops for steam Generator Replacement (SGR).
1 In the May 17, 1990, safety evaluation report methodology (DGH) used for generating floor son res(SER) of the
=e spectra (FF.5)direct for generation the snubber reduction program at Catawba 1 and 2, t1e .4RC staff approved, after ',
extensive discussions with Duke Power Company (DPC), the use of a composite-- :
ground response spectrum (GRS) as in)ut for generating the FRS utilizing _ an_
appropriate DGM (Reference 1). In t1e same SER, the. staff also approved the-use of a computer program called EDASP for DGM.- In response to a question-(raised by the staff during a teleconference on October 28,1992), DPC stated that it will generate the new FRS using either the time history method or the DGM as permitted in Section 3.7 of the FSAR.
- 1. DPC should clarify if it intends to use, in the SGR project at Catawba 1, the same composite GRS and the DGM that were approved for the snubber reduction program at Catawba 1 and 2 in the May 17, 1990, SER cited above; if not, DPC should furnish the details of the GRS and the analysis procedure it will use for generating the FRS for the SGR project at Catawba 1. In order to expedite the resolution.of this-issue, DPC is advised to review all of its submittals and the staff's review comments and additional information requests on-its application for the snubber reduction program at Catawba 1 and 2, and provide detailed information on the two related issues, namely, the GRS and the analysis procedure used.
- 2. Similarly, furnish the details of the GRS and the analysis procedure that will be used for the SGR project at McGuire 1 and 2.
Referenggn
- 1. Letter from K. N. Jabbour, NRC, to 't. B. Tucker, DPC, dated May 17, 1990, " Safety Evaluation of Direct Generation Method of Generating Floor Response Spectra for the Snubber Reduction Program ---Catawba > '
Nuclear Station, Units 1 and 2".