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Category:CORRESPONDENCE-LETTERS
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 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 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 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 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 ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 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 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 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 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 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 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 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 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 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 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 ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl 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 ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages 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 ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units 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 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 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual 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 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach 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 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 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H0041999-10-13013 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 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 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 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 ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 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 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 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 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 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 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 ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20196E9541999-06-18018 June 1999 Forwards SG Tube Insp Conducted During Unit 1 End of Cycle 11 Refueling Outage.Attachments 1,2,3 & 4 Identify Tubes with Imperfections in SGs A,B,C & D,Respectively ML20195K4571999-06-14014 June 1999 Forwards MORs for May 1999 & Revised MORs for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20195J1691999-06-10010 June 1999 Forwards Written Documentation of Background & Technical Info Supporting Catawba Unit 1,notice of Enforcement Discretion Request Re TS 3.5.2 (ECCS-Operating),TS 3.7.12 (Auxiliary Bldg Filtered Ventilation Exhaust Sys) ML20217G5771999-06-0909 June 1999 Forwards Post Exam Comments & Supporting Reference Matls for Written Exams Administered at Catawba Nuclear Station on 990603 05000414/LER-1999-002, Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 9907081999-06-0303 June 1999 Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 990708 ML20207F2381999-06-0101 June 1999 Forwards Copy of Catawba Nuclear Station Units 1 & 2 1998 10CFR50.59 Rept, for NRC Files ML20195J1131999-05-26026 May 1999 Requests Approval to Change Cycle Dates for Two Year Requalification Training Program Required by 10CFR55.59,to Improve Scheduling of Requalification Exams to non-outage Periods 05000413/LER-1999-007, Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section1999-05-26026 May 1999 Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section ML20195B4751999-05-24024 May 1999 Forwards Rev 7 to UFSAR Chapter 2 & Chapter 3 from 1998 UFSAR for Catawba Nuclear Station.List of Instructions on Insertion Encl ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers 05000413/LER-1997-009, Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept1999-05-17017 May 1999 Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R1721999-05-13013 May 1999 Forwards Monthly Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 ML20206T0281999-05-12012 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual. Document Constitutes Chapter 16 of UFSAR 05000413/LER-1999-006, Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 9906071999-05-10010 May 1999 Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 990607 ML20206N8201999-05-10010 May 1999 Forwards Revs 15 & 16 to Catawba Unit 1 Cycle 12 COLR, Per TS 5.6.5.Rev 15 Updates Limits for New Catawba 1 Cycle 12 Reload Core & Rev 16 Revises Values Re Min Boron Concentrations for Rwst,Cla & SFP ML20206J4431999-05-0303 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e).Document Constitutes Chapter 16 of UFSAR ML20206D2141999-04-29029 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Catawba Nuclear Station,Units 1 & 2, Per Plant TS 5.6.3. Rept Contains Listed Documents ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5491990-09-14014 September 1990 Forwards Proprietary Response to Question Re Scope of Review of Topical Rept, Safety Analysis Physics Parameter & Multidimensional Reactor Transients Methodology, Per & 900723 Meeting.Response Withheld ML20059L5521990-09-14014 September 1990 Forwards Response to 18 Questions Re Topical Rept DPC-NE-2004,per NRC 900802 Request for Addl Info.Encl Withheld (Ref 10CFR2.790) ML20059K2021990-09-12012 September 1990 Submits Supplemental Response to Generic Ltr 89-14, Svc Water Sys Problems Affecting Safety-Related Equipment. Intake Structure Insp Program Developed.Procedures for Insp Implemented & Intake Structures Sampled & Analyzed ML20064A8041990-09-0505 September 1990 Notifies NRC of Mod to 890301 Response to Violations Noted in Insp Repts 50-413/86-18-01 & 50-414/86-18-01 Re Valves. All Valve Locking Mechanisms Would Be Installed by End of Unit 2 Refueling Outage (Approx Aug 1990) ML20064A5741990-09-0404 September 1990 Discusses Re Info to Support Util Position Relative to Resolving Issue of Main Steam Line Breaks Inside Ice Condenser Containments & Requests That Info Be Withheld (Ref 10CFR2.790) ML20059G3011990-09-0404 September 1990 Forwards Response to NRC 900327 Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20059G8321990-08-30030 August 1990 Withdraws 880726 Proposed Tech Spec Change,Clarifying Tech Spec 3/4.7.6 Re Emergency Power Requirements for Control Room Ventilation Sys ML20059D2011990-08-27027 August 1990 Forwards Piedmont Municipal Power Agency , Authorizing Use of Annual Rept for NRC Docket Requirements ML20059D2441990-08-24024 August 1990 Forwards Special Rept PIR-1-C90-0261 on 900725 Re Cathodic Protection Sys Failure to Pass Acceptance Criteria of 60-day Surveillance.Std Work Request Generated to Check Voltage Potential at Test Station TS-36 on Weekly Basis ML20056B4981990-08-22022 August 1990 Responds to NRC Request for Addl Info Re General Relief Request for Pump Vibration Submitted 900315.Relief Request Changed to Insure Data Taken Over Range That Encompasses All Main Potential Noise Contributors ML20056B5011990-08-22022 August 1990 Responds to Violation Noted in Insp Repts 50-413/90-17 & 50-414/90-17.Corrective Actions:Review Will Be Conducted to Determine Category of Infrequently Run Procedures Needing Addl Verification Controls ML16259A2391990-08-22022 August 1990 Forwards Public Version of Rev 27 to Company Crisis Mgt Implementing Procedure CMIP-2, News Group Plan. W/ Dh Grimsley 900906 Release Memo ML20056B4971990-08-20020 August 1990 Clarifies Info Submitted in 871207 & s Re Steam Generator Tube Rupture Analysis Demonstration Runs. Demonstration Runs Met plant-specific Requirements in Section D to NRC SER on WCAP-10698 ML20059C1201990-08-20020 August 1990 Forwards Rept Summarizing Util Findings Re Three False Negative Blind Performance Urine Drug Screens Which Occurred During Jan & Feb 1990.Recommends That NRC Consider Generic Communication to Clearly State Reporting Requirement ML20059B6581990-08-17017 August 1990 Responds to Violation Noted in Insp Repts 50-413/90-15 & 50-414/90-15.Corrective Actions:Present Methods of Testing Operability of CO2 Fire Protection Sys Will Be Evaluated by 910201 to Determine If Addl Testing Necessary ML20059C1591990-08-17017 August 1990 Suppls by Providing Addl Info to Support Util Position Re Anl Confirmatory Analysis of Main Steamline Breaks in Ice Condenser Plants.Encl Withheld ML20063Q0951990-08-15015 August 1990 Forwards Monthly Operating Rept for Jul 1990 for Catawba Nuclear Station Units 1 & 2 & Revised Rept for June 1990 ML20059C1231990-08-15015 August 1990 Advises That Util Submitting Special Rept Re Valid Failure of Diesel Generator 2B Would Be Delayed Until 880229 Had Incorrect Ltr Date.Date of Ltr Should Have Been 880204 Instead of 880104.Corrected Ltr Encl ML20063Q2671990-08-14014 August 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8 & Rev 35 to CMIP-9.W/DH Grimsley 900821 Release Memo ML20059C2211990-08-13013 August 1990 Forwards Revised Chapter 16, Selected Licensee Commitments Manual, to Plant Updated Fsar,Per 10CFR50.4 & 50.71.Manual Contains Commitments Which Require Control But Not Appropriate in Tech Specs ML20063Q0261990-08-10010 August 1990 Forwards Rev 0 to Catawba Unit 2 Cycle 4 Core Operating Limits Rept, Per Tech Spec 6.9.1.9 ML20063Q0671990-08-10010 August 1990 Submits Revised Response to Violations Noted in Insp Rept 50-413/90-09.Procedure to Verify Test Inputs Modified to Verify Dummy Input Signal to Channel RTD Circuit ML20058N0181990-08-0808 August 1990 Forwards Response to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20081E1601990-08-0101 August 1990 Advises of Completion of 900330 Commitment Re Standing Work Request for Insp of Air Flow Monitors & Dampers,Per Violations Noted in Insp Rept 50-413/90-03 & 50-414/90-03 ML20058P3261990-08-0101 August 1990 Forwards Public Version of Rev 26 to Station Directive 3.8.4, Onsite Emergency Organization ML20081E0951990-07-27027 July 1990 Forwards Decommissioning Financial Assurance Certification Rept for Duke Power Co,co-owner of Catawba Nuclear Station Units 1 & 2 ML20055H9741990-07-26026 July 1990 Forwards end-of-cycle 3 Steam Generator Insp Rept.Nineteen Tubes Removed from Svc by Plugging W/Rolled Mechanical Plug ML20055H5231990-07-24024 July 1990 Discusses co-licensee Relationship & Obligations Re Decommissioning Financial Assurance for Facilities ML20055H4571990-07-19019 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-413/90-11 & 50-414/90-11.Corrective actions:I-beams/ Hoists Rolled to Ends of Ice Condenser & Securely Located on Rails to Prevent Any Movement ML20055H1741990-07-18018 July 1990 Withdraws 880527 & 0725 Amends Clarifying Requirements for Containment Pressure Control Sys ML20055J3441990-07-17017 July 1990 Advises That Commitment Re Procedure IP/O/A/3190/01,per Violation in Insp Repts 50-413/90-06 & 50-414/90-06, Completed on 900619 ML20055H4131990-07-16016 July 1990 Forwards Public Version of Epips,Including RP/0/A/5000/07 & HP/0/B/1009/04 ML20055F8991990-07-13013 July 1990 Forwards Monthly Repts for June 1990 for Catawba Nuclear Station Units 1 & 2 & Operating Status Rept for May 1990 ML20055G2311990-07-13013 July 1990 Withdraws 880311 Proposed Amend to Tech Spec Table 3.3-3, Item 8.f Re Number of Instrumentation Channels Associated W/ Main Feedwater Pumps.Util Determined That Change Unnecessary ML20055F8461990-07-12012 July 1990 Requests 14-day Extension Until 900802 to Submit LER 414/90-010 to Investigate Power Supply Realignment ML20058P1231990-07-0707 July 1990 Advises That Commitment to Revise Maint Mgt Procedure 1.12 to Include Functional Verification Requirements & to Develop Retest Manual to Address Retest Requirements for Any Maint Performed on Components Completed on 900614 ML20055F4131990-07-0505 July 1990 Forwards Inservice Insp Rept Unit 1 Catawba 1990 Refueling Outage 4, Per 10CFR50.55(a)(q) & Tech Spec 4.0.5.Insp Performed Per Section XI of ASME Boiler & Pressure Vessel Code & Applicable Addenda ML20055D4291990-06-29029 June 1990 Supplemental Response to Violations Noted in Insp Repts 50-413/89-13 & 50-414/89-13,per .Personnel Responsible for Maintaining Crisis Mgt Ctr Drawing Trained. Util Will Continue to Evaluate Changes Made to Program ML20055E2191990-06-29029 June 1990 Submits Revised Commitment Dates Re Implementation of Dept Guidance on post-maint Testing,Per Commitment Made in 891002 Response to Violations in Insp Repts 50-413/89-19 & 50-414/89-19.Completion Date Changed to 900701 ML20044B0621990-06-26026 June 1990 Forwards Public Version of Revised EPIP HP/0/B/1009/05, Personnel/Vehicle Monitoring for Emergency Conditions. W/Dh Grimsley 900716 Release Memo ML20043H6921990-06-18018 June 1990 Advises of Revised Completion Date for VA Ductwork Cleaning to 901231,per Insp Repts 50-413/90-03 & 50-414/90-03. Vendor Personnel Assigned to Task Unavailable to Complete Cleaning Until Late 1990 Due to Outage Support Needs ML20043G1691990-06-15015 June 1990 Forwards Monthly Operating Repts for May 1990 for Catawba Nuclear Station,Units 1 & 2 & Corrected Monthly Operating Repts for Apr 1990 Re Personnel Exposure ML20055C8041990-06-15015 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-413/90-10 & 50-414/90-10.Corrective Actions:Instrument Root Valves Unisolated & Analog Channel Operational Tests for Low Temp Overpressure Protection Completed ML20043G4331990-06-13013 June 1990 Withdraws 900423 Proposed Amend to Tech Spec 4.6.1.8 Re Lab Test of Carbon Samples from Annulus Ventilation Sys ML20043G3771990-06-13013 June 1990 Withdraws 900423 Proposed Amend to Tech Spec 4.7.7 Which Required That Lab Test of Carbon Samples from Auxiliary Bldg Filtered Exhaust Sys Be Tested for Methyl Iodide Penetration of 0.71% ML20043G2511990-06-12012 June 1990 Withdraws 900419 Suppl to 871221 Application for Amends to Licenses NPF-35 & NPF-32 Re Tech Specs 4.7.6 Re Control Room Area Ventilation Surveillance Requirements ML20043G1741990-06-0707 June 1990 Responds to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire. Correct RCS Operating Pressure Would Be 2,250 Psia as Identified in Table 3-1 ML20043G3451990-06-0707 June 1990 Forwards Proprietary Response to Request for Addl Info Re Topical Rept BAW-10174, Mark-BW Reload Safety Analysis for Catawba & Mcguire. Response Withheld ML20043G0721990-06-0707 June 1990 Responds to NRC 900510 Ltr Re Violations Noted in Insp Repts 50-413/90-09 & 50-414/90-09.Corrective Actions:Vc/Yc Train a Returned to Svc W/Supply Power from 2ETA.Terminal Box 1TB0X0346 Inspected & Insured Operable ML20043F6111990-06-0606 June 1990 Advises That Response to Request for Addl Info Re Operator Response Times During Simulated Steam Generator Tube Rupture at Facility,Will Be Delayed Until 900630 1990-09-05
[Table view] |
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DUKE POWER COMPANY Powen 11cu.nswo 422 Sourn Cnuncu Srazer. Cauntorre, N. C.asa4a .
WIL LI A M O. PA R M ER, J R.
Vice Petsiors, itLtewoht:AntA 704 s'ca= Peooucoa April 2, 1982 37 3-4o s 3 Mr. Harold R. Denton, Director -
Office of Nuclear Reactor Regulation f /
U. S. Nuclear Regulatory Commission e o M x3 Washington, D. C. 20555 ,
%gt h ;; j VJ ig Attention: Ms. E. G. Adensam, Chief g ((! N gi- Yh I!i
- T Licensing Branch No. 4 - =
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Re: Catawba Nuclear Station g Docket Nos. 50-413 and 50-414
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Dear Mr. Denton:
Elinor G. Adensam's letter of March 8, 1982 requested additional information related to the storage of non-Catawba fuel at the Catawba Nuclear Station.
Attached are responses to these questions with the exception of questions 6 and 10c, which will be provided by May 7,1982.
V y truly yours, q
., e,.u r c -
William O. Parker, Jr.
ROS/php Attachment l
cc: J. P. O'Reilly l
P. K. Van Doorn R. Guild Palmetto Alliance J. L. Riley H. Presler TzoOl t' s/,i 8204120280 820402 PDR ADOCK 05000 A
a n 2 - S.-
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Duke Power Company Catawba Nuclear Station Response to Elinor G. Adensam's Letter of 3/8/82 The following responses are based on the current spent fuel storage capacity of the Duke system plus firmly planned expansions and additions thereof. The current Duke system includes poison storage racks at Oconee 1, 2 and high density storage racks at Oconee 3, McGuire 1 and McGuire 2. Firmly planned additions are the Catawba pools with high density racks. The only firm expansion planned at this time is a poison reracking of the Oconee 3 pool.
- 1. In the FSAR, you have considered a plan to store irradiated fuel assemblies from Oconee, Unit Nos. 1, 2, and 3, and from McGuire, Unit Nos. 1 and 2.
a) Is Duke considering plans to store irradiated fuel assemblies from facilities other.than Oconee or McGuire?
b) If answer to (a) is yes,- does Duke's present application include request for authority to store irradiated fuel assemblies from facilities other than Oconee and McGuire?
c) What is the earliest date that Duke is considering commencement of shipment of irradiated fuel assemblies from Oconee and McGuire to Catawba and storage thereof at Catawba?
Response
a) Duke is not considering plans to store irradiated fuel assemblies from facilities other than Oconee or McGuire.
b) N/A c) Based on current spent fuel storage planning, the earliest date that Duke would consider commencement of shipment of irradiated i
fuel assemblies from Oconee and McGuire to Catawba is March, 1987.
These first shipments would come from McGuire based on a FCR loss j date of 3/88. Shipments from Oconee would commence in March, 1991 based on a FCR loss date of 3/90. Events occurring at McGuire or Oconee which would reduce available storage at those sites could advance these dates.
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- 2. a) What is the minimum storage time prior to the shipment of spent fuel assemblies to Catawba from the Oconee and McGuire Stations?
b) Provide the technical specification that will limit .the spent
, fuel capacity in the spent fuel pools at Catawba, Unit Nos. 1 and 2.
! How much space will be reserved for a complete core defueling from i Catawba, for other core components, and for fuel assemblies from the Oconee and McGuire Stations? How much additional space will be provided for spent fuel casks from other Duke facilities?
l Response:
a) Should spent fuel assemblies be transferred from Oconee and McGuire to Catawba, the minimum cooling time of those assemblies will be 5 years.
b) The Catawba Technical Specification limiting spcnt fuel storage capacity will be in accordance with Specification 5.6.3 of NUREG-0452, Rev. 4, " Standard Technical Specifications for Westinghouse Pressurized Water Reactors." The spent fuel storage capacity will be limited to 1418 assemblies per unit as discussed in FSAR Section 9.1.2.2. One (1) full core reserve of 193 assemblies will be reserved at the Catawba Nuclear Station. No actual storage space will be reserved for the storage of non-fuel core components.
- Although no specific storage locations will be reserved for non-l Catawba fuel, the maximum number of assemblies from Oconee and l
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McGuire that would be stored in Catawba's present storage racks will be 896 and 957, respectively, the combined total of which will not exceed 1437 assemblies. No additional space will be provided j for spent fuel casks from other Duke facilities.
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- 3. a) What is the maximum number of spent fuel assemblies per year and the maximum number of shipments per year that will be transferred from Oconee and McGuire stations to Catawba? Will they be shipped by truck, rail or barge?
b) What is the estimated water temperature in the spent fuel pool due to the schedule proposed in your response to 3a above?
c) What is the average weight of UO 2 in e ch fuel assembly from the Oconce and McGuire Stations?
c) What is the average irradiation level (burnup) of the spent fuel to be shipped to Catawba?
e) What additional amount of solid radwaste will be generated at Catawba as a result of this alternate plan?
f) Will failed fuel assemblics be shipped from the Oconee or McGuire Stations to be stored in the Catawba spent fuel pools?
Response
a) The spent fuel shipment commencement dates given in Ic above would require the transfer of at least 10 to 12 assemblies per month from each station; however, due to scheduling conflicts that might inter-fere with the shipments, there might be periods of time that would require a faster rate of shipments. It is anticipated, therefore, that the maximum number of asuemblies shipped in one month could be as much as 25 from each station or an annual total of 300 from each station. Assuming the use of a single element truck cask, the maximum number of shipments per year would be 300 from each station.
Shipments from Oconee would be by truck. Shipments from McGuire would be by truck and/or rail, b) Due to the relatively low heat content of a McGuire/Oconee fuel assembly that might be transferred to Catawba (5 years cooled), the maximum water temperature of the Catawba spent fuel pools will not be significantly affected relative to the option of storing only Catawba fuel in the Catawba pools. Liner plate material limitations prohibit bulk pool water temperatures from exceeding 150 F; however, normal operating temperatures of the pools with spent fuel from Oconee and McGuire as described above will be much lower.
c) The average weight of UO2in each Oconce fuel assembly is about 1159 pounds. Each McGuire assembly contains about 1155 pounds of UO2 '
- 3. Response (cont'd) d) The average burnup of Oconee fuel assemblies which might be shipped to Catawba would be about 26.03 MWD /KgU. The fuel which might be shipped from McGuire would have an average burnup of about 24.97 MWD /KgU.
e) The additional amount of solid radwaste generated as a result of spent fuel shipments would be approximately one cubic foot per shipment. This material will consist mainly of H.P. related supplies such as swipes, clothing and decontamination water filters, f) Any fuel assemblies showing evidence of rod failure will remain at the site from which they were generated.
- 4. Duke Power Company is presently considering spent fuel rod consolidation at Oconce. Provide your plan for possible future use of the Catawba spent fuel pools for storage of consolidated fuel assemblies from Oconee, McGuire, or Catawba.
Restense:
Duke has no plans at this time for use of the Catawba spent fuel pools for storage of compacted (consolidated) assemblies from Oconec, McGuire or Catawba. Future use of Catawba pools for this purpose would depend upon need for additional storage, development and approval of compaction tech-nology, availability of alternative storage options, licensing considera-tions and cost, a
- 5. Provide the nominal value of the effective multiplication factor of the racks and the uncertainty to be added to this value due to the storage of non-Catawba irradiated fuel at Catawba.
Response
Criticality calculations performed on the Catawba fuel storage racks included the conservative assumption that all fuel stored in the racks was fresh, j unirradiated fuel. This resulted in an effective multiplication factor of less than 0.95. Since all non-Catawba fuel that would be stored at Catawba would be irradiated to enrichment levels below that of Catawba fresh fuel, no uncertainties will be added to the nominal value for Keff as obtained in the original criticality calculations. Thus, the assessment set out in the Catawba FSAR is the bounding situation.
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- 6. Provide the verification results of the KENO Code used. This should include a description of the experiments which were calculated and the bias and standard deviation of the calculational results. It should be noted that the KENO code was not previously approved by the NRC.
Response
Detailed calculational results, benchmarking results, and documentation of the procedures used for the Catawba fuel storage racks criticality calculations will be provided by May 7, 1982.
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- 7. The Oconee fuel assemblies which may be stored in Catawba racks are 15 x 15 rather than 17 x 17 assemblies. For the same enrichment there may be small differences between these and the optimized Westinghouse design. Provide a discussion of such differences.
Response
Other than the actual number of rods in the fuel assembly the only other significant difference between the two types of fuel assemblics is in their length. This difference will be readily solved through the use of a spacer in the cell locations containing Oconee fuel. The other differences between the two fuel types will have no significant effect
- on handling, storage, criticality, pool heat-up or any other parameter of importance in the storage of spent fuel at Catawba.
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- 8. Identify the casks used for fuel shipments between Oconec, McGuire and Catawba.
_ Response:
Any future Oconee-Catawba spent fuel shipments would be by truck. Planning for any future McGuire-Catawba spent fuel shipments currently includes both truck and rail modes. NRC certified casks suitable for Oconec and McGuire fuel shipments are:
Truck Rail NAC-1, NFS-4 IF-300 NLI 1/2 NLI 10/24 TN-8 Additional NRC certified casks may be available at the time of shipment.
Shipments will be made only in NRC certified casks. Commercial considera-tions dictate that specific casks not be identified at this time.
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- 9. Provide the name of the carrier, i
Response
- Carrier or carriers for truck shipments from Oconee to Catawba or from McGuire to Catawba have not been selected. Any carriers selected would be a common carrier who meets Duke Power Company, NRC and DOT regulations.
In addition, any such carrier would be licensed by NRC as a transporter of spent nuclear fuel and regulated by the Department of Transportation j and the States of North Carolina and South Carolina.. -
l Any carrier for rail shipments from McGuire to Catawba would be the Seaboard Coast Line Railroad Company and the Southern Railway Company or their successors.
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- 10. a) Provide the routes that Duke plans to consider in shipping fuel from Oconea and McGuire to Catawba.
b) Provide the distances in miles of the proposed routes.
c) What is the average population density along each of the proposed routes?
Response
a) Because of the lack of any firm plans for the eventual shipment of spent fuel from Oconee and McGuire to Catawba, no routes have been selected. Nevertheless, the following routes have been identified to show the spectrum of routes being considered:
Rail Routes - McGuire to Catawba Route A - Seaboard Coastline from McGuire to Mount Holly, N. C.
Seaboard Coastline from Mt. Holly to Charlotte, N. C.
Interchange from Seaboard Coastline to Southern at Charlotte Southern from Charlotte to Rock Hill, S. C.
Southern from Rock Hill to Duke spur to Catawba Station Route B - Same as Route A from McGuire to Charlotte Seaboard Coastline from Charlotte to Monroe, N. C.
Seaboard Coastline from Monroe to Chester, S. C.
Southern Railroad from Chester to Rock Hill, S. C.
Southern from Rock Hill to Duke spur to Catawba Station Route C - Same as Route A from McGuire to Charlotte interchanges Southern Railroad from Charlotte to Gastonia, N. C.
Southern from Gastonia to York, S. C.
Southern from York to Duke spur to Catawba Station Truck Routes - McGuire to Catawba Route A - N. C. 73 East from McGuire to I-77 I-77 South to Westinghouse Blvd.
Westinghouse Blvd. West to N. C. 49 N. C. 49 South to S. C. 49 S. C. 49 South to S. C. 274 S. C. 274 South to Catawba Station i
Route B - N. C. 73 East from McGuire to I-77 I-77 South to S. C. 161 S. C. 161 West to S. C. 274 S. C. 274 North to Catawba Station
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- 10. Response (cont'd)
Route C - N. C. 73 East from McGuire to I-77 I-77 South to I-85 I-85 South to N. C. 161 N. C. 161 South to S. C. 161 S. C. 161 South to S. C. 55 S. C. 55 East to S. C. 274 S. C. 274 South to Catawba Station Route D - N. C. 73 West from McGuire to N. C. 27 N. C. 27 West to N. C. 150 N. C. 150 West to U. S. 321 U. S. 321 South to I-85 I-85 South to N. C. 161 N. C. 161 South to S. C. 161 S. C. 161 South to S. C. 55 S. C. 55 East to S. C. 274 S. C. 274 South to Catawba Station Truck Routes - Oconee to Catawba Route A - S. C. 130 South from Oconee to U. S. 123 U. S. 123 East to S. C. 153 S. C. 153 South to I-85 I-85 North to Charlotte (I-77)
Same as McGuire Route A from Charlotte Route B - S. C. 130 South from Oconee to U. S. 123 U. S. 123 East to S. C. 153 S. C. 153 South to I-85 I-85 North to Charlotte (I-77)
Same as McGuire Route B from Charlotte Route C - S. C. 130 South from Oconee to U. S. 123 U. S. 123 East to S. C. 153 S. C. 153 South to I-85 I-85 North to S. C. 161 Same as McGuire Route C from S. C. 161 Routes D, E, F - S. C. 130 South from Oconee to U. S. 123 U. S. 123 East to U. S. 76 U. S. 76 South to I-85 Same as Routes A, B, C from I-85 @ S. C. 153 Routes G,11, I - S. C.130 North f rom Oconee to S. C. 183 S. C. 183 West to S. C.-11 S. C. 11 East to I-85 Same as Routes A, B, C from I-85 @ S. C. 11
- 10. Response (cont'd) b) Shipment route mileages are summarized as follows:
Oconee to Catawba Truck Routes:
Route A 182 miles Route B 184 miles Route C 154 miles Route D 191 miles Route E 193 miles Route F 149 miles Route G 181 miles Route H 183 miles Route I 139 miles McGuire to Catawba Truck Routes:
Route A 48 miles Route B 50 miles Route C 79 miles Route D 63 miles McGuire to Catawba Rail Routes:
Route A 66 miles Route B 125 miles Route C 72 miles c) Although large portions of the proposed routes for use from Oconee and McGuire to Catawba have been previously studied under the Oconee to McGuire transportation license, population densities are presently being surveyed. Upon completion of these surveys, the results will be transmitted to the NRC.
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- 11. When does Duke plan to submit a route approval request in accordance with 10 CFR 73.37 for spent fuel shipments between Oconee, McGuire, and Catawba?
Response
If spent fuel were ever shipped from Oconee or McGuire to Catawba, Duke would submit a route approval request, in accordance with 10 CFR 73.37, for such shipments 7 days prior to commencement of shipments between the stations. Based on the potential schedule described in Ic above, this would be March, 1987 for McGuire to Catawba routes and March, 1991 for Oconee to Catawba routes.
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j 12. Confirm that the material combinations of the fuel and storage racks l and the spacer-insert materials to be used in the Catawba spent fuel pool for non-Catawba fuel are identical to those for Catawba fuel.
Response
The materials contained in the fuel assemblies that might be transferred to Catawba are stainless steel-304, zircaloy-4 and inconel-718. Also, the fuel assembly spacers that will be used for storing the Oconce assemblies are to be constructed of stainless steel-304. These are the same. materials that are used in the Catawba fuel assemblies. Therefore, no additional material combinations will be added to the Catawba spent fuel pools.
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- 13. Does Duke plan to return any of the Oconee or McGuire fuel stored at Catawba to these facilities (i.e., Oocnee or McGuire) in the future?
Response
If any Oconee or McGuire fuel were to be stored at Catawba, Duke would not plan to return it to Oconce or McGuire in the future.
- 14. Discuss the applicability of Table S-4, 10 CFR 51.20, to your plans for shipping fuel from Oconee and McGuire to Catawba. Include such factors as traffic density, transportation workers, exposure of the general public, radiological effects and any pertinent site specific considerations such as a large number of construction workers at any of these plants.
Response
The environmental impact results contained in Table S-4 of 10 CFR 51.20 make several assumptions on fuel assembly characteristics, traffic and population densities. As discussed below, each of these assumptions is applicable to the proposed shipments of spent fuel from Oconee and McGuire to Catawba.
Reactor type - Table S-4 assumes LWR with limited thermal power of 3800 Megawatts. Oconee and McGuire are both LWR Nuclear Stations with unit thermal power ratings of 2568 and 3411 Megawatts respectively.
Fuel type - Table S-4 assumes Zr-4 clad UO2 at enrichments below 4%.
Both Oconee and McGuire fuel is UO with Zr-4 cladding.
2 Maximum initial enrichment of fuel that would be shipped from both Oconee and McGuire is 3.20 %.
Fuel history - Table S-4 assumes fuel burnup- levels below 33,000 MWD /MTU and a minimum cooling time of 90 days. Average burnup levels are discussed-in the response to question 3D. Oconee's candidate fuel assemblies will have maximum burnup levels of only 31,000 MWD /MTU. However, there will be a limited number of McGuire assemblies with burnup levels between l 33,000 and 43,000. This higher burnup level would, however, be completely off-set by the fact that all fuel transferred (Oconee or McGuire) will have undergone at least 5 years of cooling. In any event, the bulk of shipped McGuire assemblies will have burnup levels below 33,000 MWD /MTU.
Transport Mode-Table S-4 assumes that shipments of irradiated fuel utilize truck, rail or barge transport modes. All shipments from Oconee and McGuire will be by either Truck or Rail.
Heat Loads - Table S-4 assumes a maximum of 250,000 Btu /hr heat load per cask during shipment. Due to the extended cooling time for the candidate fuel assemblies this limit will never be exceeded. For 5-year cooled fuel the heat content will be less than one KW or 3,400 Btu /hr.
- 14. Response (cont'd)
Weight limits - As mentioned in Table S-4, weight limitations will be governed by State and Federal regulations which will be observed by Duke Power Company.
Frequency of Shipments - With a maximum of 25 fuel assemblies shipped per month from each plant, the Table S-4 limits of 1 truck shipment per day and 3 rail shipments per month will not be exceeded.
Exposed Workers - Spent fuel transportation will generally require the use of less than 10 transportation workers per shipment.
This is considerably less than the Table S-4 limit of 200.
Exposed Population - Since the handling of the spent fuel at both ends of a spent fuel shipment is done within the Oconee, McGuire and Catawba sites there will be no dose to general public onlookers.
Although the general public exposure along the route will depend cn the results of the population surveys being done in response to question 10c., based on information on hand, the 600,000 maximum given in Table S-4 would not be exceeded even in the use of the most populated route being considered for spent fuel shipments to Catawba.
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- 15. The transportation of spent fuel to Catawba from Oconee and McGuire should result (except for mileage and routes) in an increased impact on the total spent fuel movement related to Catawba. What will be the additional increase in spent fuel movement over that normally expected if no spent fuel were imported from Oconee and McGuire?
Response
The additional increase in spent fuel movement over that normally expected if no spent fuel were imported from Oconee and McGuire would be as stated in 2B above.
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