Letter Sequence Other |
---|
|
|
MONTHYEARML20203A4441998-02-0303 February 1998 Forwards Document Faxed to M Kitlan Re Issues for an Upcoming Telephone Conference Project stage: Other ML20203A3701998-02-0606 February 1998 Forwards RAI on Amend Request Re Pressure Temp Limits. Response Requested within 30 Days of Ltr Receipt Project stage: RAI ML20216D8281998-03-0505 March 1998 Responds to NRC 980206 RAI on Util 970915 License Amend Request to Revise TS Requirements for Reactor Vessel Pressure & Temp Limits Project stage: Other ML20217F5731998-03-26026 March 1998 Forwards Request for Addl Info on Amend Request Re Pressure Temp Limits Project stage: RAI ML20217N8561998-04-27027 April 1998 Forwards Response to Questions 3 & 4 of NRC Request for Addl Info Contained in Ltr Re Pressure Temp Limits Project stage: Request ML20249B3931998-06-15015 June 1998 Responds to 980326 RAI Re Pressure/Temp License Amend Request, .Proposed Tech Specs Pages Re RCS Overpressure Protection,Rcs SRs & Eccs,Encl Project stage: Other ML20236U3461998-07-22022 July 1998 Submits Response to NRC 980326 RAI Re Computer Analysis Performed for Catawba Unit 1 Replacement Recirculating SG W/Respect to Low Temp Overpressure Protection Project stage: Other ML20237B2291998-08-10010 August 1998 Provides Response to RAI in Support of 980427 & s Re Pressure/Temp Limits Project stage: Response to RAI ML20154N3221998-10-15015 October 1998 Forwards Document Signifying Implementation of Amends 170 & 162 to Licenses NPF-35 & NPF-52,respectively on 981001 Project stage: Other 1998-03-05
[Table View] |
|
---|
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] |
Text
_ . _ . _ _ _ . . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ -__-__--_-
I g Duke Power CImpany LM -
t
"**"F 526 South Church Street P.O. Box 1006 Charlotre, NC 28201-1006 M. S. Tuckman Executiw Vice hident (704)382-2200 omcr Nudear Generation (704) 382-4360 !^X June 15, 1998
\
U.S. Nuclear Regulatory Commission I Attention: Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Corporation Catawba Nuclear Station, Units 1 and 2 I Docket Numbers 50-413 and 50-414 Reply to Staff Position and Request for Additional Information on Amendment Request Regarding Pressure / Temperature Limits TAC Numbers M99629 and M99630 I
Reference:
Letter from Peter S. Tam, NRC, to Gary R.
Peterson, Duke, same subject, dated March 26, 1998.
Duke Energy Corporation License Amendment Request Submittal, dated September 15, 1997.
Pursuant to 10CFR50.4 and 10CFR50.90, Duke Energy Corporation is hereby responding to Questions 1 and 2 of the NRC request for additional information contained in the March 26, 1998 reference. Duke's responses to Questions 3 and 4 of the subject request were previously provided via separate correspondence dated April 27, 1998.
The enclosed information contains a restatement of Questions 1 and 2, followed by Duke's response. This response includes, where applicable, revised proposed changes to the Technical Specifications.
The proposed changes contained in the enclosed License Amendment Request (LAR) apply to Technical Specifications 3.4.9.3, Reactor Coolant System Overpressure Protection; Proposed 4.4.9.3.3 and 4.4.9.3.4, Reactor Coolant System Surveillance Requirements; and 3.5.3, Emergency Core Cooling Systems. The proposed changes affect the requirements for low-temperature overpressure protection by adding: 1) more restrictive requirements for the accumulator discharge valves, 2) more restrictive requirements i 7
r: (
99 6 0 990615 l- PDR ADOCK 05000413 p PDR
_____m__ _ _ _ _ _ . _ _ _ _
h
.w, i
[,f E - -
I 'f' U.S. Nuclear Regulatory Commission 7 '
June 15,)-1998-Page 2 ,
on pumps capable of injecting into the reactor coolant system,-
~3) thenlowest. reactor. coolant system temperature justified by the Low Temperature Overpressure Protection . (LTOP) analysis, and L4),more restrictive requirements on reactor coolant pump
. operation during LTOP. conditions. Also, the addition of surveillance requirements associated with the proposed changes are' included in this submittal package. Additionally, a footnote L
addressing the maximum number of operable charging pumps / safety
, injection pumps during-LTOP, conditions is revised by the proposed amendment.
The proposed mmendment for conversion of the current Catawba
' 3'
. Technical Specifications to~the Catawba Improved Technical Specifications was submitted to the NRC by Duke letter dated May 27, 1997. The' changes proposed in this' reply will apply to both
'the' current Catawba'Technica1' Specifications and the Catawba Improved Technical Specifications. Consequently, as described below,' this amendment package contains the affected pages from both versions of the. Technical Specifications.
- The contents of this~ reply letter are as follows
,. Enclosure 1 is a restatement of the NRC request for additional information.for Questions 1 and 2, followed by Duke's reply and
[ technical justification forlthe additional proposed Technical
, Specifications.
. Attachments la and lb provide a marked copy of the affected
, current. Technical' Specifications pages for Catawba Units 1 and E 2, respectively, showing the proposed changes. Attachments 2a ,
'and 2b are reprinted pages of the affected current Technical '
r Specifications.pages,for Catawba Units 1 and 2 respectively.
l i Attachments 2a and 2b'also include'those reprinted pages that cy .
were part of'the original September 15, 1997 submittal package I f$~ referenced above.
,, ' Attachments-2c and 2d' provide a revised copy of the Improved
- o. Technical Specifications submittal documentation for Catawba Li C
. Units'1 and 2,'respectively, showing the proposed changes.
, Included in! Attachments 2c and'2d are revised pages of the q current: Technical Specifications markups as included in the ;
- Improved Technical Specifications conversion submittal. Also included in' Attachments 2c and 2d'are revised pages of the
.affected. Improved Technical Specifications pages. Finally,
!. revised pages of the affected markups of NUREG-1431, Revision 1, i- Standard Technical Specifications, Westinghouse Plants, are also L
o c C___________1___________.________-__-----._____-.__.- - - - _ _ J
U.S. Nuclear Regulatory Commission June 15, 1998 ,
Page 3 included in Attachments 2c and 2d. Note that the original submittal for the pressure / temperature limits, overpressure
. protection, and reactor vessel material surveillance program, dated September 15, 1997, did not include revised marked-up pages for the current Technical Specifications markups and the
. NUREG-1431 markups. Consequently, this supplement includes revised markups for all changes proposed both in the September 11 5 , 1997 original request and in this supplement.
- ' Pursuant to 10CFR50.92,. Attachment 3 contains & supplemental No l Significant Hazards Consideration Determination for the proposed l additional changes.
1 Pursuant to 10CFR51.22 (c) (9) , Attachment 4 provides a supplemental basis for categorical exclusion from performing an L Environmental Assessment / Impact Statement.
l The enclosed additional proposed changes tx) the Catawba l
Technical Specifications are in reply to the NRC request for additional-information as contained in the Marcn 26, 1998 reference. They-are technically related to the proposed I Technical Specifications changes submitted by Duke's letter; dated September 15, 1997. In addition, the enclosed changes i represent additional controls not presently included in the
- existing Technical Specifications.
Implementation of this amendment to the-Catawba Facility Operating License and Technical Specifications will impact
.the Catawba Updated Final' Safety Analysis Report (UFSAR).
Necessary UFSAR changes will be submitted in accordance with 10CFR50.71(e).
Duke.is reque.iting.that this reply and our original ~ amendment request be.ap1. roved.at the earliest possible convenience to l
~
~ support our replacement of the existing' Catawba heatup and cooldown curves with the. revised curves. The current Unit 1
, curves will expire in September of 1998 based on full power b . operation. NRC approval is needed to' ensure that a forced L shutdown is-not incurred at that time.
l l L .In accordance with Duke administrative procedures and the i
( ,
Quality Assurance Program Topical. Report, this submittal has j been reviewed and approved by the Catawba Plant Operations l Review Committee and the Duke Corporate Nuclear Safety Review j Board.. J l
l l
L i t_.____ _ _ _ _ . . _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _________ _ _ _ ___J
I l
l U.S. Nuclear Regulatory Commission 1 June 15, 1998 I Page 4 f
Pursuant to 10CFR50.91, a copy of this reply is being sent to the appropriate State of South Carolina official.
Inquiries on this matter should be directed to L.J. Rudy at (803) 831-3084.
Very truly yours, tt.3.fi;~.le,___ i l
M. S. Tuckman LJR/s i Enclosure and Attachments I xc (with enclosure and attachments): l L.A. Reyes U.S. Nuclear Regulatory Commission Regional Administrator, Region II I Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 J l
D.J. Roberts j Senior Resident Inspector (CNS) l U.S. Nuclear Regulatory Commission {
Catawba Nuclear Station P.S. Tam NRC Senior Project Manager (CNS)
U.S. Nuclear Regulatory Commission ;
Mail Stop O-14H25 l Washington, D.C. 20555-0001 M. Batavia, Chief Bureau of Radiological Health 2600 Bull St.
I Columbia, SC 29207 i
t.
l L
I U.S. Nuclear Regulatory Commission l June 15, 1998 Page 5 AFFIDAVIT l M. S. Tuckman, being du.?y sworn, states that he is Executive Vice President of Duke EL'rgy Corporation; that he is authorized on the part of said corporation to sign and file with the {
Nuclear Regulatory Commission this amendment to the Catawba !
Nuclear Station Facility Operating Licenses Numbers NPF-35 and {
NPF-52 and Technical Specifications; and that all statements and J matters set forth herein are true and correct to the best of his knowledge.
. . M ;- --
M. S. Tuckman, Executive Vice President Subscribed and sworn to me: Mmg
/kr Date 0AM Notary Pu81ic My commission expires: bM 22 200/ y Date j 1
I l
l SEAL l
l
Enclosure 1 Staff Position and Request for Additional Information Catawba Nuclear Station, Units 1 and 2 Proposed Amendment on Pressure Versus Temperature Limits Duke Response to Questions 1 and 2 and Technical Justification for Additional Proposed Technical Specifications
- 1. Regarding restrictions assumed in Duke Energy Corporation's (Duke's) low-temperature overpressure protection (LTOP) analyses, Duke's submittal of September 15, 1997, as supplemented by letter dated March 5, 1998, d.id not address such in the Catawba Technical Specifications. These are as follows:
- a. Restrictions on accumulator discharge valves.
- b. Restrictions on pumps capable of injecting into the reactor coolant system for the entire LTOP range.
l
- c. Lowest temperature justified per LTOP analysis.
It is the staff's position that the proposed amendment cannot be approved unless Duke also proposes LTOP requirements to reflect the above restrictions.
DUKE RESPONSE AND TECHNICAL JUSTIFICATION For items la, lb, and Ic above, Duke has proposed additional changes to the Catawba Technical Specifications requirements to
. address these issues. The three additional requirements represent controls not presently included in Technical Specifications. They therefore represent additional conservatism imposed upon plant operation by the Technical Specifications.
Items la and lb have already been included in Catawba's Improved i Technical Specifications (ITS) conversion submittal of May 27, 1997. The Technical Justification included in the ITS submittal i remains applicable to these changes. Note that Duke has also proposed to correct the erroneous footnote associated with Technical Specification 3/4.5.3 (ECCS Subsystems - Tavg < 350 F) by changing the designated "and" to an "or". This will make this footnote consistent with other LTOP requirements in the Technical Specifications and with the Catawba LTOP analysis.
For Item lc the proposed additional Technical Specifications provide protection against cold overpressure of the reactor
( coolant system based on the peak pressure from the limiting l
1 1
i
l l
l i
steady state condition mass-addition transient from a single safety injection pump with no reactor coolant pumps running. This also highlights the lower reactor system temperature limits that l could be approached under extreme winter time outage conditions.
l This helps to ensure that the Appendix G limits are not exceeded.
The issues identified by Items la and lb are currently being addressed administratively by existing Duke procedures.
Consequently, the proposed additional Technical Specifications addressing Items la and lb represent no substantial change to current operating practices. The issue identified by Item lc will result in more conservative operational requirements in the Technical Specifications and in the resultant implementing station procedures.
1
- 2. Does Duke's analysis depend on restrictions on the number of reactor coolant pumps operable during different temperature ranges? If so, it is the staff's position that appropriate l requirements must be added to the Technical Specifications.
DUKE RESPONSE AND TECHNICAL JUSTIFICATION Yes, the Appendix G curves are evaluated for the fracture toughness of the beltline region of the reactor vessel. The signals used to generate the pressure setpoint originate from wide range pressure transmitters NCPT5120 and NCPT5140 for pressurizer power operated relief valves (PORVs) NC34A and NC32B, respectively. These instruments are associated with the hot legs of the Reactor Coolant System. During startup and shutdown, the reactor coolant pumps are operating and their induced flows create a pressure drop across the vessel. This pressure drop along with the difference in elevation between the beltline region and the instrumentation locations are added to the indicated pressure to determine an accurate pressure for the reactor vessel beltline region.
The difference in elevation between the beltline region and the instrumentation locations is 4.6 psi and this system error correction is accounted for in the LTOP setpoint evaluation and is conservatively applied at all time regardless of the number of reactor coolant pumps in operation.
i i
2 l
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ m__ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ J
i l
l The pressure drop across the reactor vessel associated with the l Ieactor coolant pump is also accounted for in the LTOP setpoint evaluation. However, the value associated with this pressure drop is dependent on the number of pumps in operation.
Pumps Pressure Drop On (psid) )
4 56.9 3 34.7 2 16.8 1 4.8 0 1 Factored into these numbers as a conservatism is the flow dp effects of two trains of residual heat removal also in operation.
To realize the benefit of the pressure drop being dependent on the number of reactor coolant pumps in operation, the LTOP setpoint evaluation has accounted for this during different temperature regions. Plant operational procedures have been modified to adhere to the pump restriction as dictated by the LTOP evaluation.
Duke has proposed additional changes to the Catawba Technical Specifications to address this issue. The proposed reactor coolant pump operating restrictions are already being controlled administratively at Catawba. These proposed operating restrictions represent additional controls not presently contained within the Technical Specifications. The additional restrictions provided by the proposed addition of Table 3.4-3 to the technical specifications also provide protection against cold overpressure of the reactor coolant system based on the peak pressure from the limiting steady state condition mass addition and heat addition transients with various combinations of reactor coolant pumps running. This helps to ensure that the Appendix G limits are not exceeded.
l 3
1 L.. .- - _ - - - - - - - - - - - - - _ - - - - - - - - - - - _ _ - - - - - - - - - - - -- - - - - - - ------- - - - - - - - - - J