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| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 5 | | | page count = 5 |
| | | project = TAC:M97466, TAC:M97467 |
| | | stage = Other |
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| ==Dear Mr. McCollum:== | | ==Dear Mr. McCollum:== |
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| 4 By letter dated December 12, 1996, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations. No change to the TS is involved. | | 4 By {{letter dated|date=December 12, 1996|text=letter dated December 12, 1996}}, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations. No change to the TS is involved. |
| As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change), | | As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change), |
| then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval. | | then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval. |
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| ==Dear Mr. McCollum:== | | ==Dear Mr. McCollum:== |
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| l By letter dated December 12, 1996, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases l Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations. No change to the TS is involved. l As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change), | | l By {{letter dated|date=December 12, 1996|text=letter dated December 12, 1996}}, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases l Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations. No change to the TS is involved. l As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change), |
| then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval. | | then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval. |
| For administrative purposes, the revised TS Bases, which you provide to the staff, will ensure that all Catawba TS are updated in a consistent and timely manner. Enclosed is a copy of the revised TS Bases page B 3/4 3-3 for. Catawba Units 1 and 2 that have been dated to correspond to the issue date of this letter. | | For administrative purposes, the revised TS Bases, which you provide to the staff, will ensure that all Catawba TS are updated in a consistent and timely manner. Enclosed is a copy of the revised TS Bases page B 3/4 3-3 for. Catawba Units 1 and 2 that have been dated to correspond to the issue date of this letter. |
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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:OUTGOING CORRESPONDENCE
MONTHYEARML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl 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 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 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 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 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 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 ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 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 NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 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 ML20209E2701999-07-0101 July 1999 Forwards Insp Repts 50-413/99-03 & 50-414/99-03 on 990425- 0605.Six Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209E3931999-06-28028 June 1999 Informs of 990618 Meeting Conducted at Facility to Present Results of Most Recent Periodic Plant Performance Review for Plant.List of Attendees Encl ML20196G8861999-06-24024 June 1999 Discusses GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structrual Integrity 950816 & 960729 Responses.Rvid,Version 2 Released as Result of Review.Rvid Should Be Reviewed & Comments Should Be Received by 990901 If Not Acceptable for Plant ML20196G6541999-06-17017 June 1999 Confirms 990614 Telephone Conversation Re Rescheduling of Two Predecisional Enforcement Conferences Originally Scheduled for 990623.SSS Conference Rescheduled for 990712 & Ice Condenser Conference Rescheduled for 990720 ML20196A5781999-06-14014 June 1999 Discusses Notice of Enforcement Discretion for Duke Energy Corp Re Catawba Nuclear Station Unit 1 TSs 3.5.2 & 3.7.12 ML20195E9171999-06-0303 June 1999 Confirms Conversation with Bradshaw on 990526 Re Rescheduling 990607 Predecisional Enforcement Conference to Discuss Apparent Violation in Insp Repts 50-413/99-10 & 50-414/99-10.Conference Will Be on 990623 in Atlanta,Ga ML20195F4141999-06-0202 June 1999 Forwards Insp Repts 50-413/99-11 & 50-414/99-11 on 990422-23 & 0503.Apparent Violation Identified & Being Considered for Escalated Enforcement Action.Violation Involved Failure to Maintain Unit 1 Ice Condenser Lower Inlet Door Operable ML20207D0671999-05-20020 May 1999 Informs That During Meeting on 990512,arrangements Modified for Administration of Licensing Exams at Catawba Nuclear Station During Weeks of 990524 & 0607,respectively ML20207C8721999-05-20020 May 1999 Forwards Insp Repts 50-413/99-02 & 50-414/99-02 on 990314-0424.Three Violations Occurred & Being Treated as non-cited Violations.Activities Generally Characterized by Safety Conscious Operations & Sound Engineering & Maint ML20207C8061999-05-19019 May 1999 Confirms 990510 Telcon with R Jones Re Predecisional Enforcement Conference Requested by NRC & Scheduled for 990607 in Atlanta,Ga to Discuss Apparent Violation Associated with Potential Inoperability of SSS ML20207C7761999-05-19019 May 1999 Informs That on 990618,NRC Will Meet with Mgt of Duke Energy Corp to Discuss Performance of Catawba Facility & Extends Invitation to Attend Meeting as Observer ML20206P4911999-05-14014 May 1999 Forwards Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206M4201999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation (NRR) Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt (DLPM) Created.Reorganization Chart Encl ML20206U4091999-05-10010 May 1999 Forwards Insp Repts 50-413/99-10 & 50-414/99-10 on 990314-0424.One Violation Occurred & Being Considered for Escalated Enforcement Action Involving Inoperability of Standby Shutdown Sys from 981216-29 ML20206N4191999-05-0606 May 1999 Informs That Team Will Inspect Dam at Standby Nuclear Service Water Pond on 990609.Purpose of Insp Will Be to Confirm That Structure Conforms with Design Documents & Capability of Performing Design Functions ML20205S5491999-04-21021 April 1999 Forwards SE Discussing DPC Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. Response Acceptable ML20206B7941999-04-16016 April 1999 Confirms 990331 Telcon Between M Purser of Util & R Franovich of NRC Re Public Meeting Scheduled for 990618 in York,Sc to Discuss Results of NRC Recent Plant Performance Review for Catawba Nuclear Station ML20205N3471999-04-12012 April 1999 Forwards Safety Evaluation & Eri/Nrc 95-506, Technical Evaluation Rept on Submittal Only Review of IPE of External Events at Catawba Nuclear Station,Units 1 & 2 ML20205T3491999-04-0909 April 1999 Informs That on 990317,T Beedle & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Catawba Nuclear Station for Y2K.No Y2K Exam Scheduled.Initial Exam Requested for Apr 2001 for Approx 18 Candidates ML20205N0531999-04-0606 April 1999 Forwards Insp Repts 50-413/99-01 & 50-414/99-01 on 990124-0313.DPC Conduct of Activities at Catawba Facility Generally Characterized by Safety Conscious Operations & Sound Engineering.Five Violations Noted & Treated as NCVs ML20196K9961999-03-30030 March 1999 Forwards Synopsis of NRC OI Completed Rept Re Alleged Compromise of Initial Licensed Operator Exam at Cns.Oi Did Not Substantiate Allegation That Initial Operator Exam Compromised.Plans No Further Action Re Matter ML20205M2651999-03-25025 March 1999 Discusses PPR Completed 990201.Advises of Planned Insp Effort Resulting from Catawba PPR Review.Forwards Plant Issues Matrix & Insp Plan ML20207L7741999-03-15015 March 1999 Requests That NRC Exercise Discretion Not to Enforce Compliance with Actions Required by Plant,Units 1 & 2 Re TS Limiting Conditions for Operation 3.3.7 & 3.3.8 ML20207M9091999-03-0505 March 1999 Informs That Info Submitted by Application, Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20207A5821999-02-17017 February 1999 Forwards Insp Repts 50-413/98-12 & 50-414/98-12 & Notice of Violation.One Violation Being Considered for Escalated Enforcement Action ML20203G5161999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20203A2421999-02-0505 February 1999 Forwards SE Accepting Proposal to Revise Methodology in TR DPC-NE-3002-A,to Permit Use of single-node Model,Instead of multi-node Model,To Represent SG Secondary Sys for post-trip Phase of Loss of Normal Feedwater Analysis for Plant,Unit 2 ML20202J4751999-01-29029 January 1999 Responds to Concern Raised on 981020 Re Appropriateness of Interaction of NRC Headquarters Operations Officer with on-shift Operations Staff During Event ML20202C2511999-01-27027 January 1999 Forwards Request for Addl Info Re Util 980331 Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Catawba Nuclear Station. Response Requested within 60 Days of Date of Ltr 1999-09-24
[Table view] |
Text
..
January 13, 199'7 # '
Mr. Willian R. McCollum Site Vice President '
t Catawba Nuclear Station Duke Power Company '
4800 Concord Road York, South Carolina 29745-9635
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - DISTRIBUTION OF REVISED TECHNICAL SPECIFICATIONS BASES PAGES (TAC NOS. M97466 AND M97467)
Dear Mr. McCollum:
4 By letter dated December 12, 1996, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations. No change to the TS is involved.
As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change),
then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.
For administrative purposes, the revised TS Bases, which you provide to the staff, will ensure that all Catawba TS are updated in a consistent and timely manner. Enclosed is a copy of the revised TS Bases page B 3/4 3-3 for Catawba Units 1 and 2 that have been dated to correspond to the issue date of this letter.
Sincerely, l Original signed by:
Peter S. Tam, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - I/II i Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414 DISTRIBUTION Docket File' SVarga'
Enclosure:
Bases Change Pages PUBLIC . '
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PDII-2 RF . HBerkow .. \
cc w/ encl: See next page PTam . LBerry , t \
OGC ACRS RCrlenjak, RII EMerschoff,'RII DOCUMENT NAME: G:\ CATAWBA \ CAT 97466.LTR '
To receive a copy of this document, indicate in the box: "C" - Copy without 4 attachment / enclosure "E" - Copy with attachment / enclosure "N" dad &opy 0FFICE PDII-2/PM PDII-2/LA\l)g N- PDII-ME//
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NAME PTam:cn LBerry, HBerhtiw DATE / /97 / % /97 (C / /97 / / /1)/97-0FFICIAL RECORD COPY 9701150 95 970113 PDR ADOCK 05000413 khh P PDR
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UNITED STATES !
NUCLEAR REGULATORY COMMISSION f WASHINGTON. D.C. 20666-0001
%,.....,e# January 13, 1997 I Mr. William R. McCollum '
Site Vice President
' Catawba Nuclear Station l l
Duke Power Company 4800 Concord Road York, South Carolina 29745-9635
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - DISTRIBUTION OF REVISED TECHNICAL SPECIFICATIONS BASES PAGES (TAC NOS. M97466 AND M97467) i
Dear Mr. McCollum:
l By letter dated December 12, 1996, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases l Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations. No change to the TS is involved. l As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change),
then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.
For administrative purposes, the revised TS Bases, which you provide to the staff, will ensure that all Catawba TS are updated in a consistent and timely manner. Enclosed is a copy of the revised TS Bases page B 3/4 3-3 for. Catawba Units 1 and 2 that have been dated to correspond to the issue date of this letter.
Sincerely, e f -
w Pete 6. Tam, Senior Project Manager Project Directorate II-2 Divi.sion of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414
Enclosure:
Bases Change Pages cc w/ encl: See next page
Mr. W. R. McCollum Duke Power Company Catawba Nuclear Station cc:
Mr. M. S. Kitlan North Carolina Electric Membership Regulatory Compliance Manager Corporation Duke Power Company P. O. Box 27306 4800 Concord Road Raleigh, North Carolina 27611 York, South Carolina 29745 Senior Resident Inspector Mr. Paul R. Newton 4830 Concord Road Legal Department (PB05E) York, South Carolina 29745 Duke Power Company 422 South Church Street Regional Administrator, Region II Charlotte, North Carolina 28242-0001 U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 J. Michael McGarry, III, Esquire Atlanta, Georgia 30323 Winston and Strawn 1400 L Street, NW Max Batavia, Chief Washington, DC 20005 Bureau of Radiological Health South Carolina Department of North Carolina Municipal Power
~~
Health and Environmental Control Agency Number 1 2600 Bull Street 1427 Meadowwood Boulevard Columbia, South Carolina 29201 P. O. Box 29513 Raleigh, North Carolina 27626-0513 Mr. G. A. Copp Licensing - EC050 Mr. Peter R. Harden, IV Duke Power Company Account Sales Manager 526 South Church Street Westinghouse Electric Corporation Charlotte, North Carolina 28242-0001 Power Systems Field Sales P. O. Box 7288 Saluda River Electric Charlotte, North Carolina 28241 P. O. Box 929 Laurens, South Carolina 29360 County Manager of York County York County Courthouse Ms. Karen E. Long York, South Carolina 29745 Assistant Attorney General North Carolina Department of Justice Richard P. Wilson, Esquire P. O. Box 629 Assistant Attorney General Raleigh, North Carolina 27602 South Carolina Attorney General's Office Elaine Wathen, Lead REP Planner P. O. Box 11549 Division of Emergency Management Columbia, South Carolina 29211 116 West Jones Street Raleigh, North Carolina 27603-1335 Piedmont Municipal Power Agency 121 Village Drive Dayne H. Brown, Director Greer, South Carolina 29651 Division of Radiation Protection N.C. Department of Environment, Mr. T. Richard Puryear Health and Natural Resources Owners Group (NCEMC) P. O. Box 27687 Duke Power Company Raleigh, North Carolina 27611-7687 4800 Concord Road :
York, South Carolina 29745
_ . . _ . _ _ ~ _ _ . _ _ _ _._ __
INSTRUMENTATION BASES REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)
The Engineered Safety Features Actuation System interlocks perform the following functions:
P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves on T , below Setpoint, prevents the opening of the main feedwater ,
valves which were closed by a Safety Injection or High Steam i Generator Water Level signal, allows safety injection block so that components can be reset or tripped. l l
Reactor not tripped - prevents manual block of Safety Injection.
l P-11 Defeats the manual block of Safety Injection actuation on low pres-surizer pressure and low steam line pressure and defeats steam line isolation on r gative steam line pressure rate. Defeats the manual block of the motor-driven auxiliary feedwater pumps on trip of main feedwater pumps and low-low steam generator water level.
P-12 On decreasing reactor coolant loop temperature, P-12 automatically blocks steam dump and allows manual bypass of steam dump block for the cooldown valves only. On increasing reactor coolant loop temper-ature, P-12 automatically defeats the manual bypass of the steam dump block.
P-14 On increasing steam generator level, P-14 automatically trips all feedwater isolation valves, pumps and turbine and inhibits feedwater ;
control valve modulation.
Surveillances for the Reactor Trip Bypass Breakers are included in respense to the NRC's Generic Letter 85-09, dated May 23, 1985.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLAhi OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that: (1)theassociatedactionwillbeinitiatedwhenthe radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance. The radiation monitors for plant operations sense radiation levels in selected plant systems and locations and determine whether or not predetermined limits are being exceeded. The radiation monitors send actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems. Some of the final actuations are dependent on plant condition in addition to the actuation signals from the radiation monitors.
CATAWBA - UNIT 1 B 3/4 3-3 Revised by NRC Letter dated J@nu@rL 13, 1997
o INSTRUMENTATION l
BASES REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTVATION SYSTEM INSTRUMENTATION (Continued)
The Engineered Safety Features Actuation System interlocks perform the following functions:
P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves below Setpoint, prevents the opening of the main feedwater on T 'which were closed by a Safety Injection or High Steam va1Es Generator Water Level signal, allows safety injection block so that components can be reset or tripped.
Reactor not tripped - prevents manual block of Safety Injection.
P-11 Defeats the manual block of Safety Injection actuation on low pres- l surizer pressure and low steam line pressure and defeats steam line isolation on negative steam line pressure rate. Defeats the manual ,
block of the motor-driven auxiliary feedwater pumps on trip of main l feedwater pumps and low-low steam generator water level.
P-12 On decreasing reactor coolant loop temperature, P-12 automatically blocks steam dump and allows manual bypass of steam dump block for the cooldown valves only. On increasing reactor coolant loop temper-ature, P-12 automatically defeats the manual bypass of the steam dump l block. )
l P-14 On increasing steam generator level, P-14 automatically trips all feedwater isolation valves, pumps and turbine and inhibits feedwater control valve modulation.
Surveillances for the Reactor Trip Bypass Breakers are included in response to the NRC's Generic Letter 85-09, dated May 23, 1985.
3/4.3.3 MONITORING INSTRUMENTATION 1
3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that: (1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to pemit a channel to be out-of-service for testing or maintenance. The radiation monitors for plant operations sense radiation levels in selected plant systems and locations and detemine whether or not predetemined limits are being exceeded. The radiation monitors send actuation signals to initiate alams or automatic isolation action and l actuation of Emergency Exhaust or Ventilation Systems. Scme of the final l actuations are dependent on plant condition in addition to the actuation
- signals from the radiation monitors.
CATAWBA - UNIT 2 B 3/4 3-3 Revised by NRC Letter i
dated January / 13, 1997 -