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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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$g[t , Ji f.S.1Niiclear Regulatory Commission Document Control Desk l C[, NH IWashington, D.C. '20555 ,
~ Sub,)ect: Catawba Nuclear Station Docket Nos. 50-413:and 50-414 NRC Inspection Report Nos. 50-413, 414/89-09 i Reply to Inspector Follow-up Items Gentlemen:
Enclosed.is the response to Inspector Follow-up Items identified in Inspection- t Report ~ 50-413, 414/89-09 issued July 10,.1989 by Albert V. Gibson. !
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Very truly yours,- '
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Ital B. Tucker-WRC76/lcs r4
-xct- Mr. S.'D. Ebneter-
' Regional Administrator- ;
T Region II 101 Marietta Street, NW, Suite 2900 ,
Atlanta, Georgia 30323 Mr. W. T. Orders NRC Resident Inspector-Catawba Nuclear Station m.
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- - R. L.-;; Gill, Jr.
T. D. Curtis - ONS' ,
- R. O. Sharpe - MNS ,
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- 7. G. Hudss E. E Parris !
N. A. " Rutherford i 0, - L.R.; Cross Mgr. QA T/S -EC12A' NRC.'Coord QA T/S - EC12A.
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REPLY TO A WEAKNESS (IFI)
{l 413, 414/89-09-03 1 V
Controls on the thermal power computer and its inputs are weak. This computer is used for normal determination of plant' power level and for adjusting the gain on the nuclear. ,
instruments. (Paragraph 2.b)
;
RESPONSE
- 1. Corrective Actions Taken and Results Achieved'. .
The-Unit 1 procedure used to perform a check of the :
computer inputs to the thermal power calculation was added to the Catawba Periodic Test (CPT) test tracking ,
program. This was a committed action.
- 2. Corrective Actions to be Taken to Avoid Further Incidents.
The Maintenance Management Procedure concerning control of the Standing Work Roquest program will be revised to
~
ensure that the cognizant System Exports roccive notification of any instrumentation that will exceed its normal. calibration frequency. This is a committed action.
- 3. :Date of Full Compliance.
Duke Power will be in full compliance by December 1, 1989.'
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3 DUKE POWER CCMPANY REPLY 'IO A WEAKNESS (IFI) 413, 414/89-09-04 One 10CFR50.59 Evaluation was weak concerning a modification to the nuclear service water pit strainer instrumentation.
Annunciators described in the FSAR'were disabled for about 30 days with no written consideration of compensatory action.
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RESPONSE
.l. Corrective Actions Taken and Results Achieved.
A. A review of the 10CFR50.59 Evaluation was performed and it was determined that even though the RN Pit Screen Hi D/P annunciators were not specifically stated in the 10CFR50.59 Evaluation as being described in the FSAR, ,
it was apparent that the preparer knew this because the FSAR Section.9.2.1, Nuclear Service Water System, was listed as an FSAR Section consulted. It was also decided that the information contained on Page 3 of 3 of the evaluation answered the appropriate questions:
Screening for'10CFR50.59 Applicability and Unreviewed Safety Question (USQ) Evaluation. Addressing what compensatory measures will be taken for removing a piece of equipment from service is not a concern of the +
l 10CFR50.59 Evaluation. Any compensatory actions necessary when removing a piece of equipment from
, service is determined by Operations and would be l- included in the body of the procedure. The need for compensatory action was listed in the 10CFR50.59 Evaluation for the level of the SNSWP because of the requirement of Tech. Spec. 3/4.7.5. The specific
- compensatory action was still not specified in the evaluation; instead, it was left up to the operator.
'2. Corrective Actions to be Taken to Avoid Further Incidents.
A. All modifications will be looked at on a case to case basis, but compensatory measures for a piece of equipment being removed from service will not normally be included in the 10CFR50.59 Evaluation.
- 3. Date of Full Compliance.
Duke Power is in full compliance now.
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DUKE POWER COMPANY. Page 1 of 2 t
REPLY TO A WEAKNESS (IFI) 413, 414/89-09-05 s
Auxiliary operators on rounds failed. to frisk immediately 1 after exiting contaminated areas.- (paragraph 2.c) ,
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RESPONSE
- 1. - Corrective Actions Taken and Results Achieved.- .
l A. The OSTI review was conducted immediately following refueling outages on Unit #1 and #2.
Budget and manpower limitations resulted in. a dilution of normal decontamination resources
.during outages. As a result, approximately 15-Safety Related Pump Rooms were contaminated during the review period.
The decontamination program at the time of this- 1 response has achieved a condition where only three (3) of the Safety Related Pump Rooms' are contaminated. .
Station Directive 3.8.3 (Contamination Provention, '
Control and Decontamination Responsibilitics) was ,
revised August 28, 1989 to simplify the frisking requirements for Operators performing routing surveillances. These changes will create a more officient work process and contribute to improved compliance. ,
- 2. ~ Corrective Actions to bc Taken to Avoid Further Incidents.
and manpower limitations exist, A. Since budget
' additional management attention can be directed to the particular category of contaminated safety related pump rooms as we assess our status- and develop decontamination plans. The Monthly Report <
documenting contamination status and decontamination efforts / plans will be revised to indicate under " Priority Items" a permanent category of " Contaminated Safety Related Pump Rooms". In addition, the Radiation Protection Monthly Status Report will be revised to indicate a category for " Contaminated Safety Related Pump Rooms".
The availability of this information to station management will provide sufficient attention to maintain Safety Related Pump Rooms in acceptable condition to support Operations personnel performing routine inspections.
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Thes two;- reports , ref erenced ' ; will' be'~ revis'edf toi*includel a '
Lthe!above changes.4 Reports published after iSeptember}
y"' y 3 ' 30,11989 willJbe in this'new format.
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3gs y DUKE POWER COMPANY REPLY TO A WEAKNESS'(IFI).
413, 414/89-09-06.
Control.of doors was weak, as indicated by the three open fire doors or security doors found by.the team. (paragraph 2.g.).
RESPONSE
- 1. Corrective Actions Taken and Results Achieved.
A. Upon notification of the prob 1cm with the' door to the diesel generator room (AX302) maintenance personnel. replaced the automatic closer and replaced the weather stripping which was preventing the door from completely closing.
I
- The problem with the door on the Unit 3 side of the control room was created when the tile in the corridor leading to the control room was replaced with now, thicker tile. Work request H001593MES has been written to correct this problem by removing the tile and grinding down a high spot on .
the concreto bcncath the tilo.
The door at the entrance to the IAE offico arca is a non-committed fire door (i.e., this door is in a non-vital arca, but designated as a fire door to prevent property damage). The Safety section at Catawba has roccived permission from the insurance carrier for Catawba to allow the doors in this' area to remain open when personnel are in the area.
- 2. Correctivo Actions to be Taken to Provent Further l' Incidents.
A. All members of Radiation Protection arc in a position-to be involved in incidents which cause a Security or Fire Door to f ail to perform an intended function. In addition, all members of Radiation Protection are in a position due to proximity to many of these doors, to identify problems which have previously gone undetected. A package identifying this weakness and requesting Radiation Protection personnel be sensitive to this problem during their work activitics has been prepared and distributed to Radiation Protection Supervision for presentation to all employees.
Presentations will be completed by September 30, 1989.
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I B.- JA preventativoimaintenance; program is-being:
established to inspect'and maintain all doors in ;
the auxiliary building on a periodic basis; the.
. doors 11eading.to-the diesel generator rooms will
- be inspected and necessary maintenanco performed -;
quarterly. This should climinate' mechanical problems associated with these doors. This program will be in place by November 1, 1989. .
C. To provent creating situations that cause doors to- i drag, all NPD maintenance personnel and Construction and Maintenanco Department personnel associated with installation of flooring materials
' wil1~be cautioned to assure that door operation is not impaired. This action'will be complete by November 1, 1989. ,
F D. -All non-committed fire doors are being marked with permanent signs. Any doors which are not required to be maintained in a closed position will also-be marked with permanent signs to indicato'this condition and avoid ,ny confusion. This action will be completed by March 1, 1990.
3.. Date of Full Compliance A. The Maintenance Section will be in full compliance by March 1, 1990.
l B. Tho~ Radiation Protection Section will be in full compliance by September 30, 1989.
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f DUKE PGER COMPANY L REPLY 10 A WEAKNESS (IFI) ,
50-413,414/89-094)7 c
In the Independent Verification and Safety Tag procedures, three items of potential improvement are identified. (paragraph 2.1)
RESPONSE
- 1. JCorrective Action Taken and Results Achieved A. Based on operr. tor. knowledge of the independent verification process and its intent combined with our past record of minimal errors, we believe-the efficiency of operation out weights the effectiveness of the recomended practice. No cortective action will be taken.
l: - B. Verification of vaNa position by remote indication satisfies the requirements
, cof independent verification and also accomplishes the job with respect L to dose-ALARA. Operators are trained-to be alert to signs of material L. ' degradation'of components whenever they are observed. Based on current l'
operating practices we do not believe that the remote verification of "
valve' position constitutes a deficiency. No corrective action will be taken.>
r L C. Plant procedures will be revised to direct the operator to include on l the Removal and Restoration tagout sheet (R&R),'in addition to the isolation
. boundary valves,~the valve on which maintenance is actually-being performed.
'All other valves inside the boundary remain in the position required by their operating procedure. Change from this required position muct be
.docunented on the R&R sheet.
- 2. Corrective Action to be Taken to Avoid Further Incidents, A. Corrective action stated in item 1 shall resolve the recognized deficiency with no further action required.
- 3. Date of Full Compliance Duke Power will be in full compliance by December 1, 1989.
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DUKE POWER COMPANY k-REPLY TO A WEAKNESS.(IFI) i 413,414/89-09-08 Several deficiencies were noted'during observation of a
-performance test on one of.the Containment Spray pumps !
(paragraph-2.m.).
- 1. No.Section 2.0 reference for the KF system.
2.-Momentary lack of adequate miniflo during throttling process. *
- 3. Significant digit mismatch between acceptance criteria and available data. .
i 4.' Poor communication between remote location of throttle valve and meter that reads flow.
- 5. Instrument 1NSTH5010 broken with an incorrect laminate tag. Also, NS Pump-1B motor covers were either' loose or missing.
RESPONSE
- 1. Corrective Actions Taken and Results Achieved.
.A. Item 1 will'be resolved by climinating all valve t lineup references to'KF valves on the subject procedurc~and the other threc NS pump procedures.
KF101B'and KF103A valves on both units are not required to perform an IWP test on these pumps.
B. Item 2 will be resolved by noting throttle valvo-positions for each NS pump after flow has been setup. This information will be used to accurately determine the " Required Initial Test Position" in both the periodic test procedure lineups as.well as the Operations' ops.
C. Even though the accuracy specified in the procedure (i.e. to a tenth of a gpm) exceeds that available from the instrument, the acceptance criteria for the test can still be met by reading a value of 615 -
625 gpm which is within the instruments capability.
l The instrument in question meets the IWP requirement for accuracy. For this reason we feel a change to L the procedure is not required at this time.
D. Item 4 has been evaluated by Performance and determined not to be a significant weakness provided 1 I
Item 2 is resolved.
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iL - Item Sa is being'followed up and will bc:rcsolved p' with'a work' request'if problem is~still outstanding. ,
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' Item 5b has been resolved by initiating a'chango to the NS pump'procedurcs. Motor cover removal and replacements will now bo performed per those procedures.
- 2. Corrective-Actions to be Taken to Avoid Further I Incidents. ,
A._ Normal periodic procedure upgrades should correct similar weaknesses to Item 1 in otaer procedurcs if they exist'.
B. A review of other IWP procedurcs revealed no problems similar to Item 2.
C.. Not applicable.
D. Not applicabic with the resolution of Item 2.
E. Item 5a is not considered a generic problem. No r
- 'further action deemed necessary. Item 5b
- Motor cover removal and replacement on certain IWP tested pumps aro_now performed por their respectivo
' procedures.
- 3. Date of Full Compliance.
Duke Power will bc in full compliance where deemed necessary on January 1,.1990.' Item-2 cannot be resolved-until all the NS pumps' arc retested. These pumps-are tested quarterly.
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L DUKE POWER COMPANY REPLY TO A WEAKNESS (IFI) g -
413,414/80-09-09 t' .,
Scaffolding procedures do not address seismic considerations and resultant inoperability;of safety equipment. (paragraph 2.r.)
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1.- Corrective Actions Taken and Results Achieved. ,
A. A' review of existing scaffolds was performed-by Design Engineering personnel.. No areas of concern relative to installed scaffolds were r identified.
U B.- .The scaffold crew personnel assisted in the review addressed in A above. Through this review, the crew members have become aware.of concerns based on seismic considerations.
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' 2 .~ Corrective Actions to be Taken to Avoid Further Incidents.
A. A guideline is being developed to address the administrative controls '
and technical details concerning the erection of scaffolds. This ,
j' guideline is being developed by a team of representatives from various L Duke Power departments.
I B. - A site specific procedure will be generated to include information from the above guideline and to address seismic considerations in the ,
erection of' scaffolds.
- L 3. Date of Full Compliance.
The date of full compliance will be July 1, 1990.
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? Duke Power Company F Reply to a Weakness (IFI)
' > 413, 414/89-09-10 h
- i. " .-IAE Maintenance does not use portable equipment to facilitate timely locating of DC ground faults. -(paragraph 2.5) !
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RESPONSE
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- 1. Corrective Action Taken and Results Achieved A. A review of the practices for locating DC ground faults was undertaken. -The supervisor _ felt that he was unable to use the portable ground locating equipment because of its sensitivity.
This equipment is so sensitive that it picks up noise from surrounding AC circuits, to the point that you can't distinguish the tone received when a ground is present because the noise =from surrounding AC circuits is too loud. We have contacted McGuire personnel about the equipment they use that is similar to ours. They have experienced the same problems even after special filters were installed on their tester at
- the factory. This test equipment is a model 201002 DC ground fault detector made by Electrom Co.
B. We are actively trying to check for DC ground faults by using other types of test devices that would allow us to test with the circuits energized. .
2.. -Corrective Actions to be Taken to Avoid Further Incidents A. We have obtained an additional piece of test equipment that
- i. will enable us to test for and locate DC ground faults more efficiently. We feel that we can better locate DC ground
.7 faults than with the model 201002 tester.
Our approach will be to ask Operations personnel to
^
B.
de-energize any circuits on the bus that will have no impact on the safe operation of the plant. If the ground still is present, we will then test the active circuits with our tester until the ground is located.
C. A thorough review of all avenues will be conducted to ensure the most efficient way to locate DC ground faults is used.
- 3. Date of Full Compliance This information will be covered with all IAE Supervisors and General Supervisors at Catawba Nuclear Station by October 30, 1989.
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DUKE POWER COMPANY ,
REPLY 10AWEAKNESS(IFI) 50-413,414/89-09-11 TherearemanysignificantdeviationsbetweentheEDPsand.thePSIG(PlantSpecific Technical Guidelines) where there should be none. This is primaril being made in the EDPs before being made in the guidance document PSIG). (y due to chang y 3andAppendixB)
RESPONSE
1 '. Corrective Action Taken and Results Achieved.
.A plan has been agreed upon between the Safety Analysis section and the station Document Development section to review all the coments in Appendix B listed as PSIG Deviations. The result of this review will be a change to either
. doctanent so that the difference in guidance is eliminated. Technical Verification of_the E0Ps, a required step in the Verification and Validation program, will serve as the process by which this plan will be implemented. The Safety Analysis
'section performs the Technical Verification process. All of the identified deficiencies will be corrected through this review process by 12-31-90.
- 2. Corrective Action to be Taken to Avoid Further Incidents.
The Technical Verification process is designed to provide a means by which changes made to the EDPs are verified to be technically correct. Verification of technical correctness may lead to a modification of the PSIG, with appropriate justification, or a rejection of the E0P change as written. This process provides a functional means to ensure the E0Ps accurately and consistantly reflect the guidance in PSIG. Sufficient resources and timely efforts will
'be committed to this process to avoid future inconsistencies between E0Ps ,
and PSTU.
- 3. Date of Fbil Compliance.
Duke Power will be in full compliance by December 31, 1990. ;
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REPLY 10AWEAKNESS(IFI) c 50-413,414/89-09-12 Many technical and human factor discrepancies were identified in the EDPs. .
Eachoneislisted(paragraph 3.b.andAppendixB).
RE51MSE:
- 1. Corrective' Action Taken and Results Achieved A.. A formal process for the inclusion or dismissal of the items listed in Appendix B into the E0Ps has been planned, but not implemented.
Consideration will be given to each item based on the benefit realized to make the procedure more user friendly or technically correct. To ensure those items deemed beneficial are incorporated into the procedure properly and consistantly, the actual rewrite of the E0Ps will follow the publishing of the revised EP/AP Writer's Guide.
l- B. A0Ps are currently under revision to upgrade them to the current standard for E0Ps. The AOP revision took priority over the E0Ps based on the recuest of licensed operators and the inspection team's recomencation. Complete revision of the A0Ps to address l
the items identified by the inspection team will be accomplished I after the publishing of the revised EP/AP Writer's Guide.
l: C. Discrepancies between PSIG and E0Ps will be resolved in the process
! of Technical Verification of E0Ps during the revision to address inspection team concerns.
- 2. Corrective Action to be Taken to Avoid Fbrther Incidents.
A. -Revising of the EP/AP Writer's Guide will establish a new standard
'for future EDP/AOP development. The methods for maintaining the L standard and are already)
Validation established (V&V processes and well as descrfoed docmentedManagement in Operations by the Verification Procedures.
B. AOPs, which were not formally subjected to the V&V process in previous revisions, will be scrutinized under V&V criteria in subsequent revisions.
- 3. 'Date of Full Compliance.
Duke Power will be in full compliance on December 31, 1990.
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i DUKE F0WER COMPANY l
REPLY 'IU A WEAKNESS (IFI) 50-413,414/89-09-13 Many. labeling discrepancies between E0Ps and panel indication were identified.
Each one is listed. (paragraph 3.c and Appendix D)_
RESPGtSE:
g 1. Corrective Action Taken and Results Achieved.
A. Consideration of the-labeling discrepancies noted in Appendix D will be_ accomplished during the revision of the EP/AP Writer's Guide. Control board / panel labeling is not necessarily the nomenclature by which the operator identifies his indication / controls. Based on training and day to day operation, a functional nomenclature has evolved. Guidance provided to the procedure writer in the
-EP/AP Writer's Guide must allow enough flexibility so that nomenclature familiar to the operator can be used.
B. Consideration of the labeling discrepancies will also include proposals'to change control board / panel labeling so as to more functionally describe the indication / control items.
- 2. Corrective Action to be Taken to Avoid Further Incidents.
i A. Revising the EP/AP Writer's Guide to establish a standard for referring to indications /and controls and maintaining the standard by the Verification and Validation processes will provide a method of quality control for the E0Ps and A0Ps.
l- B. Control board / panel nomenclature is a controlled item. To change chis nomenclature requires approval of management at various levels
! based on plant configuration control. 'Ihis process is considered l adequate and will not require modification to make changes, deemed necessary, based on this inspection.
I'
- 3. Date of Full Compliance.
I l Duke Power will be in full compliance with our commitment to consider I
the labeling concerns listed in Appendix D by June 1, 1990. Based on the EP/AP Writer's Guide, those concerns involving only a procedure revision will be completed by Dec 31, 1990. For those items of concern L requiring Control Board / panel labeling modification, the full compliance l- date will coincide with the end of the respective unit refueling outage in 1991; 1EOC5 and 2EOC4.
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[i DUKE IOER 00MPAW REPLY 10 A WEAKNESS 50-413,414/89-0)-14 ancy between the E0Ps and the S/G pressure meter in !
There is a room the control discrep(paragraph 3.c and Appendix B item 1.g.)
RESIMSE:
- 1. Corrective Actions Taken and Results Achieved.
The marking of the S/G steam pressure gauges has been addressed by originatic<a of work requests 432120PS and 511720PS (Unit 2 and Unit 1respectively). The ranges, which depict abnormal conditions for normal at power operation, have been specified. The corrective action will redesignate the lower red range on each S/G pressure meter starting at 725 psig (Iow S/G Steam Pressure SI setpoint) and ending at 0 PSIG on the scale. This work requires removal of the meter from the control board and thus has not been completed with the units at operating temperature and pressure.
- 2. Corrective Actions to be Taken to Avoid Further incidents.
The red range marking of control pnel meters is a functional process and considered an operator aid, wien performed correctly. Individual responsibility for this process has been reassigned to better utilize our personnel resources and assure the process functions as intended.
- 3. Date of Full Compliance.
- Duke Power will be in full compliance by the end of the next scheduled refueling outage 1EOC-4, 2EDC3 (Unit 1, Unit 2 respectively) 1990.
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L. j 1 L DUKE POWER 00NPANY REPLY 10 A WEAKNESS (IFI)'
50-413,414/89-09-15 Many writer's guide discrepancies were identified in the EDPs. Each one is. listed (paragraph 3.c. and Appendix C). ,
RESPGtSE:
- 1. Corrective Action Taken and Results Achieved.
A.- A decision has been made to revise the EP/AP Writer's Guide.
Based'on the comments of the inspection team, it is evident that more detailed guidance should be provided te the E0P and AOP writer.
B. Many of the discrepancies noted in Appendices B, C and D can only be addressed after decisive guidance is established in the EP/AP
-Writer's Guide. Thus revisions to the E0Ps and A0Ps will be made based on the revised EP/AP Writer's Guide and comments deemed appropriate from reports 50-413,414/89-09.
- 2. Corrective Actions to be Taken to Avoid Fbrther Incidents.
A. IbecurrentprocessesofVerificationandValidation(V&V) provide an efficient and adequate means of assuring BOPS conform to written guidance. No corrective action is necessary.
B. AOPs will be subjected to the V&V processes to assure conformity with written guidance and compatibility with operational experience.
.3. Date of Full Compliance.
Duke Power will be in full compliance with regard to the EP/AP Writer's Guide by June 1, 1989 and, with regard to the revised E0Ps and A0Ps, by Dccember 31, 1990.
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DUKE POWER COMPANY I REPLY 'IO A WEAKNESS (IFI) _
50-413,414/89-09-16 '
' Noise level in the control room'during auto-start of both ventilation trains during S/I' response is excessive (paragraph 3c).
RESPONSE
- 1. Corrective Action Taken and Results Achieved.
'A design ~ study has been initiated to review the problem with excessive noise in the Control Room due to'the operation of the ventilation system.- A test-will be performed to determine noise levels'for various configurations'of_
the ventilation system. Based on the test results a resolution of the problem will'be proposed to management for corrective action.
-2. Corrective Action'to be Taken to Avoid Further Incidents.
-Corrective action taken, based on' proposals by the design study stated in item 1', should resolve the recognized deficiency with no further action required.
- 3. Date of Full Compliance. .!
-Dateoffullcompliance'isdcpendantonthecomplexity;oftheproposedcorrective
. action. Duke Power will have a proposal for corrective action by December
'31, 1989.
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L REPLY 'IO A WEAKNESS (IFI) 50-413,414/89 09-17
_ Deficiencies were identified in simulator effectiveness in training on I.DPs (paragraph 3.d). . s RESPONSE: ,
- 1. Corrective Action Taken and Results Achieved.
A. . % e concurrent use of A0Ps is.-justifiable based on the quantity and control of-resources available during a multi-failure scenario. By conscientious decision the Shift Supervisor may-use more than one AOP at a time. Bis is. allowed-since the AOPs are written to provide various options to sta'ullize the plant after a particular malfunction. We do not consider this a deficiency.
i B.- he E0P/A0P' filing methods will be reviewed to determine whether an identification-and retrieval problem exists for Control Room personnel.
We deficiency noted:was based on the observation of a staff person'c performance. Appropriate corrective action will be taken, if required. !
C. Entry conditions.for EDP/A0Ps will be reviewed in conjunction with the !
review of procedures for other deficiencies noted in this report. Le j E0P/AOPs will be revised as. deemed necessary.
- 2. Corrective Actions to be Taken to Avoid Ebether Incidents. j i
A. Discrepancies discusr.ed in Item 1, with exception of 1.c., are not expected i to recur . B us surveillance programs, to monitor for the repetition t of the; discrepancy, are not required.
B. ~ h e EP/AP Writer's Guide and the Verification and Validation processes i will ensure that future revisions to E0P/A0P entry conditions are written to'an established standard.
3.- Date of Full Compliance: !
Duke Power will be in full compliance for the following corrective actions as listed: ;
. E0P/AOP filing method review -
January 2, 1990
. BOP /AOP entry condition review - December 31, 1990
$? ,s 3)fd? ( 3 f Jel l i,n DUKE POWER COMPANY REPLY TO A WEAKNESS (IFI) 413,414/09-09-18 Weakness noted in the site's ETQS (Employee. Training and Qualification System, paragraph 4.a.).
RESPONSE
a .
- 1. ' Corrective Actions'Taken and Results Achieved. i
- v. . , l
~The new Mechanical Maintenance ETQS program is still being developed.-
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We are working with McGuire, Oconee and the training organization to
' finalize all aspects of the new program. The task rewrite is
~
1 approximately.95% complete. The continuing training plan is being ,
-developed by Production Training Services (PTS), with input from the i stations and' changeover qualification from old tasks to new tasks-should be. started by November'1, 1989. We will not begin our communication to all personnel until the program is finalized. .)
- 2. Corrective Actions to be Taken to Avoid Further Incidents. 1 I
A. 'The new program is scheduled to be implemented by January 1, 1990.
g- B... We will communicate, through crew meetings, the requirements of the !
new program to all Mechanical Maintenance Personnel.
"3. Date of Full Compliance.
The: communication to personnel will be completed by March 1, 1990.
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-REPLY TO A WEAKNESS (IFI) -l
^
i- 413, 414/89-09 x There-are approximately 131 temporary modifications in effect on site. -Some date back as far as 3 or 4 years.- l i RESPONSE: !
l 1.1 ' Corrective Actions Taken and Results Achieved.
L
.In 1986 Catawba Nuclear Station had approximately 320 TSM's
- i. 4 t installed. LAt that time a working group was formed to f identify who was responsible for each TSM and what it would L require to clear them. Most of the older TSM's'which are-installed have' required modifications to be originated to- -
E -clear.them. The Station Directive (4.4.5) has'been-revised' several1 times:since 1986 and it is now clear that the Temporary Modification program shall=not be used to bypass the normal modification process for changes that are
,1 intended to remain permanent. ,
l.
- 2. -Corrective Actions to be Taken to Avoid Further Incidents All TSM's-have been reviewed to determine an estimated clearing date and.what station group is responsible for i clearing the TSM.- Approximately fifty percent of the .'
-installed TSM's have been identified to clear during the upcoming Unit 1 and Unit 2 outages in 1990.- The remaining TSM's are not tied to an outage, but do have a current estimated clearing date. ,
'3. Date of Full Compliance
, Catawba Nuclear Station is in full compliance with this
- issue at this time. Catawba h'as significantly reduced the number of TSM's and has an estimated clearing date assigned to all installed TSM's.
According to the Catawba Nuclear Station Performance Indicators, the station's goal is to maintain the number of TSM's to no more than 60. This is a new indicator which is just beginning to be looked at. Catawba expects to achieve this goal by October 1, 1990.
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DUKE POWER COMPANY.
1 REPLY 'EO A WEAKNESS (IFI) :;
s .
413;;414/89-09 :
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.; The' separate' reporting authority : arid duplication of support u
^ ^ functions: for the Transmission- Group is considered a i weakness.
JRESPONSE:
Upon l review of the report several-areas are in need of further explanation. ,
The report Estates that Transmission has its. own procedures, training. program,. l u and equipment calibration. program which is true. These. procedures and programs - '
q L were Lall; developed specifically to support Transmission and Distribution personnel 1 m in performing : their assigned L work activities .at the nuclear stations. Also,,
y' i these programs andiprocedures, must meet the same. requirements as those of other
. departments. and in manyx: cases fall under Nuclear Production Department . (NPD)
' policies: and procedures., For J example, procedures used by Transmission.and-1 Distribution -~ (T&D) personnel at the station are originated by ' T&D engineering. >
personnel; however,' the procedures are the same'as any other station procedure-
' and 'must. follow the same station approval process. The only major difference is the originating group, b . Training programs for T&D personnel are developed in cooperation with the l Production: Support Department which also coordinates with other - departments in a- - similiar - fashion. . These ' programs are tailored specifically for T&D personnel, and the- type of work performed by the department .at the station. ,'
They. may; or may not' be the same as other departments programs- depending on the p <
l needs' identified. e J '
'The equipment calibration program allows T&D personnel to have their equipment calibrated .at a central location thereby not having to make ~special trips to
!thes stations. to constantly drop off and pick up equipment. - This equipment is used by~T&D-personne1'at other company locations, and the central location offers
- l. convenience and efficient service. .
s
, The report also focuses on limited resources available to support T&D c . activities, The amount of resources assigned to any task should be commensurate
- a
- .with the identified need. This approach has been used in each area pertaining
.to nuclear related activities. Resources for required work are made available onL an' as 'needed basis without comparison to resources supplied by other
. departments and are considered a normal overhead expense associated with nuclear maintenance work.
In. summary, the weakness noted by the report is not perceived as a true weaknes.s. First, the fact that separate reporting authority exists does not necessarily indicate that changes to station programs will not be implemented in kind in the T&D Department, f 5
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Effective communication, administrative controls, and audit. practices help ensure
. this ' continuity. Second, the' duplication of service in -this case i s a more - .
efficient and productive way of providing support for T&D personnel performing ,
work - ati the stations. Procedures - are written by engineeering personnel who 1
have the necessary: experience with .the equipment and the maintenance activities -!
. to - be performed. - Training programs are- tailored to specific T&D needs which may be.different.from those of station personnel.- Finally, equipment calibrations are performed at a central-location- to accommodate T&O personnel that must work at other Duke locations.
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