|
---|
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
,
p 1
l JAN l 2 S93 i Duke Power Company ATIN: Mr. M. S. Tuckman Vice President Catawba Site 4800 Concord Road York, SC 29745-9635 Gentlemen:
SUBJECT:
REQUALIFICATION PROGRAM EVALUATION - CATAWBA NUCLEAR STATION EXAMINATION REPORT NO. 50-413/93-300 Arrangements have been made between Mr. Wendall Barron, Director, Operator Training, and Mr. Garry Harris, License Examiner, for an evaluation of the requalification program and licensed personnel at your Catawba Nuclear Station. The examination preparation visit is scheduled for the week of April 26,1993. The evaluation visit is scheduled for the week of May 10, 1993. The requalification examinations and the subsequent evaluation of the facility requalification program will be performed in accordance with Sections 501 through 604 of NUREG 1021, Operator Licensing Examiner Standards, Revision 6. You are encouraged to ensure that your training staff and proposed examinees are familiar with these standards.
Please note that Revision 7 of the Examiner Standards may be available for use -
by the time of the examinations. We will coordinate with your staff to deter-mine whether you would prefer to be evaluated under the new or old standards.
In addition, a written retake examination will be administered to those candidates who failed the initial examination administered in October, 1992.
This examination will be administered during the requalification preparation visit.
For the examiners to adequately prepare for this visit, it will be necessary for the facility to furnish the approved items listed in Enclosure 1,
" Reference Material Requirements." Failure to supply the reference material as required by Enclosure 1 may result in postponement of the examination. The Chief Examiner may request that the facility submit a proposed examination for use during the examination week in addition to the material requirements of Enclosure 1. Submission of a proposed examination, even if requested, is optional. However, if a proposed examination is submitted, those personnel participating in its development may become subject to the security restrictions described below. Mr. Barron has been advised of our reference material requirements, whether a proposed examination is requested, and where these items are to be sent.
Your attention is directed to the guidance promulgated in Revision 6 to NUREG-1021 pertaining to the content and scope of simulator examination f scenarios. The scenario examination bank should cover the entire spectrum of l
9301260062 930112 l PDR ADOCK 05000413
1 i
l Duke Power Company 2 JAN I 219%
i Emergency Operating Procedures (EOPs), including alternate decision paths l withi.n E0Ps, and incorporate a range of failures with varying degrees of severity for the same type event. Each scenario should-contain simultaneous ,
events that require prioritization of actions and allocation of resources, and !
should exercise E0Ps in-depth, i.e., sr:narios require transitions and/or H decisions to be made on actions to take within the E0Ps.
You are requested to designate at least one employee to be a member of a joint NRC-facility examination team. The employee shall be an active SR0 (per the requirements of 10 CFR 55.53(e) or (f) from the Catawba Nuclear Station Operations Department. You are encluraged to designate a second employee from .
the training staff to be a member of the examination team. This employee _ _ l
, should be an active SR0 (per the requirements of 10 CFR 55.53(e) or (f)), but may be a facility or INP0 certified instructor. If desired and agreed to by the Chief Examiner, you may designate one additional employee from the training staff with appropriate qualifications to be a member of the l examination team, in addition to these individuals, a simulator operator must j be made available for scenario preview and validation during the on-site ,
examination preparation week. In some cases, it may be necessary to designate I a simulator operator during the test item review period. This individual will also be subject to the examination security agreement.
Any facility representatives under the security agreement shall be restricted from knowingly communicating by any means the content or scope of the examination to unauthorized persons and from participating in any facility programs such as instruction, examination, or tutoring in which an identified requalification examinee (s) will be present. These restrictions shall- apply from the day that the facility representative signs the examination security agreement indicating that the representative understands that he or she has-specialized knowledge of the examination. The Chief Examiner will determine when facility representatives have received specialized knowledge concerning the examination and require execution of an examinatio_n security agreement.
In most cases, the examination team member.s will not be required to enter into an examination security agreement more than 60 days prior to the examination week. The simulator operator will normally become subject to the requirements during the examination preparation and validation week, but in some. cases, this may occur as much as 30 days prior to the examination week to support operating test item review and revision.
Sixty-days prior to the examination-administration date, the facility training staff shall identify and provide directly to the NRC's Chief Examiner a list of .the proposed operators, including crew composition, for~ the examination.
.Also, to ensure privacy, the only copy of the current mailing address and Part 55 docket number of each proposed operator should be mailed in an envelope labeled "To Be Opened By Addressee Only" to the attention of Mr.
Thomas A. Peebles, Chief, Operations Branch, Division of Reactor Safety, Region II.
Duke Power Company 3 JAN I 21993 l
The- facility management is responsible for providing adequate space and l
accommodations to properly develop and _ conduct the examinations. Enclosure 2, !
" Administration of Requalification Examinations," describes our re'quirements ,
for developing and conducting the examinations. Mr. Barron has also been :
informed of these requirements. Also, a facility' operations management- l representative (as a minimum, first level above shift supervisor) should !
observe the simulation facility examination process at the site.
This request is covered by Office of Management and Budget (OMB) Clearance Number 3150-0101,-which expires October 31, 1995. This estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, xeroxing, and mailing the required material. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggesticns for l reducing this burden, to_the Information and Records Management Branch, MNBB-7714, Division-of =Information Support Services, Office of Information_
Resources Management, U. S. Nuclear Regulatory Commission,_ Washington, D. C.
20555, and to the Paperwork-Reduction Project (3150-0101), 0ffice of Information and Regulatory Affairs, NE0B-3019, Office of Management and Budget, Washington, D. C. 20503.
Thank you for your_ consi.deration in this matter. If you have any questions on ~
the evaluation process, please contact Mr. Michael Ernstes, Chief, Operator d-Licensing Section-2, at (404) 331-5594, or myself at (404) 331-5541.
Sincerely, ORIGINAL. SIGNED BY T. A.PEEBLES Thomas A. Peebles, Chief Operations Branch Division of Reactor. Safety
Enclosures:
- 1. Reference Material Requirements
- 2. Administration of Requalification Examinations
- 3. NRC Rules and Guidance for Examinees cc w/encls:
W. R. McCollum, Jr.
Station ~ Manager Catawba Nuclear ~ Station
__ Duke Power Company _
4800 Concord Road York,.SC 29745-9635 (cc w/oncls cont'd - See page 4)
.-_ _ _ = _ .
=
Duke Power Company 4 JAN 121993-1 l
cc w/encls cont'd.
W. H. Barron, Director Operator Training i Catawba Nuclear Station !
Duke Power Company 4800 Concord Road York, SC 29745-9635 R. C. Futrell 1 Compliance Duke Power Company 4800 Concord Road York, SC 29745-9635 A. V. Carr, Esq.
Duke Power Company 422 South Churth Street Charlotte, NC 28242-0001 J. Michael McGarry, III, Esq.
Winston and Strawn 1400 L Street, NW Washington, D. C. 20005 North Carolina MPA-1 Suite 600 P. O. Box 29513 Raleigh, NC 27626-0513 Heyward G. Shealy, Chief Bureau of Radiological Health S. C. Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Richard P. Wilson, Esq.
Assistant Attorney General S. C. Attorney General's Office P. O. Box 11549 Columbia, SC 29211
-Michael Hirsch
. federal Emergency Management ' Agency 500 C Street, Sw, Room 840 Washington, D. C. 20472 (cc w/encls cont'd - See page 5)
i l
Duke Power Company 5 JAN I 21993 1 cc w/encls cont'd:
North Carolina Electric Membership Corporation P. O. Box 27306 Raleigh, NC 27611 Saluda River Electric Cooperative, Inc.
P. O. Box 929 Laurens, SC 29360 Karen E. Long Assistant Attorney General N. C. Department of Justice P. O. Box 629 Raleigh, NC 27602 T. Richard Puryear Nuclear Technical Services Manager Carolinas District Westinghouse Electric Corporation P. O. Box 32817 Charlotte, NC 28232 County Manager of York County York Ccunty Courthouse York, SC 29745 Piedmont Municipal Power Agency 121 Village Drive Greer, SC 29651 R. L. Gill Nuclear Generation Department Mail Stop EC050 Duke Power Company P. O. Box 1006 Charlotte, NC= 28201-1006 bcc w/o encls:
S. Ebneter, RA A. Gibson, DRS R. Martin, NRR W. Miller, DRP' G. Belisle, DRP (bec w/o encls cont'd - see page 6)
Duke Power Company 6' JAN - l 2 1993 bec w/o encls cont'd:
A. Herdt, DRP' J. Moorman, DRS 'l G. Harris, DRS l l
U.S. Nuclear Regulatory Commission ATTN: Mr. W. Order, Senior Resident l Inspector (Catawba) ;
Route 1, Box'179-N i York, SC 29745 l
bec w/encls Document Control Desk 4
RII:DRS RII:DRS RII:D M4N, /ht %
CHarris:sd- MErristes T les 01//1./92 01/gt /92 01/j1./92 ;
doc name: g:\la\ catawba \r30090da.gah
{ .
_ ._ -_. _ - _ . _ ._ . _ . _ , _ _ -_. _ . _ _ _ _ _ _ . m.. . ,
ENCLOSURE l j
REFERENCE MATERIAL-REQUIREMENTS Test items to support all aspects of the requalification examination must be -
provided to the NRC 60 days prior to the examination date. !
All test items should be developed in accordance with the guidelines provided_ l in Sections 602 through 604 of NUREG 1021, Operator Licensing Examiner Standards, and their respective attachments.
For the first requalification evaluation at the facility, the submittal must contain at least: . ,
H 700 test items for use in the written examination. They should be '
equally divided between the two sections of the examination, and there .
must be at least 350 test items for use in each section. =
75 Job Performance Measures (JPMs) for use on the walk-through portion of the operating examination. To the extent possible, approximately 40 percent of the JPMs should evaluate "in plant" tasks (system / component operation outside the control room).
15 simulater scenarios of approximately 50 minutes each in length for _use on the simulator portion of the operating examination for examinations administered in one week.
For subsequent requalification examinations facilities are expected to make submittals reflecting progress toward the following targets over the next five years after the initial evaluation visit:
A minimum of 700 test items for use in the written examination equally
- divided between the two sections of the written-examination and which-cover all safety-related elements of the -facility Job Task Analysis (JTA). The bank shall be dynamic in nature, in that at least 150 questions a year shall- be reviewed, revised, (n' generated. New questions that are developed should cover equipment and system modifications, recent industry, and licensee events and procedural changes.
JPMs to evaluate each operator and senior operator safety-related task-identified in the ' facility JTA, which meet the criteria in ES-603. The-JPM bank should-expand-at a rate of at least ten JPMs per year untilithis goal is reached. It is estimated at l' 5 i - 150 JPMs will be the final result. Development of the questions associated with the JPMs shall also Lcontinue, such that there is a representative sample of- questions given the knowledges associated with the-task listed in the; JTA.
A bank of- at least-30 simulator scenarios which reflect all plausible or expected. abnormal-and emergency situations to which control room operators are excacted to respond or control. At least' five scenarios per year should be generated until all -aspects of the emergency operating .
procedures are covered with sufficient variation in the type and-scope of-initiating events and level of degradation.
> . , - - % e-- v rs-* -***
Inclosure 1 2 for all requalification examination and evaluation visits, the f acility shall:
Submit an Examination Test Outline / Sample Plan which meets the requirements of ES-601, Attachment 1.
Provide the associated examination banks (written, simulator, and JPM) and associated reference material to the region and contractor. At a minimum, this shall include Technical Specifications, applicable plant operating, surveillance and administrative procedures, abnormal and emergency operating procedures, emergency plan procedures, and training material utilized in the requalification training (including student handouts and lesson plans). Additional reference material may be requested by the Chief Examiner, if a proposed examination is submitted to the region, also submit a copy of the simulator scenario portion to the Chief, Regional Support and Oversight Section, Operator Licensing Branch, Division of Licensee Performance and Quality, Washington, DC 20555, 45 days in advance of the first day of the examinations. The reason for the increased period of days is to allow a reasonable amount of time for feedback, discussion and time to make any necessary changes, i
l l
J ENrLOSURE 2
, J ADMINISTRATION OF RE0VAllFICAT10N EXAMINATIONS l J
- 1. An evaluation of at least 12 facility licensed operators is required for 1 a program evaluation. Normally the crew scheduled for requalification j training during the period selected for the program evaluation should be i selected. The sample will include other licensed operators who are not -
routinely performing shift duties or are not maintaining an active license per 10 CFR 55.53(3). The restrictions on crew composition in the simulator are described in ES-601 C.I.b. and ES-604,
- 2. The simulator and simulator operator (s) shall be provided for examination ,
development. The date(s) and duration of time needed to develop the examinations will be agreed upon by the Chief Examiner and the' facility.
- 3. The reference material used in the simulator will be reviewed by the Chief Examiner. No material will be used that is solely used _for
- 4. A single room shall be provided for completing Section B of_the written examination. The location of this room and supporting rest room facilities shall be such as to prevent contact with all other facility ;
and/or contractor personnel for the duration of the examination.
- 5. Minimum spacing is required to ensure examination integrity and will be evaluated by the Chief Examiner. Minimum spacing consists of one '
examinee per table and a 3 foot space between tables. No wall charts, -
models, and/or other training materials shall be present in the examination room.
- 6. Copics of reference material for Section B of the written examination '
shall be 3rovided for each examinee. The reference material will. be reviewed )y the Chief Examiner and will consist of Technical Specifications, operating / abnormal procedures, administrative procedures, ,
and Emergency Plans as available to the plant operators. ;
- 7. Video taping capabilities may- be- utilized. 'The facility should contact the Chief Examiner for restrictions related to its usage.
- 8. An attempt will be made to distinguish between R0 and 'SR0 knowledge and abilities to the extent that such a distinction is supported by the facility training materials.
- 9. Prudent scheduling of exam week activities is important to help alleviate-undue stress.on.the operators. Your training staff and the Chief Examiner should work very closely in formulating a schedule which does . -
not result in excessive delays in crews or individuals being administered.
- their examination. The following are some suggestions for structuring' the exam activities to achieve this purpose: r
)
f
%-we,- r-,e. * - - . , , , - , - ---rwwr, --..-e....,4-.w. . - - - , . . , , - + - . . - .--4, ,.--.---.r- ,,e.. .--.+-~--...-%.,v.--.m- - - - . . - . . - , e e e- -+w-.-e-
1 Enclosure 2 2 Don't oring in crews or individuals well before their scheduled exam times.
When examining operators in groups, it is better to hold the group ;
just completing their exam vice the groups that are taking their l exam later. q following simulator sce -ios, the facility evaluators and NRC I examiners should quickly determine whether follow up questioning is !
required, so that the crew may be released to talk among themselves about the scenario. -
Ensure that time validation of JPMs, particularly those 1erformod in l the simulator, is conducted accurately. A reasonable sc adn'e ,
should be established to prevent operators from waiting -for simulator availability to complete their JPMs.
l l
l l :
!~
i b
r l
i INCLOSVRE 3 l NRC RULES AND GU1 DANCE FOR EXAMINEES
- 1. Use black ink or dark pencil ONLY to facilitate legible reproduction.
- 2. Print your name in the blank provided on the cover sheet of the ;
examination. 1
't
- 3. fill in the date on the cover sheet of the examination, if necessary. '
- 4. Answer each question on the examination. If additional paper is required, use only the lined-paper _provided by-the examiner.
- 5. Use abbreviations only if they are commonly used in facility literature. ,
- 6. The point value for each question is indicated in parentheses after the-question and can be used as a guide for the depth of answer required.
- 7. Show all calculations, methods, or assumptions used to obtain an answer ,
to a short answer test item, whether asked for in the question or not. >
- 8. Unless solicited, the location of references need not be stated.
- 9. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each response will be worth 0.20 points, if one of your five responses is incorrect, 0.20 will be deducted, and your total credit for that question will be 0.80, even though you may-have listed the four-correct responses in the answer key.
- 10. Partial credit may be given, except on multiple choice questions.
Therefore, ANSWER ALL PARTS OF THE QUESTION, AND DO NOT LEAVE ANY ANSWERS BLANK.
- 11. If parts of the examination are not clear with respect 1to their intent, ask questions of the examiner only.
- 12. You must sign the statement on the cover sheet that indicates tho' work.on the. examination is your own and that you'have not received or been'given any assistance in completing the examination. This must be signed AFTER the examination has been completed. ,
- 13. Rest room trips are to be limited, and only one examinee at a time may leave. You must avoid all contact with anyone outside the examination-room to avoid even the appearance or possibility of. examination compromise.
- 14. Cheating on the examination would result in a revocation of your license and could result in more severe penalties. '
i inclosure 3 2
- 15. Each section of the examination is designed to take approximately 90 minutes to complete. You will be given two hours to complete each section to allow for thirty minutes of review.
- 16. The examination has been time validated by knowledgeable persons. You should be aware that not every answer needs to be verified by consulting a reference, and excessive usage of reference material may cause you to not complete the exam in the allotted time.
- 17. Due to the existence of questions that will require all examinees to refer to the same indications or controls, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating.
- 18. When you are finished and have turned in your completed examination, leave the examination area.
. - _ _ _ _ - _ - __-