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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210Q4611999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 ML20210G3351999-07-27027 July 1999 Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20210E0121999-07-23023 July 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D9341999-07-22022 July 1999 Discusses Closure of TACs MA0581 & MA0582,response to Requests for Info in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20210E0431999-07-15015 July 1999 Forwards Insp Repts 50-424/99-04 & 50-425/99-04 on 990502- 0619.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196H8081999-06-28028 June 1999 Discusses 990528 Meeting Re Results of Periodic PPR for Period of Feb 1997 to Jan 1999.List of Attendees Encl ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage ML20207E7421999-06-0303 June 1999 Refers to from NRC Which Issued Personnel Assignment Ltr to Inform of Lm Padovan Assignment as Project Manager for Farley Npp.Reissues Ltr with Effective Date Corrected to 990525 ML20207F6201999-06-0202 June 1999 Sixth Partial Response to FOIA Request for Documents.Records in App J Encl & Will Be Available in Pdr.App K Records Withheld in Part (Ref FOIA Exemptions 7) & App L Records Completely Withheld (Ref FOIA Exemption 7) ML20207D9861999-05-28028 May 1999 Informs That,Effective 990325,LM Padovan Was Assigned as Project Manager for Plant,Units 1 & 2 ML20207D2701999-05-19019 May 1999 Forwards Insp Repts 50-424/99-03 & 50-425/99-03 on 990321- 0501.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206M5141999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Rl Emch Section Chief for Vogtle. Reorganization Chart Encl ML20206U4061999-05-11011 May 1999 Confirms Telcon with J Bailey Re Mgt Meeting Scheduled for 990528 to Discuss Results of Periodic Plant Performance Review for Plan Nuclear Facility Fo Period of Feb 1997 - Jan 1999 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20206A6371999-04-21021 April 1999 Forwards SE Authorizing Licensee Re Rev 9 to First 10-yr ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20205Q3351999-04-15015 April 1999 Forwards Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320.Three Violations Identified & Being Treated as Non-Cited Violations ML20205T2351999-04-0909 April 1999 Informs That on 990317,B Brown & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Scheduled for Wk of 991213 for Approx 10 Candidates ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl 1999-09-20
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl ML20205H4051999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3891999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1).Page 2 in Third Amend Power Sales Contract of Incoming Submittal Not Included ML20205A9441999-03-25025 March 1999 Forwards VEGP Unit 1 Cycle 9 Colr,Per TS 5.6.5.d ML20205H3811999-03-24024 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3621999-03-22022 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81, as Requested IAW 10CFR50.75(f)(1) ML20204G4361999-03-18018 March 1999 Forwards Summary Rept of Present Level & Source of on-site Property Damage Insurance Coverage for Vegp,Iaw Requirements of 10CFR50.54(w)(3) ML20204C0591999-03-17017 March 1999 Forwards Rev 0 to WCAP-15160, Evaluation of Pressurized Thermal Shock for Vegp,Unit 2 & Rev 0 to WCAP-15159, Analysis of Capsule X from Vegp,Unit 2 Reactor Vessel Radiation Surveillance Program ML20207K9551999-03-11011 March 1999 Forwards Response to Rai,Pertaining to Positive Alcohol Test of Licensed Operator.Encl Info Provided for NRC Use in Evaluation of Fitness for Duty Occurrence.Encl Withheld,Per 10CFR2.790(a)(6) ML20207L9721999-03-10010 March 1999 Forwards Rev 15 to EPIP 91104-C of Manual Set 6 of Vogtle Epips.Without Encl ML20207B0191999-02-25025 February 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 980701-1231,IAW 10CFR26.71(d) 05000424/LER-1998-009, Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 9812291999-01-27027 January 1999 Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 981229 ML20199F7701999-01-13013 January 1999 Submits Revised Response to RAI Re Licensee 980713 Proposed Amend to Ts,Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Protection Channels. Corrected Copy of Table,Encl ML20199F7981999-01-13013 January 1999 Forwards Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage. Change Bar in Margin of Affected Pages Denotes Changes to Rept ML20199G1381999-01-13013 January 1999 Forwards Copy of Permit Renewal Application Package for NPDES Permit Number GA0026786,per Section 3.2 of VP Environ Protection Plan 05000424/LER-1998-007, Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.731999-01-13013 January 1999 Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.73 ML20198F6131998-12-18018 December 1998 Forwards Revised Certification of Medical Exam Form for License SOP-21147.Licensee Being Treated for Hypertension. Util Requests That Individual License Be Amended to Reflect Change in Status ML20198L6631998-12-18018 December 1998 Forwards Amend 37 to Physical Security & Contingency Plan. Encl 1 Provides Description & Justification for Changes & Encl 2 Contains Actual Amend 37 Pages.Amend Withheld,Per 10CFR73.21 ML20198D9291998-12-16016 December 1998 Forwards Requested Info Re Request to Revise TSs Elimination of Periodic Pressure Sensor Response Time Tests & Elimination of Periodic Protection Channel Response Time Tests ML20198D9991998-12-16016 December 1998 Forwards Responses to 980916 RAI Re Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations ML20198D8171998-12-14014 December 1998 Forwards NRC Form 396 & Form 398 for Renewal of License OP-20993.Without Encls ML20206N3051998-12-0808 December 1998 Submits RAI Re Replacement of Nuclear Instrument Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys 1999-09-20
[Table view] Category:UTILITY TO NRC
MONTHYEARELV-02056, Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam1990-09-0606 September 1990 Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam ELV-01599, Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator1990-09-0404 September 1990 Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator ELV-02059, Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B1990-08-30030 August 1990 Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B ELV-01956, Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request1990-08-30030 August 1990 Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request ELV-02050, Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required1990-08-30030 August 1990 Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required ELV-02028, Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d)1990-08-22022 August 1990 Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d) ELV-02022, Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld1990-08-22022 August 1990 Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld ELV-02027, Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively1990-08-20020 August 1990 Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively ELV-01973, Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical1990-08-14014 August 1990 Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical ELV-01918, Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion1990-08-0303 August 1990 Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion ELV-01943, Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned1990-07-27027 July 1990 Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned ELV-01949, Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable1990-07-26026 July 1990 Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable ELV-01500, Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities1990-07-25025 July 1990 Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities ML20055H6441990-07-23023 July 1990 Submits Summary of Snubber Types & Sample Plans for Functional Testing to Be Performed During Sept 1990 Outage ML20044B0311990-07-13013 July 1990 Forwards Vogtle Electric Generating Plant Unit 1 Reactor Containment Bldg 1990 Integrated Leakage Rate Test Final Rept. ML20044B1541990-07-12012 July 1990 Responds to NRC 900612 Ltr Re Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Eop Step Deviation Documents to Be Upgraded,Adding More Justification & Temporary Change Issued to Correct EOP Deficiencies ELV-01867, Responds to Violations Noted in Insp Repts 50-424/90-10 & 50-425/90-10.Corrective Action:Level Indication Error Corrected After Discrepancy Discovered1990-07-12012 July 1990 Responds to Violations Noted in Insp Repts 50-424/90-10 & 50-425/90-10.Corrective Action:Level Indication Error Corrected After Discrepancy Discovered ML20055F1651990-07-0909 July 1990 Forwards Comments Re NUREG-1410 ELV-01858, Advises That Full Compliance W/Violation Will Not Be Achieved Until Nov 1990,when Evaluation of VP-2693 Complete1990-07-0606 July 1990 Advises That Full Compliance W/Violation Will Not Be Achieved Until Nov 1990,when Evaluation of VP-2693 Complete ML20044A8851990-07-0606 July 1990 Forwards Response to NRC Question on Steam Generator Level Instrumentation Setpoints,Per Revised Instrument Line Tap Locations.Tap Location Will Be Changed from Above Transition Cone to Below Transition Cone ELV-01834, Forwards Response & Comments to Regulatory Effectiveness Review Rept.Encl Withheld (Ref 10CFR73.21)1990-06-28028 June 1990 Forwards Response & Comments to Regulatory Effectiveness Review Rept.Encl Withheld (Ref 10CFR73.21) ML20044A2791990-06-25025 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Indicating Status of Each Generic Safety Issue Encl ML20043J0171990-06-22022 June 1990 Discusses Corrective Actions for Plant Site Area Emergency, Per 900514 Ltr.Jacket Water High Temp Switches Calibr for Diesel Generators,Using Revised Calibr Procedure ML20043H3061990-06-15015 June 1990 Forwards Rev 3 to ISI-P-014, Inservice Insp Program, for Review & Approval,Per Tech Spec 4.0.5 Re Surveillance Requirements.Rev Includes Withdrawal of Relief Requests RR-45,47,48 & 54 ML20043G2071990-06-12012 June 1990 Forwards Amend 18 to Physical Security & Contingency Plan. Amend Withheld (Ref 10CFR73.21) ML20043G1021990-06-0606 June 1990 Requests Temporary Waiver of Compliance from Requirements of Action Statement 27 of Tech Spec 3.3.2 for Period of 6 H When Two Operating Control Room Emergency Filtration Sys Trains Shut Down for Required Testing ML20043E6901990-06-0505 June 1990 Forwards Rev 12 to Emergency Plan & Detailed Description & Justification of Changes.W/O Rev ML20043G7651990-06-0505 June 1990 Forwards Rev 13 to Emergency Plan & Description & Justification of Changes ML20043B5991990-05-25025 May 1990 Forwards Scope & Objectives Re 1990 Annual Emergency Preparedness Exercise to Be Conducted on 900801 ML20043B5981990-05-24024 May 1990 Responds to Violations Noted in Insp Rept 50-424/90-05 on 900217-0330.Corrective Actions:Locked Valve Procedure Revised to Eliminate Utilization of Hold Tag on Valves Required by Tech Specs to Be Secured in Position ML20043B6291990-05-22022 May 1990 Forwards Rev 5 to ISI-P-008, Inservice Testing Program, Per Tech Specs 4.0.5 Re Surveillance Requirements & Generic Ltr 89-04 ML20043B6351990-05-22022 May 1990 Forwards Rev 2 to ISI-P-016, Inservice Testing Program, Per Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. ML20042H0601990-05-14014 May 1990 Forwards Summary of Corrective Actions for 900320 Site Area Emergency Due to Loss of Offsite Power Concurrent W/Loss of Onsite Emergency Diesel Generator Capability.Truck Driver Disciplined for Lack of Attention ML20042G7301990-05-11011 May 1990 Forwards Revised Pages for May 1989,Jan & Mar 1990 Monthly Operating Repts for Vogtle Electric Generating Plant,Units 1 & 2.Revs Necessary Due to Errors Discovered in Ref Repts ML20042E2911990-04-18018 April 1990 Forwards Amend 17 to Security Plan.Amend Withheld (Ref 10CFR2.790) ML20042E7481990-04-0909 April 1990 Requests Approval to Return Facility to Mode 2 & Subsequent Power Operation,Per 900320 Event Re Loss of Offsite Power Concurrent W/Loss of Onsite Emergency Diesel Generator Capability ML20012E9001990-03-28028 March 1990 Provides Supplemental Response to Station Blackout Rule,Per NUMARC 900104 Request.Mods & Associated Procedure Changes Identified in Sections B & C W/Exception of Mods to Seals Will Be Completed 1 Yr from Acceptance of Analysis ML20012E8581990-03-28028 March 1990 Suppls Response to NRC Bulletin 88-010,Suppl 1 Re Traceability Reviews on Molded Case Circuit Breakers Installed in safety-related Applications.All Breakers Procured & Installed in Class 1E Equipment Reviewed ML20012E9761990-03-27027 March 1990 Requests Withdrawal of Inservice Insp Relief Requests RR-45, RR-47,RR-48 & Conditional Withdrawal of RR-54 Based on Reasons Discussed in Encl,Per 900206 Conference Call ML20012D8561990-03-22022 March 1990 Submits Special Rept 1-90-02 Re Number of Steam Generator Tubes Plugged During 1R2.One of Four Tubes Exceeded Plugging Limit & Required Plugging.Remaining Three Tubes Plugged as Precautionary Measure.No Defective Tubes Detected ML20012D6641990-03-22022 March 1990 Provides Followup Written Request for Waiver of Compliance to Make Tech Spec 3.04 Inapplicable to Tech Spec 3.8.1.2 to Permit Entry Into Mode 5 W/Operability of Diesel Generator a & Associated Load Sequencer Unverified ML20012D3681990-03-19019 March 1990 Forwards Proprietary & Nonproprietary Suppl 2 to WCAP-12218 & WCAP-12219, Supplementary Assessment of Leak-Before-Break for Pressurizer Surge Lines of Vogtle Units 1 & 2, Per 900226 Request.Proprietary Rept Withheld (Ref 10CFR2.790) ML20012D3401990-03-19019 March 1990 Submits Response to 891121 Request for Addl Info Re Settlement Monitoring Program.Current Surveying Procedures Used by Plant to Monitor Settlement of Major Structures Outlined in Procedure 84301-C.W/41 Oversize Drawings ML20012D6631990-03-15015 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Safety Implications of Control Sys in Lwrs.Overfill Protection Sys Sufficiently Separate from Control Portion of Main Feedwater Control Sys & Not Powered from Same Source ML20012C4681990-03-0606 March 1990 Provides Summary Rept of Property Damage Insurance Levels, Per 10CFR50.54(w)(1) ML20012B2891990-03-0606 March 1990 Forwards Plant Pipe Break Isometrics,Vols 1 & 2 & Advises That Encl Figures Have Been Revised to Be Consistent W/Pipe Analysis in Effect at Time That Unit 2 Received Ol,Including Revs Through 890930.W/309 Oversize Figures ML20012B2421990-03-0606 March 1990 Forwards Cycle 3 Radial Peaking Factor Limit Rept & Elevation Dependent Peaking Factor Vs Core Height Graph ML20011F5291990-02-26026 February 1990 Withdraws 881107 Proposed Amend to Tech Spec 3.8.1.1, Revising Action Requirements for Inoperable Diesel Generator to Clarify Acceptability of Air Roll Tests on Remaining Operable Diesel Generator ML20011F5261990-02-26026 February 1990 Forwards 1989 Annual Rept - Part 1. Part 2 Will Be Submitted by 900501 ML20011E8911990-02-12012 February 1990 Advises That Hh Butterworth No Longer Employed by Util 1990-09-06
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.- '* Georgis Power Company Post Office Box 282 Waynssboro, Georgia 30830 Telephone 404 554-99S1 404 724-8114 Southern Company Services, Inc.
Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 870-6011 Vogtie Project October 31, 1986 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Mr. B. J. Youngblood Log: GN-ll53 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 SER OPEN ITEM 14a: ' CONTROL ROOM DESIGN REVIEW (CRDR)
Dear Mr. Denton:
During the exit meeting, alminating your staff's CRDR preimplementation audit of September 18-19, 1986, your staff requested additional information.
Attached are responses to the items identified by your staff during the exit '
meeting.
If your staff requires any additional information, please do not hesitate to contact me.
n:e rely, J. A. Bailey Project Licensing Manager JAB /sm i Attachment xc: R. E. Conway NRC Regional Administrator )
j R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. Feig l B. W. Churchill, Esquire R. W. McManus '
M. A. Miller (2) L. T. Gucwa B. Jones, Esquire Vogtle Project File G. Bockhold, Jr.
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GEOR3IA POGER COMPANY VOGTLE wrRCTRIC GENERATING PLANT UNIT ONE NUCLEAR OPERATIONS CONTROL ROOM DESIGN REVIEW NRC PREIMPLEMENTATION AUDIT
RESPONSE
OCTOBER 24, 1986
TABLE OF CONTENTS
1.0 INTRODUCTION
........................................ 1 1.1 SYSTEMS FUNCTION AND TASK ANALYSIS.................. 1 1.1.1 System Operating Procedures invoked by EOPs.... 2 1.1.2 EOP Caution Statements......................... 2 1.1.3 Task Analysis of revisions to the EOPs......... 2 1.1.4 Control Panels referenced in the EOPs.......... 4 1.1.5 Instrument Response Time Capabilities.......... 4 1.1.6 Control And Display Type Comparison............ 6 l'. 2 CRDR TEAM DISCUSSIONS CONCERNING RESOLUTION OF HEDS. 6 1.3 COORDINATION OF CRDR WITH TRAINING.................. 8 1.4 HED CATEGORY ASSESSMENT PROCESS..................... 8 APPENDIX A Control Room Inventory...................... 12 APPENDIX B Mini Survey................................. 21 l
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. GEORGIA POWER COMPANY Page 1 VOGTLE ELECTRIC GENERATING PLANT UNIT ONE CONTROL ROOM DESIGN REVIEW NRC PREIMPLEMENTATION AUDIT RESPONSE
1.0 INTRODUCTION
On September 18 and 19, 1986 the Vogtle Unit One Control Room Design Review (CRDR) Preimplementation Audit and Mini Survey (Appendix B) was conducted by the Nuclear Regulatory Commission (NRC) and Lawrence Livermore National Laboratory (LLNL), acting as a consultant to the NRC. The audit was held at the Vogtle site to ' discuss and resolve questions resulting from the NRC/LLNL review of the Vogtle Unit One CRDR Summary Report. The audit discussed all aspects of the CRDR process. This report is submitted to the NRC as a preliminary response to some of the open iteus.
presented to Georgia Power Corporation (GPC) during the NRC exit meeting'on September 19, 1986. i 1.1 SYSTEMS FUNCTION AND TASK ANALYSIS The Vogtle Systems Function and Task Analysis process was reviewed by the NRC staff and LLNL. The NRC Audit Team stepped through the task analysis for a portion of the Steam Generator Tube Rupture procedure with the GPC CRDR Team. The NRC Audit Team identified several potential shortcomings in the Task Analysis process as a result of this review:
O System Operating Procedures (SOP) invoked by the Emergency Operating Procedures (EOP) were not Task Analyzed.
4 O EOP caution statements may not have been task analyzed.
O A formal mechanism for verifying Control Room displays and controls are suitable to support new or revised operator tasks resulting from EOP revisions does not exist.
O The EOPs may reference control panels in the control room outside the scope of the CRDR Program Plan.
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GEORGIA POWER COMPANY Page 2 O A comparison of needed instrument response time versus instrument response time capability was not performed. j O A comparison of the needed display and control types versus display and control types provided was not documented.
1.1.1 System Operating Procedures invoked by EOPs Each procedure in the EOP set was reviewed to identify the SOPS that are referenced. The review identified .
fifteen Unit One System Operating Procedures called for l in the EOP set. A Task Analysis was performed on control room equipment for each of the identified SOPS according to the process discussed in the VEGP CRDR-Summary Report. No additional Human Engineering Discrepancies (HED) were identified.
1.1.2 EOP Caution Statements l
All EOP caution statements were extracted from the EOP l set and duplicates were eliminated. The caution ~
statements were evaluated to identify the displays and controls needed to assess plant conditions. A computer search was conducted on the EOP Task Analysis data base for the identified displays and controls. The search l revealed that each EOP caution had been addressed in another procedure step during .the original Task Analysis. No additional HEDs were identified.
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1.1.3 Task Analysis of revisions to the EOPs The following elements of a task analysis are being added to the EOP revision process to provide some i
assurance that control room displays and controls are suitable to support new or revised operator tasks resulting from proposed EOP changes:
i INFORMATION CHARACTERISTICS UNITS: The parameter identified in the EOP step (s) agrees with the units on the specified control room instrument
, (examples: psig; %; gpm; etc.).
s.
, GEORGIA POWER COMPANY Page 3 RANGE: The interval over which the parameter !
(EOP step) may vary does not exceed the !
range of the installed instrument (examples: 0 to 3000 psig; 250 to 500 deg. F; O to 100%; etc.).
RESOLUTION: The EOP step (s) does not require the l determination of a parameter's value in l excess of the installed instrument resolution (example: greater than 1837
. psig on an instrument with a resolution of 50 psig).
TYPE: The EOP step (s) does not require visual information that the installed instrumentation cannot support, and classified as one of the following:
a) discrete or instantaneous (single value or alarm setpoint) b) continuous (multiple values within a ,
range) I c) trending (changing values within a range over a time period)
CONTROL CAPABILITY CHARACTERISTICS POSITIONS: The EOP step (s) does not require identification of control status unavailable in the control room (example: open; closed; throttled; on; off; etc.).
TYPE: The EOP step (s) does not require control actions that the installed controls can not support, classified as one of the following:
a) continuous (variable control; b) discrete (individual position (s) control) l l
GEORGIA POWER COMPANY Page 4 1.1.4 Control Panels referenced in the EOPs The NRC Audit Team requested that GPC conduct a review of the EOPs to ensure any referenced Control Room.back panels are included in the Unit One CRDR effort.
The review was conducted by the EOP procedure group.
This review confirmed that panels outside the scope of the Unit One CRDR Program Plan were not referenced.
1.1.5 Instrument Response Time Capabilities The comparison of needed instrument response times versus instrument response time capabilities was evaluated. In evaluating the response times for VEGP installed instrument loops, three factors were considered:
0 Response time of the transmitter O Response time of the process racks O Response time of the indicators l
Industry experience dictates that transmitter response <
times are in the range of a couple of seconds, process )
racks response times are in the range of milliseconds and indicator response times are insignificant compared 1 to the other two. This provides a typical response time l of less than 5 seconds. The exceptions to this !
statement are temperature elements (RTD's) where the
, heat transfer characteristics of the thermowell may result in response times longer than direct immersion detectors.
Due to the present state of plant construction and testing, it is impractical to verify all actual instrument loop response times. The response times provided in the Control Room Inventory data base (Appendix A) were derived from the following sources:
a) Actual instrument rack response time measurements (35 to 60 milliseconds) for some but not all primary process rack inputs, b) Quality Assurance and Design Specification documents for Differential Pressure and Pressure transmitters used in Westinghouse Nuclear Steam Supply System.
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, GEORGIA POWER COMPANY Page 5 Step response times were required to be demonstrated as part of the supplier's type testing program. Each of the following was demonstrated:
- 1) Time to reach 50% output from an input step from 45% to 55%
- 2) Time to reach 50% output from i an input step from 5% to 95%
Neither value to exceed .4 seconds and for filled systems neither value to exceed I second independent of capillary length, size or fill fluid.
c) Quality Assurance and Design Specification documents for Resistance Temperature Detectors (RTD's) used in Westinghouse Nuclear Steam Supply System.
Step response times were required to be demonstrated as part of the supplier's type testing program. Each of the following was demonstrated:
- 1) The direct immersion RTD time response shall be 2.5 seconds for a 63.2% response to a step change in the media.
- 2) Well mounted RTD's shall have a time response of 4 seconds for a 63.2% response to a step change in the media.
In lieu of actual instrument loop time measurements the specification times were at least doubled to provide l some conservatism in determining the response time capabilities used in the comparison to the Westinghouse Instrument and Control Characteristics Review (ICCR) requirements'.
The Control Room Inventory of Instruments Identified in the ICCR was updated and compared to the requirements.
No HEDs were identified during this evaluation.
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, GEORGIA POWER COMPANY Page 6 1.1.6 Control And Display Type Comparison The comparison of the needed display and control types versus the actual installed display and control types was performed. The . Control Room Inventory of Instruments Identified in the ICCR (Appendix A) was updated and compared to the requirements. No HEDs were identified during this evaluation.
1.2 CRDR TEAM DISCUSSIONS CONCERNING RESOLUTION OF HEDS The NRC Audit Team had a concern that important Team discussions relevant to the resolution of HEDs will not i be preserved for future reference (ie. Unit Two CRDR).
4 To aid in the preservation of relevant comments, the !
HED Form has been modified to include Team Member i discussions (Figure 1). l l
1 i
1
, - . - - - . . _ . . ,-, - ,..... . - , - .,n_n-.. . - - , ,
GEORGIA POWER COMPANY Page 7 REV: 1 DATE: 10/17/86 VOGTLE ELECTRIC GENERATING PLANT HUMAN ENGINEERING DISCREPANCY (HED)
HED Number:
Item (s) involved:
Origin:
HED
Description:
Originator: /
Signature Date Team Menber Discussions:
T/M 1 T/M 2 T/M 3 T/M 4 FR--:*3 Resolution: Category:
CRIR Team Approval /
(Team Imader Signature) Date Pages Attached (Figure 1)
GEORGIA POWER COMPANY Page 8 1.3 COORDINATION OF CRDR WITH TRAINING The CRDR process described in VEGP CRDR Summary Report
! was coordinated with other post-TMI activities. The CRDR Summary Report details the mechanisms for coordination of control room improvements with other programs. In addition, the CRDR was coordinated with the Training Program as follows:
- 1) The Team Captain and one other team member attended a Senior Reactor Operator License Training Program during the Unit One CRDR effort. This improved the CRDR Team Members knowledge of operations and plant design, allowing them to more effectively identify design problems later in the CRDR process.
- 2) Where appropriate, HED resolutions identified training needs which were incorporated in formal lesson plans by the Training Department.
- 3) Both students and instructors in the Simulator Training Program were surveyed to=
identify Human Engineering Discrepancies which were noted during simulator exercises.
This was an especially valuable technique since new operators problems with the controls reveal design problems that more experienced operators have learned to compensate for.
j 4) Control room modifications that resulted from the Emergency Operating Procedures Validation Program and/or CRDR Survey Instruments were first installed in the Training simulator (when practicable) in order to gain operator feedback regarding the suitability of the improvement. The formal feedback mechanisms were the Operator Questionnaires and Problem Reports as presented in the CRDR Summary Report.
1.4 HED CATEGORY ASSESSMENT PROCESS
, As discussed in the VEGP CRDR Summary Report, the last aspect of the Assessment Phase was an independent HED category review. This HED category review was conducted to provide assurance that each HED identified during the Execution Phase of the CRDR wcs in fact properly categorized.
. GEORGIA POWER COMPANY Page 9 During the NRC Preimplementation Audit, the Audit Team noted that a potential existed for HEDs with safety significance and high error probability to be assigned a category that would not require correction if they were not identified during the EOP Validation Exercise.
The review of the HED data base conducted by the CRDR Team during the Audit determined that no HEDs of safety significance and high error probability would be left uncorrected. However, to provide assurance that HEDs of safety significance and high error probability would be properly categorized, the algorithm was modified to permit HEDs to be categorized as Category 1 without reference to the EOP Validation Exercise and before the Category 2 decision point.
All HEDs identified in the future will be subjected to the following modified algorithm (Figures 2 and 3) to determine their significance and effects on plant safety.
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-n.- , - ,-- , . - , -- - , ,..--,..-,---r , - - . - - - - , - , . , e - - - - , , , - - - - - , - . , - - - , , - - ,---- ~.-- - . , - - , ,- a.n --
i CRDR DISCREPANCIES IDENTIFIED SURVEYS CHECKLISTS Fig u re 2 TASK ANALYSIS hff g E EE
! IDENTIFIED HED'sk o
YES E
- HED CATEGORIZED ITEM >
7 NO l
1 2 3 >l CATEGORY 1 l V 8
4 4 >l CATEGORY 2 l
! 3 CATEGORY 3 l l n 9 CATEGORY 4 l D suu 6 5
ALGORITHM ATTRIBUTES ITEM 1 ITEM 2 HED's experienced or assessed as having a hig h probability of HED's associated with ESF contributing to operator e rro r. System s.
e e
S ITEM 3 ITEM 4
- HED's that could result in HED's idenlified through the unsafe operation or violation Operat,ing Experience Review of a Techn.ical Specif.icat. ion. or actual problems identified o in the Operator Questionnaire. %
ITEM 5 ITEM 6 HED's determined to be easily HED's determined to contribute correctable with point, tape, labels, to Operator mental work load engraving changes or work space (cumulative effects) resulting in environment improvements. fatigue, confusion or discomfort.
Fig u re 3 g 11
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., GEORGIA POWER COMPANY Page 12 1
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l APPENDIX A i 1
CONTROL ROOM INVENTORY OF INSTRUMENTATION IDENTIFIED IN THE VEGP ICCR l i
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CEOR2IA POWER COMPANY Paga 13 CONIROL ROCH INVENIORY OF INSTHJMENTATION IDENTIFIED IN THE VEGP ICCR MST INSTRUMNIATION INSTRUM!NTATION (MITS MIN MAX RESOLUTION ACCtRACY RESPONSE TYPE NO. NUM ER NAME TIME 001 TSIE-3 SI ACIUATED N/A N/A N/A N/A N/A N/A D !
BPIB WDOCH l l
002 ALBO9-A4 SI ANNUNCIATORS N/A N/A N/A N/A N/A N/A D 003 AIB GROUP 1 & 4 CMT ISO PHASE N/A N/A N/A N/A N/A N/A D A PONITOR LIGifrS 004 Car ISO PH B NO ISO OCCURS N/A N/A N/A N/A N/A N/A ON PHASE B 005 TSIB-4 CONTAIMENT N/A N/A N/A N/A N/A N/A D SPRAY STATUS 006 TSLB-1 IDW STMLINE N/A N/A N/A N/A N/A N/A. D PRESS SI SIGNAL STATUS 007 TSIB-3 LOW PRZR PRESS N/A N/A N/A N/A N/A N/A D SI SIGNAL STATUS 008 1-LI-0990A REFUELING WATER % 0 100 2 3.7 3 SEC. D,C STORAGE TANK 009 ALB06-E5 RHST I!MPTY N/A N/A N/A N/A N/A N/A D AIARM 010 1-FI-0918 SAFE INJ PU W GPM O 800 20 3.6 3 SEC. D,C P6003 DISCH 011 1-FI-0917A CVCS CIE319F TO GPM O 1000 20 3.7 3 SEC. D,C BGt INJ TK V6 012 1-PI-0947 BOR N INJECT PSIG 0 2800 50 3.0 3 SEC. D,C TANK 013 1-PI-0919 sAPE INJ PUDP PSIG 0 2000 50 3.0 3 SEC. D,C P6003 DISCH 014 1-NI-OO41B POMR RAN3E- 1 % FULL 0- 120 2 5.2 1 SEC. D,C,T 1-NR-0045 % PULL POMR POMR 015 1-NI-0036B INTEREDIATE AMPS 10E-11 10E-3' 1 10.2 1 SEC. D,C,T 1-NR-0045 RANGE-2
1 GEOR3IA POWER COMPANY Pcga 14 CONTROL ROCN INVENTORY OF INSTRUMENTATION IDENTIFIED IN THE VEGP ICCR E ST INSTRUMENTATION INSTRUMENTATION IMITS MIN MAX RESOLITIION ACCtRACY RESPONSE TYPE NO. NUPEER NAME TIME 016 1-NI-0035D INTERMEDIATE DPM .-5 5 .1 N AVAIL N/A D,C RANGE-1 STRT UP 016 1-NI-0036D INIEREDIATE DPM .-5 5 .1 N AVAIL N/A D,C RANGE-2 STRT UP 017 1-NI-0032B SOURCE RANGE-2 CPS 10E0 10E6 1 11.0 1 SEC. D,C,T 1-NR-0045 CCUNE RATE 018 1-NI-0032D SOUICE RANGE-2 DPM .5 5 .1 N AVAIL N/A D,C STRr UP RATE 019 N/A RCD BOT 1tN N/A N/A N/A N/A N/A N/A D LIGRTS 020 1-RE-0002 AREA 60N M/h 10E-1 10E4 DIGITAL >20.0 N AVAIL D,C CONTAIN OP LEVEL 020 1-RE-0005 AREA M]N M/h 10E-3 10E11 DIGITAL >20.0 N AVAIL D,C CONTAIN OP LEVEL 021 1-RE-OO19 STEAM GENERATOR UCI/cm3 4E-7 4E-2 DIGITAL >20.0 N AVAIL D,C LIQUID 022 1-RE-0021 STM GEN BIh0N UCI/cm3 4E-7 4E-2 DIGITAL >20.0 N AVAIL D,C TO CONIENSER 023 1-RE-12839A SJAE & STM PEG N/A N N AVAIL DIGITAL >20.0 N AVAIL D,C EXH RAD MRI*1TR AV.~ . L 023 1-RE-12839B SJAE & SIM PNG N/A N N AVAIL DIGITAL >20.0 N AVAIL D,C EXH RAD M3fITTR AVAIL 023 1-RE-12839C SL7AE & SIM PNG N/A N N AVAIL DIGITAL >20.0 N AVAIL D,C EXH RAD 60NITOR AVAIL 024 1-RE-0024A SEtaCT CCMP UCI/an3 1E-10 1E-5 DIGITAL >20.0 N AVAIL D,C CUBICIE 024 1-RE-0024B SELECT CCMP UCI/an3 5E-7 5E-2 DIGITAL >20.0 N AVAIL D,C CUBICLE O25 1-RE-13119 MAIN STEAM LINE N/A N N AVAIL DIGITAL >20.0 N AVAIL D,C MON AVAIL
, GEOR2IA POWER COMPANY Paga 15 CONIROL ROCN INVENIORY OF INSTRUMENTATION IDENTIFIED IN THE VEGP ICCR E ST INSTRUMENTATION INSTRUMENTATION INITS MIN MAX RESOLUTION ACCGtACY RESPONSE TWZ NO. NUBBER NAME TIME 026 1-RE-12442A PIANI VENT UCI/cm3 1E-11 1E-6 DIGITAL >20.0 N AVAIL D,C 026 1-RE-12442B PLANT VENT UCI/cm3 1E-11 1E-6 DIGITAL >20.0 N AVAIL D,C 026 1-RE-12442C PLANT VENT UCI/cm3 5E-7 SE-2 DIGITAL >20.0 N AVAIL D,C 027 1-AI-12979 CONTAIN H2 % 0 10 .1 N AVAIL N AVAIL D,C MONITUR TRN A 027 1-AR-12979 CONTAIN H2 % 0 10 .1 N AVAIL N AVAIL D,C PONITOR TRN A 028 1-PI-0934 CONTAIPM!NT PSIG 0 75 1 3.0 3 SEC. D,C,T 1-PR-0934 029 1-LI-0764 CONIAIN !!MERG % 0 100 2 3.7 3 SEC. D,C FLOOR DRNS LEVEL 030 1-FI-0930 SPRAY AIDITIVE GEN O 300 5 3.2 3 SEC. D,C TANK IN 031 1-LI-0931A SPRAY AIDIT TK % 0 100 2 3.7 3 SEC. D,C T6001 LEVEL 032 1-PI-0408 REAC COOLANT PSIG 0 3000 50 3.0 3 SEC. D,C,T 1-PR-0428 LOCP 1 }OT LEG 033 1-TI-0412 REAC 000 IDCP 1 DEGREE F 530 630 2 3.6 8 SEC. D,C.T 1-TR-0412 TilDF AVERAGE 034 CORE EXIT T/C T/C's DEGREE F 0 2400 .1 N AVAIL 5 SEC. D,C,T l 1-XR-400053 !
l 035 1-UI-13134A RCS SUBCOOLING DEGREE F N N AVAIL N AVAIL N AVAIL N AVAIL D,C i BONITOR AVAIL l 036 1-TI-0413A REAC IOOP 1 DEGREE F 0 700 10 3.7 8 SEC. D,C,T 1-TR-0433A WIDE RANGE HCfr 037 1-TI-0413B REAC IDOP 1 DEGREE F 0 700 10 3.7 8 SEC. D,C,T 1-TR-0433B WIDE FANGE COID i
038, 1-LR-1310 REACTOR VPmvr. % 60/0 120 1/2 3.3 3 SEC. D,C,T 39, WATER LEVELS 40 1
GEORGIA POWER COMPANY Paga 16 4
CONIROL ROOM INVENIORY OF INSTRUMENTATION IDENTIFIED IN THE VEGP ICCR 1
l MST INSIMM!NTATION INSTRUMNTATION (NITS MIN MAX RESOLUTION ACCCRACY RESPONSE TYPE NO. !GSER NAM TIM 1
J l
- 041 1-TE-173 RCP #1 SEAL DEGREE F N N AVAIL N/A N AVAIL N AVAIL l T!!MP AVAIL l 042 1-FI-0414 REAC COOLANT % 0 120 2 3.0 3 SEC. D,C LOOP 1
! 042 1-FI-0444 REAC COOLANT % 0 120 2 3.0 3 SEC. D,C j
043 1-PI-0455A PRESSURIZER PSIG 1700 2500 10 2.5 3 SEC. D,C,T 1-PR-0455A VAPOR l 044 1-TI-0453 PRESSURIZER DEGREE F 100 700 10 3.7 8 SEC. D,C i LIQUID l
045 1-LI-0459A PRESSURIZER % 0 100 2 3.6 3 SEC- D,C,T 1-IR-0459 1
046 1-TI-0468 PRESSURIZER DEGREE F 50 350 5 3.7 8 SEC. D,C RELIEF TANK
- 047 1-LI-0470 PRESSURIZER % 0 100 2 3.7 3 SEC. D,C RELIEF TANK 048 1-PI-0469 PRESSURIZER PSIG 0 100 2 3.0 3 SEC. D,C RELIEF TA M l 049 1-TI-0449 PRESSURIZER oe n F 50 400 10 3.7 8 SEC. D,C poler RELIEF 4 050 1-TI-0464 PRESSURIZER DEM EE F 50 400 10 3.7 8 SEC. D,C SAFETY VALVE j DISCH 051 1-FI-0618A RESID NT RBOV @M 0 5000 100 3.6 3 SEC. D,C IP RET BYPASS A t
052 1-PI-0614 RESID HT RB OV PSIG 0 800 20 3.0 3 SEC. D,C l PLMP 1 DISCH 053 ALB06-Al & B1 RIE PUW DISCH N/A N/A N/A N/A N/A N/A D l HIGH PRESS ALAM
- i 054 1-FI-0183A EMRG B0 RATION @M O 150 2 3.2 3 SEC. D,C 055, 1-FR-0110 BCRIC ACID 0 160/40 2/1 4 % 2.8/3.4 3 SEC. D,C,T 67 BLEND 00N m0L l
t GEORGIA POWER COMPANY Paga 17 l
00NTROL ROCH INVENIORY OF INSTRUMDrIATION IDENTIFIED IN THE VEGP ICCR Mt31' INSTRUMENTATION INSTRUMENTATION LMITS MIN MAX RESOLUTION ACCLRACY RESPONSE TYPE NO. IG BER NADE TDE 056 1-TI-0103 BORIC ACID TANK DEGREE F 50 150 2 3.7 8 SEC. D,C T4003 057 1-FI-0121C CHARGING LINE GPM O 200 10 3.7 3 SEC. D,C j 058 1-FI-0142A REAC COOLANT GPM 0 20 0.5 3.7 3 SEC. D,C PLMP 4 SEAL WATER 059 1-FI-0132C IRID 06N FLOW GPM O 200 5 3.7 3 SEC. D,C 060 1-FI-0406A REACIOR HEAD GPM O 80 1 3.7 3 SEC. D,C LETD9M LINE 061 1-ER-0156 REAC COOL ENP gal 0 1.0 .02 3.4 3 SEC. D,C,T 1AND2 L RANGE IJC 062 1-FR-0158 REAC COOL PMP GPM O 6.0 .2 3.4 3 SEC. D,C,T 3AND4 H RANGE IJC 063 1-PDI-0150 REAC COOLANT PSID 0 400 10 3.0 3 SEC. D,C PlNP 4 NO 1 SEAL 064 N AVAIL RCP SEAL N/A N/A N/A N/A N/A N/A INJECTION SUPPLY TBF 065 1-PI-0120A CHARGING HEAIER PSIG O 3500 50 3.0 3 SEC. D,C 066 1-LI-0185 VOL CGfTROL % 0 100 2 3.7 3 SEC. D,C TANK 068 1-PI-0131A ID PRES LETDPH PSIG 0 600 10 3.0 3 SEC. D,C 069 1-PI-0124 EXCES LEID6M PSIG 0 250 5 3.0 3 SEC. D,C HEATEXCH DISCH 070 ZIB-12,13,614 AB BREAK DETECT N/A N/A N/A N/A N/A N/A D SYS STATUS LIGfr I
071 1-FT-19052 RCP CCW THERMAL N/A N/A N/A N/A N/A N/A D l BARRIER FIDW
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, GEERGIA POWER COMPANY PXgia 18 CONIROL ROOM INVENIORY OF INS'IBUMENTATION IDENTIFIED IN THE l VEGP ICCR MST INS"1PUM!lNTATION INSTRUMENTATION . IMITS MIN MAX RESOLUTION ACCtRACY RESPONSE TYPE NO. NUM ER NAME TIME i
072 1-FE-1929 CCW FIIN 'IO RHR N/A N/A N/A N/A N/A N/A D HK's j 073 1-PI-1874 COMPO CW PUW PSIG O 200 5 3.0 3 SEC. D,C TRAIN A DISCH 074 1-PI-1977 AIR C(NPO CW PSIG O 200 5 3.0 3 SEC. D,C PMPS DISCH 075 1-FI-1876 CCEPO CW PUW GPM x 10E2 0 150 2 3.6 3 SEC. D,C TRAIN A DISCH 076 1-TE-1967 AOCW SUPPLY DEGREE F N N AVAIL N/A N AVAIL N AVAIL D T!!MP AVAIL 077 AIBO4-B3,4,5,&6 ACCW RCP COOLER N/A N/A N/A N/A N/A N/A D FIDW ANNINCIA'ICR 078 1-PI-9361 INSIR AIR DRYER PSIG O 150 2 3.0 3 SEC. D,C
'ID SCS EQUIP 079 1-PI-1636 NUC SERV CW PMP PSIG O 200 5 3.0 3 SEC. D,C 7 RAIN A DISCH 080 1-FI-1640A NUC SERV TRAIN GEN X10E3 0 25 .5 3.6 3 SEC. D,C 1 A RETURN FIDW 081 1-PI-0514A STM GEN LOOP 1 PSIG O 1300 20 3.0 3 SEC. D,C,T l 1-PR-0514 STM 082 AIa13-F1 STEAM PRESSURE N/A N/A N/A N/A N/A N/A D l RATE AIARM
)
083 1-LI-0517 SIM GEN LOCP 1 % 0 100 2 3.6 3 SEC. D,C,T 1-FR-0510 084 1-LI-0501 STM GEN IDOP 1 % 0 100 2 3.6 3 SEC. D WIDE RANGE 085 1-SI-5316 SGFPI A SPEED R1H X10E3 0 8 .2 N AVAIL N AVAIL D,C TACH DO RMr N
086 1-PI-0508 FEEDWIR PUW PSIG 200 1500 20 3.0 3 SEC. D,C l DISCE
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, GE3R3IA POWER COMPANY Pcga 10 COMm0L ROCN INVENIORY OF INSTRUMENTATION IDENTIFIED IN THE VEGP ICCR MST INSTRUMENTATION INSTRUMENTATION (MITS MIN MAX RESOLUTION ACCCRACY RESPONSE TYPE NO. NUMER NAME TIME
\
087 1-FI-0510A SIM GEN IDOP 1 WPH 0 5 .1 4.0 3 SEC. D,C FEEDfrR 088 1-PR-6292 LPI A & B PSIG 0 30 0.5 2.6 3 SEC. D,C,T ExxAuST N0ao PRESS N 089 1-FI-5150A AIN FEEDWrR GPM 0 600 10 3.6 3 SEC. D,C SUPP TO SIM GEN 4
090 1-SI-15109A ALE FW TURB RPM x10E3 0 6 .1 N AVAIL N AVAIL D,C SPEED 091 1-PI-5107A AIN FEED PMP TD PSIG X10 0 200 5 3.0 3 SEC. D,C P4001 IM DISCH 092 1-LI-5101 CONDENSATE % 0 100 2 3.7 3 SEC. D,C SICRAGE TANK 1 i 093 1-JI-40132 GENERATOR A-C MGA 0 1500 20 1.0 INST D,C JI-Gl>N 094 1-PI-6338 HYDRAULIC FLUID PSIG x10E3 0 2 .5 N AVAIL N AVAIL D,C PRESSURE 095 1-JI-40113 DG1A WAIT KIIDDETTS O 10E4 200 1.0 INST D,C OUIPUT 095 1-JI-40114 DG1B WATT KIIO9ATTS O 10E4 200 1.0 INST D,C OUTPUT 096 1-EI-40137B DG1A 001PUT AC VOLTS 0 5000 100 1.0 INST D,C VOLTAGE 096 1-EI-40138B DG1B OUIPUT AC VOLTS 0 5000 100 1.0 INST D,C VOLTAGE
, 097 N/A 13.8KV BUS VOLTS O 18000 200 1 INST D,C 1 VOLTAGE 098 N/A 13.8KV BUS HZ 57 61 .5 1 INST D,C FREQUENCY 099 N/A 4.16KV BUS VOLTS O 5000 10 1 INST D,C VOLTAGE i
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CEORGIA POWER COMPANY Pcga 20 CON 1 POL ROOM INVENIDRY OF INSTRUMENTATION IDENTIFIED IN 'INE VEGP ICCR M ST INSTRUMENTATION INSTRUMENTATION UNITS MIN MAX RESOLITTION ACCT. RACY RESPONSE TYPE NO. NUMER NAME TIME 100 N/A 480 VOLT BUS N/A N/A N/A N/A N/A INST D POTENTIAL LIGHTS 101 N/A AC EM!RGENCY VOLTS O 5000 10 1 INST D BUS VOLTAGE 102 1-LSHL-0625 SPENT FUEL N/A N/A N/A N/A N/A N/A D LEVEL 103 1-FI-0631 SFPCPS FLOW N/A N/A N/A N/A N/A N/A D 104 N/A CONTROL ROCN MIN /HR 00:01 24:00 00:01 N AVAIL INST D,C CLOCK l
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GEORGIA POWER COMPANY Page 21 l
APPENDIE B l
! VOGTLE PREIMPLEMENTATION AUDIT l CONTROL ROOM MINI SURVEY RESULTS SEPTEMBER 18, 1986 NRC MINI AUDIT HEDS Plant VOGTLE position j
)
- 1) The meter face non-glare VEGP HEDS 1288 I coating or other damage impairs the readability of the meter !
scales.
- 2) No reflash capability for VEGP BED # 1211 & 1281 multiple input annunciators, l
- 3) Annunciator group labels The current label referring to are misleading or incomplete MFW and steam generators is (e.g. AFW annunciators located inclusive of the AFW systema. i in a group of Main Feedwater) This level of labeling meets the guidelines of NUREG 0700.
Revisions to these labels were-already planned to standmedize nomenclature and has been installed, it now reads 'MFW, AFW and STEAM GENERATORS'.
- 4) Inconsistent channel VEGP HEDS 1012, 1013 & 1139 terminology used on the AFW pumps and controls (e.g. A,B,C versus 1,2,3).
1
- 5) Vibration monitor controls VEGP EED# 1068, 1251 & 1253, appear to be out of reach for
, the 5th percentile female.
- 6) Steam / Feed Flow / Level blue Refer to RED # 1149 & 1285 and and green recorder pointers are their resolution, but no obscured by the recorder scale. problems have been identified in the Simulator or the Operator Experience Reports. The operatore do not normally stand at attention, pressed to the rail to read this instrument.
Normal flexure to operate the l controls makes the pens visible.
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- . GEORGIA POWER COMPANY Page 22
- 7) The normal range of the VEGP HEDS 1048 displayed parameters are not indicated
- 8) The meaning of the amber VEGP HED# 1099 lights associated with the hand switches are not clear
- 9) The labels for the steam HED resulted from a modification generator flow element inputs to correct a previous HED. This are obscured from tall operators item has not been subjected to by the recorder covers. the Verification Program at this time.
- 10) TDI-15215 (Delta "T" The parameter is also identified indicators) parameter indication in the Hierarchical label above located on meter scales instead the indicator (1TI for temp.
of device labels. indicator and 1DTI for Delta temp. indicator).
- 11) Parameter units are not This panel was not subject to provided on the digital Rad the Unit One CRDR, but it was Monitor displays. our intention to add the units to the Rad Monitor displays on this panel and the local read outs via the Supplemental Label Program.
- 12) Annunciators are located VEGP HED# 1067 & 1070 too high for continued viewing, especially by shorter operators.
- 13) Labeling on many "J" handle VEGP HEDS 1295 switches is obscured by the "J" handle itself.
- 14) One set of labels (Hotwell This control room item was level control) is placed midway previously identified by the between two sets of functionally CRDR Team and is now corrected.
distinct displays. Operator misreads will result.
- 15) The Load Limit Set Dial This specific problem was not readings are not readable, need addressed in 0700,.but the dials l contrast from background, need cleaning, and will be j addressed under our house cleaning procedure.
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- 16) The height of lower "J" and We plan to perform a second "T" handles and associated Anthropometric Survey of the controls on panel PSDA are too Shutdown Panels to ensure no low. other errors exist.
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