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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
[Table view] |
Text
I Georg.a Power Comp;my ,
Nuclear Operations I y
I
- Posr Ofhce pox jerg Wayne 2oro, Georgia 30830 Teephone 404 7pa 3j 9a 404 554 9961 Vogtle Project m.
Georgia Power 87 AUG l2 All: 23 "" + n. c , ,s ,
August 8, 1987 I
1 United States Nuclear Regulatory Commission Region II 101 Marietta Street, NW Atlanta, Georgia 30323 Attention: Mr J. Arildsen
Dear Mr. Arildsen:
j Enclosed in the five (5) boxes are the following: ,
BOX TITLE 1 System Operating Procedures Operations Administrative Procedures Unit Operating Procedures System Alignment Procedures Plant Administrative Procedures Alarm Response Procedures Vol. 1 2 Alarm Response Procedures (Vol. 2)
Abnormal Operating Procedures Emergency Operating Procedures Health Physics Procedures Emergency Response Proceduras Refueling Procedures Approved Plant Procedure Index Operations Standing Orders Precautions, Limitations & Setpoint Document Simulator Malfunction Book Plant Technical Data Book Technical Specifications i\
u.s e geTMBMjk U.S. NRCT REGION 2 F
OFFICIAL COPY
BOX TITLE 3 VEGP Training Text:
Volume 5 (la, Ib, Ic, 2, 3a, 3b, 3c, 4a, 4b)
Volume 6 (Sa, 6, 7, 9a, 9b, 10a, 10b, 10c, 10e, lla)
Volume 7 (12a, 12b, 13a, 13b, 13d, 14a, 14c, 14d)
Volume L (15a, 15b, 16a, 16b, 17b, 17c, 18b)
Volume 9 (20, 21, 23, 25) 4 Licensed Operator Lesson Pla.ts Vols. 1-8 5 Heat Transfer Thermodynamics and Fluid Flow Fundamentals Licensed Operator Lesson Plans Vols. 9-10 NRC Exam Bank Vols. 1-2 One-Line Diagrams- Electrical System P & ID 's Index and Diagrams The requirements for footwear have recent:y changed. Currently, shoes worn on the plant site must have a defined heel and have leather uppers. Please inform all the examiners concerning this requirement.
Please return this material upon completion of your examination preparation. If you need any assistance, please call me at (404) 724-8114 -
extension 3301.
Sinc ely.
Paul D. Rushton Plant Training & Emergency Preparedness Manager PDR:jmc
, A .
- 1. ,
p- ONE LINE DIAGRAMS - ELECTRICAL SYSTEMS j k_/
s I TYPE SUB-f' l IX3D CAT CAT DESCRIPTION AA A GEN NOTES, SYMBOLS, NUMBERING SYS.
ABBREVIATION, DRAWING INDEX AND MAIN ONE LINE
- j. AA B GENERATOR AA i MAIN AND UNIT AUXILIARY TRANSFORMERS AA B RESERVE TRANSFORMER AA C 13800V SWITCHGEAR AA D 4160V SWITCHGEAR (NON CLASS 1E)
AA D 4160V SWITCHGEAR (CLASS 1E) '
AA E 480V SWITCHGEAR (NON CLASS 1E)
AA E 480V SWITCHGEAR (CLASS 1E)
AA F 480V MOTOR CONTROL CENTERS (T30N CLASS 1E)
AA F 480V MOTOR CONTROL CENTERS (CLASS 1E)
AA G 120V AC POWER SYSTEM (CLASS 1E UNINTERRUPT1BLE) ,
AA G 120V AC INSTRUMENT POWER SYSTEM (NON CLASS 1E)
AA 11 125V DC (NON CLASS 1E)
AA H 125 DC (CLASS 1E)
AA K STANDBY POWER SYS (DIESEL GENERATOR)
AA L SWITCHYARD SYSTEM (230 KV) r~'N Q
U
.w .
4 i
LEGEND AND SYMBOLS FOR P&ID's-LRAWING NO- SYSTEM NO DESCRIPTION l i
IX4DB100- -
P&ID AND FLOW DIAGPaM LEGEND .q 1X4DB101 INSTRUMENTATION IDENTIFICATION & SYMBOLS. -
1X4DB102 .' INSTRUMENTATION' IDENTIFICATION & SYMBOLS ;
i 1
I O
t i
)
O
_m _ . . . - _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ 2__ ____m
P&ID'S - NSSS SYSTEMS
'v/
1X4DB110 2702 POST ACCIDENT SAMPLING SYSTEM 1X4DB111 1201 REACTOR COOLANT SYSTEM 1X4DB112 1201 REACTOR COOLANT SYSTEM 1X4DB113 1201 RTD BYPASS REACTOR COOLANT SYSTEM 1X4DB114 1208 CHEMICAL & VOLUME CONTROL SYSTEM IX4DB115 1208 CHEMICAL & VOLUME CONTROL SYSTEM 1X4DB116-1 1208 CHEMICAL & VOLUME CONTROL SYSTEM 1X4DB116-2 1208 CHEMICAL & VOLUME CONTROL SYSTEM IX4DB117 1208 CHEMICAL & VOLUME CONTROL SYSTEM 1X4DB118 1208 CHEMICAL & VOLUME CONTROL SYSTEM 1X4DB119 1204 SAFETY INJECTION SYSTEM 1X4DB120 1204 SAFETY INJECTION SYSTEM 1X4DB121 1204 SAFETY INJECTION SYSTEM 1X4DB122 1205 RESIDUAL HEAT REMOVAL SYSTEM !
AX4DB123-1 1210 BORON RECYCLE SYSTEM 1X4DB124 1901 WASTE PROCESSING SYSTEM-LIQUID 1X4DB125 1901 WASTE PROCESSING SYSTEM-LIQUID 1X4DB126 1901 WASTE PROCESSING SYSTEM-LIQUID 1X4DB127 1901 WASTE PROCESSING SYSTEM-LIQUID 1X4DB128 1902 WASTE PROCESSING SYSTEM-GAS 1X4DB129 1902 WASTE PROCESSING SYSTEM-GAS 1X4DB130 1213 SPENT FUEL COOLING & PURIFICATION SYSTEM 1X4DB131 1206 CONTAINMENT SPRAY SYSTEM
()
\,_ /
1X4DB133-1 1X4DB133-2 1202 1202 NUCLEAR SERVICE CLG WTR SYS NUCLEAR SERVICE CLG FTR SYS 1X4DB134 1202 NUCLEAR SERVICE CLG WTR SYS 1X4DB135-1 1202 NUCLEAR SERVICE CLG WTR SYS 1X4DB135-2 1202 NUCLEAR SERVICE CLG WTR SYS 1X4DB136 1203 COMPONENT COOLING WATER SYS 1X4DB137 1203 COMPONENT COOLING WATER SYS 1X4DB138-1 1217 AUX COMPONENT COOLING WATER SYS 1X4DB138-2 1217 AUX COMPONENT COOLING WATER SYS 1X4DB139 1217 AUX COMPONENT COOLING WATER SYS h
N
+ .
,q P&ID: - BALANCE OF PLANT SYSTEMS s >
DRAWING NO SYSTEM NO DESCRIPTION 1X4DB140 1212 NUCLEAR SAMPLING SYSTEM - LIQUID 1X4DB141 1211 NUCLEAR SAMPLING GAS-GASEOUS 1X4DB143 1214 CONTAINMENT & AUX BLDG DRNS-RADI0 ACTIVE 1X4DB144-1 1214 CONTAINMENT & AUX BLDG DRNS-RADIOACTIVE 1X4DB144-2 1214 CONTAINMENT & AUX BLDG DRNS-RADI0 ACTIVE 1X4DB150 1401 CIRCULATING WATER SYSTEM 1X4DB150-1 1401 CIRCULATING WATER SYSTEM AX4DB152-2 1420 WASTE WATER EFFLUENT SYSTEM 1X4DB159-1 1301 MAIN STEAM SYSTEM IX4DB159-2 1301 MAIN STEAM SYSTEM IX4DB159-3 1301 MAIN STEAM SYSTEM 1X4DB160-1 1301 MAIN STEAM SYSTEM 1X4DB160-2 1301 MAIN STEAM SYSTEM 1X4DB161-2 1302 AUXILIARY FEEDWATER SYSTEM 1X4DB161-3 1302 AUXILIARY FEEDWATER SYSTEM 1X4DB168-1 1305 CONDENSATE & FEEDWATER SYS 1X4DB168-2 1305 CONDENSATE & FEEDWATER SYS 1X4DB168-3 1305 CONDENSATE & FEEDWATER SYS 1X4D3170-1 2403 DIESEL GEN SYSTEM (TRAIN-A)
)- 1X4DB170-2 2403 DIESEL GEN SYSTEM (TRAIN-B)
CX4DB173-1 2301 FIRE P3OTECTION PUMP HOUSE 1 & 2 IX4DB175-1 2401,2420 INSTRUMENT & SERVICE AIR SYSTEM I'N 1X4DB175-2 2401,2420 INSTRUMENT & SERVICE AIR SYSTEM N.
l
[N N-] '
i i
- i. ..
m P&ID'S - HVAC SYSTEMS A
DRAWING NO SYSTEM NO DESCRIPTION-
~
1X4DB221 1592 SAFETY RELATED (ESF) CHILLERS UNIT 1 TRAINS A&B 1X4DB233 1592 ESF CHILLED WATER CLG COILS, UNIT 1 TRAIN A 1X4DB234 1592 ESF CHILLED WATER CLG COILS, UNIT 1, TRAIN B 4
0
7 a k
?.
S LO LESSON PLANS Listed by Current LESSON PLAN Number JULY 1987 Current No. Title LO-LP-01102-03-C A.C. ELECTR: CAL POW 2R DIST (480-13.8, 4.16)
LO-LP-01103-01-C 120 VAC ILICTRICAL SYSTZM LO-LP-01201-01-C D.C. ELECTRICAL POWER SYSTEMS LO-L?-0140 -01 SAFIGUARDS SZQUINCIR LO-LP-02101-00-C SIRVICE AND ~NSTRUMENT AIR SYSTEMS LC-L?-04101-01-C AUXILIARY COMPONENT COOLING WTR SYS LO-LP-06101-03-r NUCLEAR SIRVICE COOLING WATER SYSTEM LO-LP-07101-03-C CIRCULATING WATER SYSTEM LO-LP-09001-00 CVCS : INTRODUCTION LO-L?-09101-00 CVCS - LETDOWN FLOW?ATH LO-LP-0920 -02 CVCS - CHARGING FLOWPATH LO-LP-09202-01 CVCS - ALTERNATE FLOW?ATHS LO-L?-09401-01-C 3LINDIR MAKIUP SYSTEM LO-LP-09501-00 CVCS-SEAL INJECTION AND RETURN FLOW?ATH LO-LP-1010;-00 OCW SYSTIM LO-12 ~~001-02-C
. DIISIL GINIRATORS - INTRO AND LAYOUT LO-L?-11101-01-C DIISIL ING:NI AUXILIARIES -
FUEL OIL SYS LO-L?-11102-01-C DIISEL INGINE AUXILIARIES -
AIR START SYSTEM LO-LP-11103-01-C DIESEL ENGINE AUXILIARIES -
COM3USTION AIR & EXHAUST SYS 1
4 0
6 LO LESSON PLANS .
Listed by Current LESSON PLAN Number JULY 1987 Current No. Title LO-LP-11104-00-C DIESIL ENGINE AUXILIARIES -
LUBE OIL SYSTEM & CRANKCASE -
VENTILATION LO-LP-11105-02-C DIES 2L ENGINE AUXILIAR IS: -
JACXIT WATZR COOLING SYSTZM LO-LP-11201-01-C ENGINE CONTROL AND PROT LO-LP 1202-04-C GIN AND GIN 3RKR CNTRL AND PROT LO-L?-12101-06-C RER SYSTEM
- O-;?-13001-01-C ICCS OV2RVIZW LO-L?-13101-02 ECCS - PART II LO-LP-13201-01 ECCS - PART I LC-LP-15101-00 CONTAINMENT S? RAY SYSTEM LO-LP-16001-01 RCS OVERV 2W LO-LP-16201-OO REACTOR VESSEL & CORE CONSTRUCTION LO-L?-16202-00 REACTOR VESSEL DES ~GN &
?Z3RICATION LO-L?-16301-03-C PRESSURIZER & PRT LO-L?-16302-01-C PRESSURIE2R LIVIL CONTROL &
PROTECTION LO-L?-16303-01-C ?RESSURIZZR PR2SSURE CONTROL &
PROTICTION LO-LP-16401-00 REACTOR COOLANT ?UM?
LO-LP-16 5 01-01 -C COLD OVERPRESSURE MITIGATION SYS LO-L?-16601-00-C DIGITAL METAL IMPACI MON SYS (DMIMS) 2 n
l -
l l>
1- LO LESSON PLANS Listed by Current LESSON PLAN Number L JULY 1987 Current No. Title 1
i LO-LP-16701-00 REACTOR VESSEL LEVEL INST SYS l (RVLIS)
LO-LP-17101-01 SOURCE RANGE NIS 1
LO-LP-1720~-00 INTERMEDIATE RANGE NIS LO-LP-17301-01 POWER RANGE NIS LO-LP-18201-00 STM GEN FEED PMP TUR3:NE AND v a z a . n.,--S A...... ..
LO-LP-18202-00 MAIN FEEDWATER PUMP SPEED CONTROL LO-LP-18301-02-C STEAM GEN WTR LVL CONT SYS (SGWLC)
LO-LP-19101-03-C FEED AND CONDENSATE LO-LP-20101-05-C AUMILIARY FEEDWATER SYSTEM LO-L?-21101-01-C STEAM GENERATOR LO-LP-21102-01 MAIN STEAM SYS LO-LP-21201-02 STEAM DUMPS LO-LP-21301-01 STEAMLINE PRESSURE ~NST LO-LP-23203-01 ESF ROOM COOLERS LO-LP-23502-01 ESSENTIAL CHILLED WTR SYS
- [J-LP-25101-02-C FUEL HANDLING SYS LO-LP-25102-01 FUIL STORAGE & SPENT FUEL P~T COCLING & PURIFICATION LO-LP-2520~-03-C REFUELING LO-LP-27101-03 ROD CONCROL PART ~
LO-LP-27;O2-02 . ROD CONTROL SYS PART II LO-LP-27201-01 ROD POSIT *0N INDICATION 3
_ _ _ _ _ _ _ - - _ _ _ ____--_-____-___- w
LO- LESSON PLANS Listed by Current LESSON PLAN Number JULY 1987 Current No. Title LO-LP-28101-01-C SOLID STATE PROTECTION SYS (SSPS)
LO-LP-28201-02 CTMT ISO SYS LO-L?-29101-00 CNMT HEAT REMOVAL SYS LO-LP-29103-00 CTMT COM3USTIBLE GAS CONTROL LO-LP-30101-00 MAIN TURB~NE.
LO-L?-30102-00 MOISTURE SEPARATOR REEEATERS LO-L?-30302-00 TUR3INE PROT 2CTION LO-LP-30303-02-C TUR3INE CONTROL LO-LP-31102-00 GENERATOR ELEC SYS LO-L?-32101-01 DIGITAL RADIATION MONITORING SYSTEMS LO-LP-33103-00 NEUTRONS FROM FISSION LO-LP-33104-00 NEUTRON DIFFUSION LO-LP-33201-00 REACTIVITY & REACT VITY COEFFICIENTS LO-LP-33202-30 MODERATOR TEMPERATURE CO-ve u... C ._r-w .
LO-LP-33203-00 FUEL TEM? COEFF AND DO??LER 4 LO-L?-33204-01 VOID, PRESSURE, POWER AND )
ISOTEIR TEMP COEFF.
LO-LP-33205-00 EXCESS REACTIVITY i
LO-LP-33301-01-C CHEMICAL SHIM LO-L?-33302-00 FISS:ON PROD. POISONS / SAMARIUM LO-LP-33303-00 XENON l
1 LO-LP-33304-00 CONTROL RODS j l 1 1
4 1
LO L2SSON ?LANS Listed by Current LESSON ?LAN Number JULY 1987 l Current No. Title LO-LP-33401-00 NEUTRON MULT & SIX FACTOR FORMULA LO-LP-33403-00 RCSPONSE OF KIFF TO CHNG PARAMETERS LO-LP-33501-00 SOURC2 NEUTRONS AND SU3 CRITICAL MULT LO-LP-33601-00 POW 2R CHANGES /INHOUR EQUAT!ON LO-LP-33602-00 POWER OPS: ?WR RESPONSE ~
LO-LP-33603-00 SHUTDOWN MARGIN CALCULATION LO-LP-33604-01-C CALCULATION OF EC?, ICC LO-L?-34101-00 THIRMO TIRMS AND CONC PTS LO-LP-34102-00 HTFF - LAWS OF THERMODYNAMICS LO-L?-34103-00 INTROPY LO-LP-34104-00 PROPERT!2S OF WORX:NG FLUIDS LO-LP-34105-00 MODES O? HEAT TRANSFER LO-LP-34106-00 THERMO CYCLES AND POWER
._ Y ,\N'.
= .
-?' ;
s LO-LP-34107-00 FLUID FLOW THEORY AND CONCE??S LO-LP-34108-00 TWO-?HASI FLOW (HTFF)
LO-LP-34109-00 CORE FLOW (HTFF)
LO-L?-34110-02-C NATURAL CIRCULATION FLOW (HTFF)
LO-L?-34201-01 THERMO3YNAMICS OF COMPONINTS LO-LP-34202-01 THERMAL DESIGN LIMITS LO-L?-34203-02-C A??L 23 THERMODYNAMICS i l
LO-LP-34204-00 FUEL ROD HEAT PRODUCTION &
TRANS?CRT 5
l l
\
a 1
LO LESSON ?LANS i Listed by Current LESSON PLAN Number JULY 1987 Current No_. Title LO-L?-35104-00 PRIMARY' SYSTEM SAMPL:NG LO-LP-35204-01-C MATERIALS AND PTS REVIEW LO-LP-35205-00 MEATUP AND COOLDOWN L MITS LO-LP-36001-01-C INTRO TO MCD: ACCIDENT ANAL METHODS LO-LP-36101-OO-C MCD CORE COOLING MICEANICS LO-LP-36102-00-C RECOGNIZING CORE DAMAGE:
INCORE INSTRUMENTS LO-LP-36103-OO-C EXCORE INSTRUMENT RESPONSE TO CORE DAMAGE LO-LP-36104-00-C MCD VITAL INSTRUMENTAL:ON LO-LP-36105-01-C POST ACCIDENT PRIMARY RADIO-CHEMISTRY LO-L?-36106-OO-C RADIOLOGICAL ASPECTS OF CORE DAMAGE LO-LP-36107-01-C GAS GENERATION LO-L?-37001-02-C INTRODUCTION TO THE EO?'S LO-LP-37002-02-C TORMAT AND USE OF THE EMERGENCY PROCEDURES LO-LP-37011-02-C REACTOR TRIP RESPONSE LO-L?-37012-03-C NATURAL CIRCULATION C00L30HN LO-LP-37021-02 SI/INADVERT SI RES?ONSE LO-L?-37031-01-C LOSS 07 ALL AC ?OWER LO-L?-37041-02-C ANT:CI?ATED TRANSIENT WITHOUT TRI?
LO-LP-37051-02-C LOSS OF SECONDARY HEAT SINK 6 l f
LO LESSON PLANS Listed by Current LESSON PLAN Number JULY 1987 Current No. Title LO-LP-37 11-03-C OPERATOR RESPONSE TO A LOSS OF PRIMARY COOLANT LO-LP-37121-03-C LOSS OF SECONDARY COOLANT /
FAULTED LO-LP-37311-03-C OPERATOR RESPONSE TO SGTR LO-LP-38103-01-C RAD SURVEYS & COUNTING INST w AIR SAMPLERS LO-LP-38201-00 PROPERTIES & INTERACTIONS OF RADIATION LO-LP-38202-00 TERMINOLOGY & DECAY EQUATIONS LO-LP-38203-00 TIME, DISTANCE & SE ELD:NG l
LO-LP-38204-00 DOSE RATE & SE! ELD:NG '
LO-LP-38205-00 3IOLOGICAL EFFECTS OF RAD -
PART I LO-LP-38206-00 3IOLOGICAL EFFECTS OF RAD -
PART II - RIV LO-LP-38208-00 CONTAMINATION CONTROL LO-LP-38209-00 INTERNAL EXPOSURE l
\
LO-LP-38210-00 RESPIRATORS I LO-LP-36211-00-C CONTAMINATION SURVEY TECEN! QUES & FIELD EVAL OF SMEARS LO-LP-38212-00-C AIR 3ORNE ACTIVITY SURVEY TECENQUES LO-LP-38213-01-C RADIATION SURVEY TECENIQUES I LO-LP-38302-04-C EST & POSTING RCA'S/DELIN OF RADIAT!ON CONTROL LO-LP-43101-01-C FIRE PROTECTION 7
e
- LO LISSON PLANS Listed by Current LESSON PLAN Number l JULY 1987 Current No. Title LO-L?-44101-00 3ORON RICYCLI SYSTIM LO-LP-46101-01 GASEOUS RADIOACTIV: WASTE SYSTEM LO-LP-47101-00 LIQUID RADWASTI SYSTEM LO-LP-60101-01-C REMOTE SMUTDOWN SYSTZM LO-L?-64201-01 POST ACCID NT SAMPL:NG SYSTEM l
1 I
l l
I l
I 8 -
l
V- .
PLANT ADMINISTRATIVE PROCEDURES PROCEDURE REVISION NUMBER NUMBER TITLE 00003-C 1 Shift Relief 00004-C 1 Plant Communications 00005-C 3 hrertime Authorization 00008-C 6 Plant Lock and Key Control 00052-C 4 Temporary. Changes to Procedures 00054-C 2 Rules for Performing Procedures 00152-C 4T Federal and State Reporting Requirements 00300-C 2T Authority to Startup and Shutdown Reactors 00301-C 2 hain Control Room Access and Personnel Conduct 00304-C 9 Equipment Clearance and Tagging 00306-C 5 Temporary Jumper and Lifter Wire Control 00308-C 1 Independent Verification Policy 00920-C 3 Radiation Exposure Limits 00930-C 3 Radiation and Contamination Control O
.(- ,
4 1'
t -.O OPERATIONS ADMINISTRATIVE PROCEDURES
. J.. -
PROCEDURE. REVIS0N NUMBER NUMBER TITLE 1
10000-C 4T Conduct of Operations l~ 100011C .3 Logkeeping.
10002-0 3 Plant Operating Orders 10003-C 4 Manning the Shift 10004-C 3 Shift Relief 10005-C .1 Operability Status Indication.for Plant Safety Systems
- 10006-C 6T Reactor Trip Re lew 10007-C 1 Reset of Lock-Out Relays and Relay Targets 10008-C 4 Recording Limiting Conditions for Operations 10009-C 3 Operator Aids 10018-C 2 Annunciator Status Control 10019-C 1 Control of Safety Related Locked Values
.]
v
4
(~3 SYSTEM ALIGNMENT PROCEDURES V
PROCEDURE REVISION NUMBER NUMBER TITLE 11869-C 2 Balance of Plant Operator Relief Checklist 11870-C 5 Operations Supervisor Relief Checklist 11871-C 3 Shift Supervisor Relief Checklist 11872-C 4 Reactor Operator Relief Checklist 11875-C 1 LCO Status Sheet 11876-C 1 LCO Status Log U
T.
[.[ . ,,1 -
,g.'
UNIT OPERATING PROCEDURES
=1 .
(V.
PROCEDURE REVISION NUMBER NUMBER TITLE l
1.
12000-1 3 Refueling Recovery 12001-1 4 Unit Heatup.To Hot Shutdown (Mode 5 To Mode 4) i 12002-1 4 Unit Heatup To Normal Operating Temperature and Pressure (Mode 4 To Mode 3) 12003-1 7 Reactor Startup (Mode 3 to Mode 2) .
12004-1 6 _ Power Operation (Mode 1) 12005-1 2 Reactor Shutdown To Hot Standby 12006-1 4 Unit Cooldown to Cold Shutdown 12007-1 3 Refueling Entry O
s'
<s SYSTEM OPERATING PROCEDURES 1
PROCEDURE- REVISION j l NUMBER NUMBER TITLE {
I 13003-1 3 . Reactor Coolant Pump Ope' ration
-13006-1 5 Chemical And Volume Control System'Startup And Normal Operation - (L) 13008-1 1 CVCS Excess Letdown 13009-1 2 CVCS Reactor Makeup Control System (L) 13011-l' 5 Residual Heat Removal System 13105-1 '2 Safety Injection System )
13115-1 2 Containment Spray System - (L) 13145-1 6 Diesel Generators 13150-1 2 Nuclear Service Cooling Water System - (L) 0s 13201-1 2 Gaseous. Waste Processing System.
13202-1 2 Gaseous Releases 13214-1 3 Liquid Waste Processing System 13216-C 3 Liquid Waste Release - (L) 13405-1 3 125V DC 1E Electrical Distribution System 13406-1 1 125V DC Non IE Electrical Distribution System 13415-1 2 Reserve Auxiliary Transformers
'13416-1 1 Unit Auxiliary and Main Transformers 13420-1 3 13.8KV AC Electrical Distribution System O
4 SYSTEM OPERATING PROCEDURES
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PROCEDURE REVISION NUMBER NUMBER TITLE 13425-1 2 4160V AC Non IE Electrical Distribution System 13427-1 5 4160V AC 1E Electrical Distribution System 13429-1 2 480V AC 1E Electrical Distribution System 13430-1 1 460V AC Non IE Electrical Distribution System 13431-1 2 120V AC 1E Vital Instrument Distribution System - (L) 13432-1 1 120V AC Non IE Instrument Distribution System 13501-1 2 Nuclear Instrumentation System
(' 13502-1 1 Control Rod Drive and Position Indication s-- System - (L) i 13601-1 1 Steam Generator and Main Steam System Operation - (L) 13610-1 4 Auxiliary Feedwater System 13615-1 3 Condensate and Feedwater Systems - (L) 13710-1 1 Service Air System 13711-C 1 Instrument Air System - (L) l 13715-1 1 Component Cooling Water System 13716-1 3 Auxiliary Component Cooling Water System -
(L) 13719-1 2 Spent Fuel Pool Cooling and Purification System 13724-1 2 Circulating Water System
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0 SYSTEM OPERATING PROCEDURES PROCEDURE REVISION TITLE i NUMBER NUMBER l
13744-1 2 Essential Chilled Water System - (L) l 13800-1 3 Main Turbine Operation 13830-1 5 Main Generator Operation 1
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r'~N i ALARM RESPONSE PROCEDURES PROCEDURE REVISION TITLE NUMBER NUMBER 17001-1 5 Annunciator Response Procedure ALB 01 on Panel 1A1 17002-1 4 Annunciator Response Procedures ALB02 on Panel 1A1 on MCB 17003-1 2 Annunciator Response Procedure ALB 03 on Panel 1A1 on MCB 17004-1 3 Annunciator Response Procedures for ALB04 on Panel 1A1 on MCB 17005-1 4 Annunciator Response Procedures for ALB-05 17006-1 5 Annunciator Response Procedures for ALB-06 17007-1 2 Annunciator Response Procedures for ALB-07 "Q
's_ / 17008-1 3 Annunciator Responce Procedure for ALB 08 on Panel 1A2 on MCB 17009-1 1 ARP for ALB-09 on Panel ICI on MCB 17010-1 3 Annunciatory Response Procedures for ALB 10 on Panel 1C1 17011-1 2 Annunciator Response Procedure for ALB 11 on Panel ICI on MCB 17012-1 2 Annunciator Response Procedures for ALB 12 on Panel 1C1 on MCB 17013-1 3 Annunciator Response Procedures for ALB13 on Panel 1B1 on MCB 17014-1 3 Annunciator Response Procedures for ALB 14 on Panel 1B1 on the MCB 17015-1 2 Annunciator Response Procedures for ALB 15 on Panel 1B1 on MCB 17016-1 2 Annunciator Response Procedures ALB
,.s 16 on Panel 1B1 on MCB
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F300EDURE REVISION TITLE NUMBER NUMBER i
17017-1 1 Annunciator Response Procedures for ALB 17 on Panel 1B2 on MCB 17018-1 0 Annunciator Response Procedures for ALB 18 Panel 1B2 on MCB 17019-1 2 Annunciator Response Procedures ALB 19 on Panel IB2 on MCB 17020-1 3 Annunciator Response Procedures for ALB 20 on Panel 1B2 on MCB l
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ABNORMAL OPERATING PROCEDURES PROCEDURE REVISION TITLE NUMBER NUMBER 18001-1 2 Primary Systems Instrumentation Malfunction
-18002-1 2 Nuclear Instrumentation System Malfunction 18003-1 3 Rod Control System Malfunction 18004-1 3 Reactor Coolant System Leakage 18005-1 1 Partial Loss of Flow 18006-1 1 Fuel Handling Event 18007-1 2 Cnemical and Volume Control System Malfunction 18008-1 2 Secondary Coolant Leakage 18009-1 2 Steam Generator Tube Leak 18010-1 1 Main Generator Malfunctions 18011-1 2 Turbine Trip Below P-9 18012-1 2 Turbine Runback 18015-1 2 Secondary Plant Chemistry 18016-1 1- Condensate and Feedwater Malfunction 18019-1 2 Loss of Residual Heat Removal 18020-1 1 Loss of Component Cooling Water 18021-1 2 Loss of Nuclear Service Cooling Water System 18022-1 2 Loss of Auxiliary Component Cooling Water
'18023-1 1 Loss of Turbine Plant Cooling Water System 18025-1 1 Loss of Utility Water j 18028-1 3 Loss of Instrument Air 18030-1 2 Loss of Spent Fuel Pool Level or Cooling 18031-1 2 Loss of Class 1E Electrical Systems i O l i
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%s sROCEDURE REVISION TITLE NUMBER NUMBER 18032-1 0 Loss of 110VAC Instrument Power 18035-1 2 Toxic / Flammable Gas Release 18036-1 2 Abnormal Operating Procedurt leismic Event 18038-1 4 Operations from Remote Shutdown Panels x.J l
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EMERGENCY OPERATING PROCEDURES
. PROCEDURE REVISION TITLE NUMBER NUMBER 19000-1 2 E-0 Reactor Trip or Safety injection 19001-1 2 ES-0.1 R-eactor Trip Response 19002-1 2 .ES-0.2 Natural Circulation Cooldown 19003-1 2 ES-0.3 Natural Circulation Cooldown with Steam Void in Vessel (With RVLIS) l 19004-1 2 ES-0.4 Natural Circulation Cooldown with Steam Void in Vessel (Without RVLIS) 19005-1 2 ES-0.0 Re-diagnosis 19010-1 4 E-1 Loss of Reactor or Secondary Coolant 19011-1 2 ES-1.1 SI Termination 19012-1 2 ES-1.2 Post-LOCA Cooldown and Depressurization V 19013-1 3 ES-1.3 Transfer to Cold Leg Recirculation 19014-1 2 ES-1.4 Transfer to Hot Leg Recirculation 19020-1 0 E-2 Faulted Steam Generator Isolation 19030-1 3 E-3 Steam Generator Tube Rupture 19031-1 2 ES-3.1 Post SGTR Cooldown Using Backfill l
19033-1 2 ES-3.3 Post SGTR Cooldown Using Steam Dumps l 19100-1 2 ECA-0.0 Loss of All AC Power 19101-1 2 ECA-0.1 Loss of All AC Power Recovery without SI Required ;
19102-1 2 ECA-0.2 Loss of All AC Power Recovery with SI Required 19111-1 3 ECA-1.1 Loss of Emergency Coolant recirculation 19112-1 0 ECA-1.2 LOCA Outside Containment 19121-1 3 ECA .2.1 Uncontrolled Depressurization of All Steam Generators
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(T EMERGENCY OPERATING PROCEDURES lJ PROCEDURE' REVISION TITLE NUMBER NUMBER 19131-1 3 ECA-3.1 SGTR With Loss of Reactor Coolant:
Subcooled Recovery Desired 19132-1 3 ECA-3.2 SGTR With Loss of Reactor Coolant -
Saturated Recovery Desired 19133-1 2 ECA-3.3 SGTR Without Pressurizer Fressure Control 19200-1 2 F.O. Critical Safety Function Status Trees 19211-1 2 FR-S.1 Response to Nuclear Power Generation /ATWT.
19212-1 0 FR-S-2 Response to Loss of Core Shutdown 19221-1 3 FR-C.1 Response to Inadequate Core Cooling 19222-1 3 FR-C.2 Response to Degraded Core Cooling-I 19223-1 2 FR-C.3 Response to Saturated Core Cooling
. 19231-1 4 FR-H.1 Response to Loss of Secondary Heat Sink 19232-1 2 FR-H.1 Response to Steam Generator Overpressure 19233-1 1 FR-H.3 Response to Steam Generator High Level 19234-1 1 FR-H.4 Response to Loss of Normal Steam Release Capabilities 19235-1 2 FR-H.S Response to Steam Generator Low Level 19241-1 3 FR-P.1 Response to Imminent Pressurized Thermal Shock Condition 19242-1 2 FR-P.2 Response to Anticipated Pressu'rized Thermal Shock Condition 19251-1 2 FR-Z.1 Response to High containment Pressure vb i
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[~h EMERGENCY OPERATING PROCEDURES
\s' PROCEDURE REVISION TITLE HUMBER NUMBER 19252-1 0 FR-Z.2 Response to Containment 19253-1 1 FR-Z.3 Response to High Containment:
Radiation Level 19261~1 2 FR-I.1 Response to High Pressurizer Level !
19262-1 0 FR-I.2 Recponse to Low Pressurizer Level 19263-1 2 FR-I.3 Response to Voids in Reactor Vessel 1
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HEALTH PHYSICS PROCEDURES t
PROCEDURE REVISION TITLE NUMBER NUMBER 43005-C 3 Establishing and Posting Radiation Control Areas 43007-C 5 Issuance Use and Control of Radiation Work Permits ;
43101-C 1 High Radiation Area Access Control O
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-s EMERGENCY RESPONSE PROCEDURES
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PROCEDURE REVISION TITLE NUMBER NUMBER 91001-C 4 Emergency Classification and Implementing Instructions -- (L) 91002-C 10 Emergency Notification - (L) 91102-C 3 Duties of the Emergency Director 91301-C 2 Emergency Exposure Guidelines t
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<-'s REFUELING PROCEDURES N
PROCEDURE REVISION TITLE NUMBER NUMBER 93210-C 1 New Fuel Elevator Operating Instructions 93220-C 1 Fuel Handling Machine Operating Instructions 93260-C 1 Fuel Transfer System Operating Instructions 93270-C 1 Sigma Refueling Machine Operating Instructions I 93300-C 2 Conduct of Refueling Operations 93360-C 1 Limitations and Precautions for Handling New and Partially Spent Fuel Assemblies
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s OPERATIONS STANDING ORDERS INDEX 07/87 l 1-87-03 1-87-06 1-87-07 1-87-08 1-87-13 1-87-17 1-87-18 1-87-23 1-87-25 1-87-34 O
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