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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F9941999-10-15015 October 1999
Discusses FPC 970819 Request for Temporary Relief from ASME Code Section XI Requirements to Repair ASME Class 3 Nuclear Service & Decay Heat Sea Water System Piping.Forwards SE Containing Results of Staff Review
ML20217J5171999-10-13013 October 1999
Informs That on 990930,NRC Staff Completed mid-cycle PPR of Plant,Unit 3 & Did Not Identify Any New Areas That Warranted More than Core Insp Program.Previously Planned Regional Initiative Insp of safety-related Mod Will Be Performed
3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999
Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed
3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999
Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made
ML20212L0771999-10-0404 October 1999
Forwards SER Accepting Licensee Relief Requests 98-012 Through 98-018 Involving Containment Insps at Crystal River Unit 3 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(a)(3)(ii)
ML20217D6551999-10-0101 October 1999
Requests That Natl Communication Sys Arrange for Licensee Participation in Government Emergency Telecommunications Service,Per NRC Info Notice 99-025
ML20212J8481999-10-0101 October 1999
Forwards Safety Evaluation Re Second 10 Yr Interval ISI Program Requests for Relief 98-009-II.Reliefs Granted for 98-009-II,Parts B & C & 98-010-II & 98-011-II
3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999
Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment
3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999
Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331
ML20212F7251999-09-23023 September 1999
Discusses Staff Review of Util 980330 Response,As Suppl on 990514,to GL 97-06, Degradation of SG Internals. Staff Concludes That Licensee Responses to GL Provide Reasonable Assurance That Condition of SG Internals Acceptable
ML20212F7331999-09-23023 September 1999
Discusses Util Licensing Action for GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants. NRC Ack Efforts Util Completed to Date in Preparing Crystal River,Unit 3 for Y2K Transition
3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999
Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46
ML20212E6741999-09-21021 September 1999
Forwards Safety Evaluation Accepting Proposed EAL Changes Submitted by ,As Supplemented by 981120,990713 & 0831 Ltrs,Incorporating Guidance in NUMARC/NESP-007,Rev 2, Methodology for Development of Eals
3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999
Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)
3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999
Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief
ML20212F3141999-09-13013 September 1999
Forwards Insp Rept 50-302/99-05 on 990704-0814.Violations Noted,But Being Treated as non-cited Violations
ML20211L9081999-09-0303 September 1999
Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Crystal River Unit 3
ML20211Q7581999-09-0101 September 1999
Forwards Summary of 990812-13 Training Managers Conference in Atlanta,Georgia Re Recent Changes to Operator Licensing Program.List Conference Attendees,Copy of Presentation Slides & List of Participant Questions Encl
3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999
Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals
ML20211G7111999-08-30030 August 1999
Modifies Approval of 980521 Request for Exception to 10CFR50.4(b)(6) & Grants Util Approval to Submit Copies of Future Updates to FSAR as Listed
ML20211G7031999-08-30030 August 1999
Informs of Approval of Util 980521 Request for Exception to 10CFR50.4(b)(6),allowing Util to Submit Updates to Plant Ufsar.Ltr Modifies That Approval & Grants Util Approval
3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999
Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002
ML20212C1351999-08-27027 August 1999
Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input
3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999
Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71
3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999
Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3
3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999
Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05
3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999
Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal
3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999
Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2
3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value
05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999
Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented
ML20210Q4511999-08-0505 August 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006
ML20210P0741999-08-0505 August 1999
Forwards SE Accepting Licensee 980416 & 1130 Ltrs Re Third 10-year Interval ISI Program Plan & Associated Requests for Relief for Plant,Unit 3
3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999
Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603
ML20210G8551999-07-27027 July 1999
Forwards Insp Rept 50-302/99-04 on 990523-0703.One Violation Identified & Being Treated as Noncited Violation
3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999
Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments
ML20209H5211999-07-16016 July 1999
Forwards Request for Addl Info Re Licensee Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in CR-3 once-through Steam Generators in Order to Complete Review
ML20209G3231999-07-15015 July 1999
Forwards Biological Opinion Issued by Natl Marine Fisheries (NMFS) of Dept of Commerce.Nmfs Concluded That Operation of Cw Intake Sys of Crystal River Not Likely to Jeopardize Existence of Species Listed in Biological Opinion
ML20209G3481999-07-15015 July 1999
Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon
3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999
Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl
3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999
Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl
3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999
Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl
3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999
Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730
3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999
Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held
3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21
ML20196L1261999-07-0707 July 1999
Discusses Closeout of TAC MA0538 Re License Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Unit 3
3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999
Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3
ML20196J4991999-07-0101 July 1999
Advises That Info Contained in ,Which Included TR BAW-2346P,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20209C0811999-06-25025 June 1999
Forwards Overdue Controlled Document Transmittals for Listed Documents
3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999
Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl
1999-09-03
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEAR3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999
Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed
3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999
Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made
3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999
Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment
3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999
Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331
3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999
Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46
3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999
Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)
3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999
Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief
3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999
Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals
ML20212C1351999-08-27027 August 1999
Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input
3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999
Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002
3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999
Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71
3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999
Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3
3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999
Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal
3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999
Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05
3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999
Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2
05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999
Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented
3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value
3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999
Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603
3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999
Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments
ML20209G3481999-07-15015 July 1999
Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon
3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999
Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl
3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999
Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl
3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999
Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl
3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999
Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730
3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999
Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held
3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999
Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3
ML20209C0811999-06-25025 June 1999
Forwards Overdue Controlled Document Transmittals for Listed Documents
3F0699-12, Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested1999-06-23023 June 1999
Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested
3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999
Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl
3F0699-08, Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments1999-06-21021 June 1999
Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments
3F0699-09, Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl1999-06-0404 June 1999
Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl
3F0599-21, Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads1999-05-28028 May 1999
Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads
3F0599-10, Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl1999-05-26026 May 1999
Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl
ML20207E4341999-05-25025 May 1999
Submits 30-day Written Rept on Significant PCT Changes in ECCS Analysis for ANO-1.CRAFT2 Limiting PCT for ANO-1 Was Bounded by 1859 F PCT Calculated at 2568 Mwt for Crystal River 3 Cold Leg Pump Discharge Break Size of 0.125 Ft
3F0599-22, Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs1999-05-21021 May 1999
Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs
3F0599-18, Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM1999-05-14014 May 1999
Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM
3F0599-17, Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments1999-05-14014 May 1999
Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments
3F0599-07, Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 19781999-05-14014 May 1999
Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 1978
3F0599-03, Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR1999-05-12012 May 1999
Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR
3F0599-05, Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl1999-05-12012 May 1999
Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl
3F0599-08, Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments1999-05-0303 May 1999
Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments
3F0599-09, Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 19981999-05-0101 May 1999
Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 1998
3F0499-24, Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent1999-04-30030 April 1999
Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent
3F0499-09, Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 9907301999-04-30030 April 1999
Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 990730
3F0499-23, Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements1999-04-23023 April 1999
Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements
3F0499-18, Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl1999-04-20020 April 1999
Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl
3F0499-05, Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin1999-04-16016 April 1999
Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin
3F0499-08, Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 19981999-04-16016 April 1999
Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 1998
1999-09-27
[Table view]
Category:UTILITY TO NRC
MONTHYEAR3F0990-11, Forwards Final Status Update Re Design & Operations Verification for Instrument Air Sys Per Generic Ltr 88-141990-09-20020 September 1990
Forwards Final Status Update Re Design & Operations Verification for Instrument Air Sys Per Generic Ltr 88-14
3F0990-05, Forwards 1990 Inservice Insp Summary Rept. Rept Contains Owners Data Rept,Data Summary Sections for Class 1,2 & 3 Components,Rept for Repair & Replacements & Listing of Exams1990-09-14014 September 1990
Forwards 1990 Inservice Insp Summary Rept. Rept Contains Owners Data Rept,Data Summary Sections for Class 1,2 & 3 Components,Rept for Repair & Replacements & Listing of Exams
3F0990-08, Forwards Response to Violations Noted in Insp Rept 50-302/90-23.Corrective Actions:Training Session Conducted to Stress Importance of Attachments Being Part of Work Package When Required by Procedure1990-09-13013 September 1990
Forwards Response to Violations Noted in Insp Rept 50-302/90-23.Corrective Actions:Training Session Conducted to Stress Importance of Attachments Being Part of Work Package When Required by Procedure
3F0890-23, Discusses Decommissioning Financial Assurance Rept Dtd 900726.Amount Util Collecting Exceeds Amount Necessary Based on NRC Formula & Does Not Include Estimated Cost of Removal & Disposal of Nonradioactive Structures & Matls1990-08-30030 August 1990
Discusses Decommissioning Financial Assurance Rept Dtd 900726.Amount Util Collecting Exceeds Amount Necessary Based on NRC Formula & Does Not Include Estimated Cost of Removal & Disposal of Nonradioactive Structures & Matls
ML20028G8251990-08-29029 August 1990
Advises That Supplemental Response to Insp Rept 50-302/89-18 Will Be Submitted by 901030
ML20059G1721990-08-24024 August 1990
Submits Info Re Change in Operator License Status.Re Rawls & Wa Stephenson Senior Reactor Licenses Should Be Terminated, Effective 900817 Due to Reassignment from Position Requiring Licenses
3F0890-15, Forwards Fitness for Duty Program Performance Data for Period of Jan-Jun 19901990-08-23023 August 1990
Forwards Fitness for Duty Program Performance Data for Period of Jan-Jun 1990
3F0890-21, Forwards Semiannual Radioactive Release Rept Jan-June 1990 for Crystal River Unit 3 & Rev 15 to Crystal River Unit 3 Odcm1990-08-23023 August 1990
Forwards Semiannual Radioactive Release Rept Jan-June 1990 for Crystal River Unit 3 & Rev 15 to Crystal River Unit 3 Odcm
ML20059A0031990-08-16016 August 1990
Responds to NRC 900613 Request for Addl Info Re Util 871222 Response to Violations Noted in Insp Rept 50-302/87-30
3F0890-03, Forwards Rev 11 to Inservice Insp - Pump & Valve Program, Crystal River Unit 31990-08-16016 August 1990
Forwards Rev 11 to Inservice Insp - Pump & Valve Program, Crystal River Unit 3
3F0890-10, Advises That Util Completed Mods to Comply w/10CFR50.62 Requirements Re Reduction of Risk from ATWS Events1990-08-16016 August 1990
Advises That Util Completed Mods to Comply w/10CFR50.62 Requirements Re Reduction of Risk from ATWS Events
3F0890-05, Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 1741990-08-10010 August 1990
Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 174
ML20058L2001990-08-0202 August 1990
Provides Current Status of Reg Guide 1.97 Activities. Pressurizer Heater Status & Main Steam Safety/Relief Valve Position Indications Completed
3F0790-10, Forwards Justification for Continued Operation Re Emergency Diesel Generator Block Loading Voltage Dips.Util Will Install Higher Accuracy Relays to Improve on Accuracy & Repeatability of Load Intervals1990-07-18018 July 1990
Forwards Justification for Continued Operation Re Emergency Diesel Generator Block Loading Voltage Dips.Util Will Install Higher Accuracy Relays to Improve on Accuracy & Repeatability of Load Intervals
3F0790-06, Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-81990-07-12012 July 1990
Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-8
ML20055D5561990-06-29029 June 1990
Forwards 890505 & s to Be Placed in Plant File
3F0690-15, Informs That Tech Spec Actions Identified in Util Addressed as Part of Tech Spec Improvement Program,Per 900518 Request for Programmed Enhancements for Generic Ltr 88-171990-06-29029 June 1990
Informs That Tech Spec Actions Identified in Util Addressed as Part of Tech Spec Improvement Program,Per 900518 Request for Programmed Enhancements for Generic Ltr 88-17
3F0690-22, Forwards Annual Financial Repts for 1989 for Orlando Utils Commission & Cities of Bushnell,Leesburg,Ocala & Tallahassee,Per 10CFR50.71(b)1990-06-27027 June 1990
Forwards Annual Financial Repts for 1989 for Orlando Utils Commission & Cities of Bushnell,Leesburg,Ocala & Tallahassee,Per 10CFR50.71(b)
3F0690-19, Responds to Deviations Noted in Insp Rept 50-302/90-15. Corrective Actions:All Reg Guide 1.97 Category 1 Instruments on Main Control Board Marked & Engineered Safeguards Matrix Indicating Lights Arranged in Unique Array1990-06-25025 June 1990
Responds to Deviations Noted in Insp Rept 50-302/90-15. Corrective Actions:All Reg Guide 1.97 Category 1 Instruments on Main Control Board Marked & Engineered Safeguards Matrix Indicating Lights Arranged in Unique Array
ML20043H5781990-06-21021 June 1990
Responds to Generic Ltr 89-06, Spds. All Open Issues Identified in NRC SER & Plant SPDS Satisfies NUREG-0737, Item I.D.2 & Suppl 1
ML20044A6121990-06-21021 June 1990
Forwards Payment of Civil Penalty,Per NRC 900524 Order Based on Findings in Insp Rept 50-302/89-09
ML20043J0221990-06-21021 June 1990
Submits Info in Support of Tech Spec Change Request 175,Rev 1,Suppl 1 Re Spent Fuel Pool Storage Capacity at Plant
ML20043H4151990-06-21021 June 1990
Forwards Response 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.
3F0690-18, Responds to Violations Noted in Insp Rept 50-302/90-09. Corrective Action:Temporary Lettering Placed on Index Plates for Consistency W/Previous Markings Immediately Following Discovery of Error1990-06-20020 June 1990
Responds to Violations Noted in Insp Rept 50-302/90-09. Corrective Action:Temporary Lettering Placed on Index Plates for Consistency W/Previous Markings Immediately Following Discovery of Error
ML20043H2901990-06-15015 June 1990
Forwards Results of Refuel 7 once-through Steam Generator (OTSG) Eddy Current Insp,Per Tech Spec Section 4.4.5.5.Eight Defective Tubes & Two Administratively Plugged Tubes in OTSG a Resulted from Review of Insp Data
ML20044A0641990-06-13013 June 1990
Forwards Rev 5 to Physical Security Plan,Replacing Currently Approved Rev 4 W/Amends.Rev Withheld (Ref 10CFR73.21)
ML20043G2271990-06-12012 June 1990
Suppls 900604 Ltr Describing How Control Room Habitability Dose Would Be Adversely Affected by Elimination of Reactor Bldg Flood Vol Unless Overly Conservative Failure Postulations Also Changed.Quarterly Updates to Be Provided
ML20043G3711990-06-12012 June 1990
Forwards 1990 Internal Cash Flow Projection for Plant Which Updates Utils Utilization of Alternative (E)
ML20043G2361990-06-12012 June 1990
Forwards Info Re Fire Protection Sys Reliability for Providing Water to Intermediate Bldg Following High Energy Line Break.B&W Issued Contract to Verify Mass/Energy Release & Motor Starters & Terminal Blocks Insulated
ML20043F1601990-06-0404 June 1990
Provides Supplemental Info on Reactor Bldg Flooding,Per Util 900517 Ltr Describing Resolution Plan Being Pursued.Util Has Limited Vol of Water Contributed by Borated Water Storage Tank & Sodium Hydroxide Tank to Flood Level
ML20043C8721990-05-31031 May 1990
Forwards Rev 0 to Crystal River Unit 3 Cycle 8 Core Operating Limits Rept, Per Tech Spec 6.9.1.7
ML20043B8431990-05-24024 May 1990
Describes Alternative Testing of Reactor Bldg Spray Suction Valves BSV-1 & BSV-8,per Generic Ltr 89-04.At Least One Valve Will Be Disassembled & Inspected During Each Refueling Outage Using Alternate Insp Method
ML20043B2771990-05-18018 May 1990
Advises of Mod to Original Commitment & Plans to Store Seal Ring in Original Storage Location During Plant Operations, Per 790606 Ltr.Mod Minimizes Personnel Exposure & Enhances Seal Plate Leak Tightness Due to Less Handling
ML20043B0321990-05-17017 May 1990
Provides Details of Resolution Util Will Pursue Re Reactor Bldg Flooding Detailed in Encl LER 90-005.Mod Will Be Installed to Add Alarm in Main Control Room to Indicate When Flood Level Reaches Point & Operator Action Begins
ML20043A5441990-05-16016 May 1990
Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project
ML20042G7681990-05-10010 May 1990
Submits Unsatisfactory Performance Testing Incident Repts, Per 10CFR26, Fitness for Duty. Results of Three Positive Blind Test Samples Certified to Contain No Drugs
ML20043A4931990-05-10010 May 1990
Forwards Executed Amend 8 to Indemnity Agreement B-54
ML20042G2101990-05-0707 May 1990
Provides Notice of MW Kirk Permanent Reassignment from Position & Requests Termination of Senior Reactor Operator License 20481-1,effective 900505
ML20042E8611990-04-26026 April 1990
Forwards Annual Financial Repts for Six Participating Owners of Plant
ML20012F2941990-03-30030 March 1990
Forwards Nonproprietary Rev to 51-1176431-02, Crystal River 3 Reactor Vessel...Temp Overpressure Protection, in Support of Tech Spec Change Request 174,Suppl 1 Re Response to Generic Ltr 88-11
ML20042D8321990-03-30030 March 1990
Provides Supplemental Response to Station Blackout Rule Implementation & Affirms That Diesel Generator Target Reliability Will Be Maintained
ML20012E2041990-03-23023 March 1990
Requests Temporary Waiver of Compliance Granted on Tech Spec 3.9.8.2 Re DHR Power Source Requirements
ML20012D9471990-03-21021 March 1990
Requests Approval of Capsule Withdrawal Schedule in Table 3-19 of BAW-1543,Rev 3, Master Integrated Reactor Vessel Surveillance Program to Allow Plant Refuel 7 Outage Plans to Continue on Schedule.Changes Needing NRC Approval Listed
ML20012D7371990-03-19019 March 1990
Responds to Generic Ltr 89-19 Re Resolution of USI A-47. Util Will Implement Appropriate Sys to Protect Against Overfill Concerns
ML20012C4501990-03-13013 March 1990
Forwards Listing of Insurance Policies in Place for Plant as of 900225
ML20012B4821990-03-0707 March 1990
Forwards Inservice Insp Pump & Valve Program Relief Request V-371 Proposing Alternate Acceptance Criteria Requirements for IWP-4150 for Fluctuations in Hydraulic Instrument Readings
ML20012B3651990-03-0101 March 1990
Lists Five Addl Drugs Included in 10CFR26 Re fitness-for- Duty Testing Program.Specimens Identified as Positive on Initial Screening Will Be Confirmed Using Gas Chromatography or Mass Spectrometry at Listed cut-off Levels
ML20012A4041990-02-27027 February 1990
Forwards 1989 Annual Rept of Personnel Exposure in Accordance w/10CFR20.407 & Tech Spec 6.9.1.5.(a) & Annual Rept of Facility Changes,Tests & Experiments in Accordance w/10CFR50.59
ML20006G1731990-02-23023 February 1990
Advises That Util Voluntarily Agrees to Participate in Emergency Response Data Sys Proposed in Generic Ltr 89-15
ML20011F2411990-02-21021 February 1990
Provides Followup on & Documents Discussion in 900116 Meeting Re Emergency Diesel Generator Loading
1990-09-20
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conronation l
. October 20, 1989 3F1089-16 -
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U.S. Nuclear Regulatory Commission Attn: Document Control Desk
. Washington, D.C. 20555 Sub-lect: Crystal River Unit 3 .;
Docket No. 50-302 i' Operating License No. DPR-72 Electrical Enhancement Plan
Dear Sir:
Please find attached five copies of a description of the plan FPC E
has developed to upgrade our understanding of the CR-3 electrical p design basis. This includes two primary features: a rescheduling
! of our existing. Configuration Management (CM) plans to be initiated
! immediately and expansion of the present CM program calculation review to include a full revalidation of the CR-3 electrical I distribution systems. FPC considers this to be an extremely l thorough program and believes the schedule to be appropriate to l' produce a high quality product. We will review this with your l staff at our November 1, 1989 meeting and anticipate incorporating l any' improvements your staff may recommend.
L During our recent meeting at the CR-3 Site and previous conversations it is apparent that concerns regarding overall plant safety with the known electrical issues still exist within the NRC !
staff. FPC hereby communicates our basis for considering the plant l to remain well supported by the present electrical systems design ,
and is safe to operate while our revalidation efforts are being completod. i The EDG's are both capable of supplying sufficient emergency AC power for all likely events. A large LOCA concurrent with a loss of offsite power scenario can load the "A" EDG to approximately 3112 KW which is within its 30 minute rating. The probability of such a scenario is 4.8 E-8 per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period as modeled in the recently reviewed CR-3 PRA. The operator action to reduce loading below 3000 KW is the removal of EFP-1 which is not needed in such scenarios. Further, CR-3 has been analyzed against the NRC's leak-0910270125 891020 PDR ADOCK 05000302 i j
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s P PNU
' GENERAL OFFICE: 3201 Thirty fourth Street South e P.o. Box 14042 . St. Petersbur0, Florida 33733 * (813) 866- 51 y A Florida Progress Company
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L October 20, 1989 3F1089-16 Page 2 before-break criteria and a GDC-4 exemption issued. Therefore, such LOCA's are no longer credible events.
The existing CR-3 station batteries are capable of supplying needed DC loads. The DC loads are now distributed in a configuration such l that actual loads are less than tested loads. The configuration I which existed prior to recent changes are being evaluated to verify design capability. Nevertheless current DC supplies are adequate.
l The CR 1/2 startup transformer is the backup offsite power supply and the alternate AC source for our plant design. It requires manual action from the CR-3 control room to lineup this configuration. The limitation on its capacity when large loads are I
started is clearly annunciated in the control room and expeditious actions can be taken to alleviate the situation. Thus, the source availability is not significantly impeded.
These issues represent compliance and design concerns which warrant the attached actions. They do not compromise plant safety. The actions FPC has planned'for Refuel 7 will constitute significant improvements and the attached reviews will provide additional confidence that not only are the systems adequate but that significant margin is available and operator burden is lessened.
We look forward to discussing the attached plans with the staff and I are strongly committed to a cooperative effort at better understanding the CR-3 electrical design. We welcome staff input to assure mutual confidence is built by the results of these j reviews.
l-l Sincerely, 1
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l Rolf C. Widell, Director Nuclear Operations Site Support RCW/KRW/wla xc: Regional Administrator, Region II Senior Resident Inspector l
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Enclosure #1
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l L FLORIDA POWER CORPORATION L
ELECTRICAL SYSTEM
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DESIGN BASIS
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RECONSTITUTION EFFORT FOR
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CRYSTAL RIVER 3
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OCTOBER 20,1989 1 e
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ELECTRICAL SYSTEM DESIGN BASIS RECONSTITUTION t
- The following discussion provides an overview of the Design Basis Reconstitution effort for Crystal River 3. In addition, specifics are provided as to the expected scope to be encompassed by this effort.for the three primary Electrical Systems.
DESIGN BASIS RECONSTITUTION OVERVIEW The Design Basis Reconstitution effort at Florida Power Corporation is a comprehensive and thorough process directed by the Configuration Management Plan (CMP) dated September 7, 1988 (This '
plan was provided to the NRC at the NRC/FPC management meeting held ,
at Crystal River 3 on October 18, 1989.) This plan is the written >
document accepted by FPC management as the overall scope of work for the Nuclear configuration Management section of the Nuclear Operations Engineering and Projects Organization. Two of the seven programs in the CMP relate directly to the design basis reconstitution effort.
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Program No. II, " ENHANCED DESIGN BASIS DOCUMENT (EDBD) PROGRAM",
I describes the plan of action for developing Enhanced Design Basis l Documents. This program was developed based on INPO report ;
j " Recommendations on Design Basis Documentation in the Nuclear
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Utility Industry" and will address previously identified weaknesses of the existing CR-3 Design Basis Documents such as:
. incorrect / incomplete source reference documentation, i.e.,
doce.ments that contain the basis for design parameters
. lack of systems interface requirements identification
. lack of margins identification
. referenced calculations not verified / checked The resultant EDBD will integrate the CR-3 design requirements and design related licensing commitments into a single document for each identified system and will include appropriate design basis information to support both Safety and Key Operational functions (see attachment 1 for sample EDBD) . The EDBD Program has been designed to produce a user-oriented document while achieving the following objectives.
. Provide an effective and reliable source of design basis information.
. Ensure the accuracy, reliability, consistency, and credibility of the available CR-3 calculations used as references in the EDBD's.
. Ensure the availability of documentation to support (document the basis for) parameters identified in the EDBD's.
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. Provide assurance that the design related licensing co.mmitments are reflected in the EDBD. '
. ' Ensure that key engineering requirements and assumptions critical to plant safety are identified in the EDBD.
4 The process for implementing the EDBD Program is described in detail in the Configuration Management EDBD Plan revised 9/20/89.
(The plan has recently been revised to incorporate enhancements l based on the two pilot EDBD's developed earlier this year.) The -i process for developing an EDBD is very methodical and extensive and can be summarized as follows: ,
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- 1. Develoo System Loaic Tree Diaarams (see attachment 2 for samole Loaic Tree) . The Logic Trees are the first stage in j the development of the EDBD's. They are developed to outline ;
-(in an easy to understand visual format) the legal j E requirements, safety functions, implied system parameters, and l component functional requirements for the system. This is accomplished by reviewing in-depth system specific documents )
! and identifying the safety requirements and the key parameters !
and components which are necessary for the system to achieve j its design safety function. J l 2. Identify. Retrieve, and Cataloc Potential EDBD Inout Sourceg. l l The existing CR-3 Design Basis Documents and FPC files, SEEK j
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system, microfiche, etc. are reviewed to identify sources of information which will support the EDBD development. These L sources are also input into a PC-based relational database ,
l program to provide better traceability and accessibility ;
l during the EDBD development. Additional sources identified l after this initial review are also input into this program for !
l future reference. The following types of documents are considered for review for identifying input sources.
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NSSS/A-E Design Criteria, Standards, Specifications, and Design Reports
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Drawings
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Procurement Documents
- 3. Inout Source Document Review. All documents identified as potential input sources are reviewed to determine their contribution to the EDBD. A form "EDBD Source Data Sheet" is completed to document its applicability and to further characterize the contents of the document into design basis topics. I
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- 4. EDBD Prenaration. Utilizing the Logic Trees and information i
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from the applicable source documents, the EDBD is prepared in draft form. Two guidance documents, " Format and Content i Guidelines" and " Writers Guide", which are part of the EDBD l
- Plan are used to develop the EDBD. This ensures that all the I appropriate topics, are addressed and provides for consistency j
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in the presentation of the information.
- 5. EDBD Review. 'In addition to the typical design control review performed by the EDBD contractor organization, the EDBD draft i receives a review by the FPC System Engineering group as a minimum and others as deemed necessary.
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- 6. Problem Identification. As with any process for which design information is being retrieved, reviewed, and dispositioned, I there is potential for problems that cannot be readily resolved. These types of problems are identified during the EDBD development as an Open Item Report. Problems that imply )
a potential safety concern or are suspected design basis i issues will be handled in accordance with FPC Nuclear Operations Department Procedure NOD-17, " Design Basis Issues '
Resolution".
- 7. EDBD Final Issuance and Control. After all comments to the draft EDBD are reconciled, a " final" document is approved. ,
The EDBD is distributed into the Design Basis Document manual replacing the existing Design Basis Document for the respective system. The manual is a controlled document which is distributed to various individuals / departments throughout
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Nuclear- Operations including Enginecring, Operations, l
Licensing, Training, and Quality Programs. Maintenance of the
- L Design Basis Document is controlled by Nuclear Engineering Procedure NEP-216, " Design Basis Document".
The systems included within the present scope of the EDBD Program were selected based upon their safety classification, importance to safety, the FPC PRA model, and interviews with operations personnel. Thirty-seven systems have been identified and are scheduled to be developed as shown on the EDBD systems schedule (see attachment 3). To date, the two pilot systems (Main Steam and Decay Heat Removal) have been completed and issued, and the second group of systems (Core Flood, Emergency Feedwater/EFIC, Reactor Coolant, and Makeup & Purification) is under development with an earlier than expected completion of January 1990. In addition, the three primary electrical systems (AC Power, DC Power, and Emergency Diesel Generator) were authorized for an early start, and completion is expected for these systems by March 1990. The schedule as shown on the attached chart is intended to be a baseline for budgeting and manpower planning. It should be noted that the schedule and/or sequence may change to accommodate or coordinate with other activities as was the case with the electrical systems.
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1 The second program in the Configuration Management Plan that relates directly to the design basis reconstitution effort is Program No. III, "EDBD FIELD VALIDATION PROGRAM". This program is intended to validate that the plant actually conforms to the EDBD and its source documents. The program was essentially modeled
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after the NRC "SSFI" technique. The following . objectives are expected to be achieved as a result of this program.
. Systems are capable of performing the safety functions q required by their design baties.
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. Testing is adequate to demonstrate that the systems are I capable of performing their safety functions, l
.. Ensure agreement between FSAR, Tech Specs, Procedures, EDBD's,
. Operator and maintenance technician training is adequate to e ensure proper operations and maintenance of the system.
. Human. factors considerations relating to the selected systems (e.g., accessibility and labeling of valves) and the systems
(' supporting procedures are adequate to ensure proper system i operation under normal and accident conditions.
The Field Validation effort is performed by a dedicated team of individuals located at the plant site. After an EDBD is completed, the Field Validation team systematically breaks the document down
'into sections. The system and component parameters are listed individually on a form " PARAMETER VALIDATION SHEET" which must be
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completed to document validation of the parameter. During the validation, walkdowns are performed, discussions with plant personnel are held, and plant procedures and drawings are compared 3 to the as-built plant. In addition, the source documents (references) are validated on a " REFERENCE VALIDATION SHEET".
l Discrepancies found as a result of the validation effort are I
recorded on a Validation Problem Report (VPR) and referred to the
. FPC supervisor for disposition. Discrepancies that appear to be I
significant and represent a suspected design basis issue are handled in accordance with Nuclear Operations Department procedure NOD-17, " Design Basis Issues Resolution". The schedule for the Field Validation is simply to follow the completion of EDBD itself.
The validations for the two pilot systems are presently underway with completion expected by December 1989.
ELECTRICAL SYSTEMS SPECIFICS l As a result of the recent discoveries of several problems in the i electrical area, FPC believes it is prudent to accelerate the
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schedule for the design basis reconstitution for the Electrical Systems. The above described programs (EDBD Development and Field
. Validation) will be applied to the AC Power, DC Power, and l Emergency Diesel Generators systems on a priority basis. In l
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- d addition, a comprehensive Electrical Calculation Enhancement effort will be performed as described in Enclosure 2, " Electrical Calculation Enhancement Program". The scope of equipment and L components expected to be addressed by the EDBD effort is l
l AC Power l' 230KV Substation CR-3 Startup Transformer CR-1&2 Startup Transformer 4160V Non-segregated Phase Bus Duct 4160V and 480V Switchgear Including Breaker
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Control and Protective Relaying 480V Motor Control Centers AC Distribution Panels 120V Vital AC Power and Control Cable
! Cable Raceway and Separation 1
Electrical Penetration Assemblies l' DC Power Batteries L Battery Chargers
[' DC Ground Detection Disconnect Switches and Bus Duct DC Distribution Panels Emeraency Diesel Generators
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Diesel Engine Electric Generator Fuel Oil Transfer Controls l
i Jacket Coolant Loading Air Cooler Load Shedding -
L Lube Oil Generator Protection '
l Compressed Starting Air Engine Exhaust ELECTRICAL SYSTEMS EDBD SCHEDULES As mentioned above, the EDBD effort for the Electrical Systems were authorized for an early start. These efforts were initiated as of October 7, 1989 (original schedule had 11/90 start for Emergency L Diesel Generators and 7/91 start for AC and DC power). The Logic Tree phase of the effort is presently under development with completion expected in December 1989. The Logic Trees will provide a better definition for the full scope of equipment necessary to be addressed as part of the EDBD. The final EDBD's for these systems are expected to be completed and issued in March 1990. The respective Field Validation efforts will then begin with the last l system to be completed by October 1990.
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SUMMARY
In' summary, FPC believes the Configuration Management efforts (EDBD
. development, EDBD Field Validations, and- Electrical Calculation
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Enhancements) will baseline the electrical systems design bases and i
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provide the appropriate information' for proper operation,
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maintenance, and design control related to these' systems.
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FLORIDA POWER CORPORATION
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ELECTRICAL CALCULATION u
ENHANCEMENT PROGRAM l
l OCTOBER 20, 1989
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SUMMARY
FPC is initiating an' Electrical Calculation (EC) Enhancement Program for the purpose of identifying and implementing specific activities which will ensure
- the continued design adequacy and regulatory compliance over the life of the Plant. This effort is an extension of the Configuration Management Program described in Enclosure #1.
I When Crystal River #3 was designed the traditional electrical calculations were done by hand to sunort the procurement of the electrical equipment. Small loads were grouped together to facilitate the calculations. Revisions to the plant normally impacts the groups which by themselves do not impact the accuracy of the calculations. Major up-dates were done as required.
FPC is actively involved in such programs as Safety Performance Improvement Program (SPIP) and Technical Specification Improvement Program. FPC has also improved our Design Review, Root Cause Analysis, Vendor Information, Operating Experience Review and related processes. During these activities FPC has found cases of electrical calculations containing errors. The types of errors are:
. Calculations not in enough detail
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. Incorrect assumptions '
. Incorrect equipment timing 41
. Error in Power Factor The Enhancement Program will revalidate the design activities performed in support of the CR3 AC and DC Distribution System. This program will also pull together the various revalidation activities that have been performed to-date and will be performed during Refuel VII on Emergency Diesel Generator. FPC will utilize state-of-the-art computer software to configure and model AC and DC distribution systems which will enable CR3 to perform on-line Short Circuit, Voltage Drop and Load Flow Analyses.
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' DETAILED DESCRIPTION 0F THE EC EM4ANCEMENT PROGRAN t-FPC is assigning this' program to key personnel in the Engineering Staff with strong support by our Licensing Group, Protective Relay Department, and contract support. An organizational chart of the program is attached.
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l.ICENSING FPC will perform an in-depth review against all Crystal River #3 Licensing documents, NRC Generic Letters, Bulletins, Notices. This effort will assure that the - CR3 Electrical Distribution Systems reflect and comply with ' the CR3
!. Regulatory Requirements. l AG <
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1 FPC will configure the Crystal River #3 AC Electrical System on a Personal
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Computer dedicated in the Electrical area for this program implementation. The following calculations / activities will be performed on this machine: _
. Data Base of "as installed" data: j
. Nameplate data of motors, transformers, will be read in the field. .
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. Manufacturers rating of relays, cables, inverters, and panel boards will be developed.
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. Field validation of protective devices installed configuration. l
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. The length of each power circuit taken from the marker tapes j when the cables were installed, will be documented. )
. Short Circuit Calculations to ANSI C37.010 to the following levels will be performed, (see Attachment #1):
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. 4160 Volt Buses
. 6900 Volt Buses b '
. 480 Volt Switchgear Buses
. 480' Volt Motor Control Centers
. 480 Volt Motors
. 120 Volt Breaker Panels
. Voltage Drop Calculations to the following levels will be performed, (see Attachnent #2):
. 4160 Volt Buses
.- 6900 Volt Buses e 480 Volt Switchgear Buses
. 480 Volt Motor Control Centers
. 480 Volt Motors
. 120 Volt Motor Control Circuits .
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. Load Flow Calculations to the following levels will be performed, _ .
(see Attachment #2)
. 4160 Volt Buses
. 6900 Volt Buses e 480 Volt Switchgear Buses
. 480 Volt Motor Control Centers
. 480 Volt Motors
. 120 Volt Breaker Panel (Primary side of transformer)
Please note that Attachments 1 and 2 are Preliminary. The Attachments represent loads in " Typical" format. It is FPC's intent to analyze all ;
loads on a given bus, except for some non-safety related loads which will be lumped in groups.
Also included in the program will be a review of all power cables to insure their selection for current carrying capabilities is correct. The voltage drop within 3
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2 the control circuits of motor control circuits will also be reviewed. This-is (g . especially important'since each Motor Control Center control circuit has its own control transformer providing an additional impedance. This effort will be done by models that bound groups of circuits and individual circuits as needed.
The major AC Electrical Components will also be certified to insure their size and rating is proper. This includes:
Start-Up Transformer Non-Segregated Bus Duct Switchgear.
Reactors Inverters The main distribut' ion system provides power for the safety related and non-safety related loads. 'Therefore, both are included in the scope of this' work as -
- necessary to support the safety related equipment. Specific activities that can
- be segregated'into safety vs. non-safety and do not impact the safety related -
. equipment are not being committed to. An example of this is a control circuit of a non-safety related motor operated valve.
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FPC will use computer technology to support the calculation / activities to be 1
- 1 I performed as part of the DC portion of the enhancement. i
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A data base for DC equipment will be developed similar to that described in the
, AC section.
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. Nameplate data of motors, chargers, will be read in the field. ,
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. Manufacturers ratings of relays, cables, panel boards, and batteries will be developed from manufacturer data.
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e Field validation of protective devices installed configuration.
. The length of each power circuit taken from the marker tapes when the cables were installed will be documented.
A short circuit analysis will be done to establish the fault current on the downstream side of all protective devices. This will be done at the 250 volt and 125 volt level. (see Attachment #3) j A voltage drop analysis will also be performed to all safety related equipment.
This includes fuse panels, motors, motor control circuits. (seeAttachment#4)- j A load flow analysis will be done to the same level as the voltage drop analysis.
1 Please note that Attachments 3 and 4 are Preliminarv. The Attachments represent loads in " Typical" format. It is FPC's intent to analyze all loads on a given I panel, except for some non-safety related loads which will be lumped in groups. l l
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Also included in the program will be a review of all power cab 1es to insure their selection for current carrying capabilities is correct. '
The major DC components will also be verified to insure their size and rating are proper. This includes:
Batteries Battery Chargers Each battery will be analyzed to determine all the equipment that will operate and their operating times for a loss of offsite power and no diesel generator.
This analysis will be for a duration of two hours. With this analysis a discharge profile will be developed for each battery half (125VDC) and the resulting voltage.
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L This analysis will be performed with the new safety related batteries being installed during Refuel VII. FPC has scheduled a project to add a non safety N related battery to the plant. This will allow the large non-safety related loads to be removed from the existing safety related batteries. The computer model of the CR3 DC distribution system will be utilized to size the new non safety related batteries which are scheduled for installation prior to Refuel VIII.
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The computer model will also enable FPC to calculate the discharge profiles based on the loads left on the existing safety related batteries. The DC coping capability required by the FPC station blackout assessment will be reevaluated to reflect the new safety related and new non-safety related batteries. l G90RDINATION The AC and DC protective devices used at Crystal River #3, will be reviewed to insure they are rated for the intended service. This includes continuous and fault. conditions. This coordination will be done for all safety related
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equipment and non-safety related equipment that impacts safety related equipment.
The protective devices associated with the 230KV substation, start-up transformer, 4160 volt level and 6900 volt level will be evaluated by the Florida Power Relay Department.
The protective devices associated with the 480 volt switchgear will be reviewed including coordination curves.
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Breakers and fuses used at the 480V Motor Control Center, 120VAC Vital Bus Panels,125VDC, 250VDC will be individually verified.
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EMERGENCY DIESEL GENERAT9RS (EDG)
The Diesel Generator has received rigorous analysis within the last two years.
The analyses have been maintained and will be updated with modifications that effect it due to MARS being installed during Refuel VII. The revalidation activities performed to date and those planned for Refuel VII were reviewed with the NRC staff during our meeting held on 8/31/89. This program will pull together these activities and will evaluate the results of EDG revalidation against the output of above described program. No other analysis is being considered.
FIELD TEST FPC will use test data when it is available to support the calculations.
Also some instrumentation will be added to gather additional field data as necessary to support the project. l SCHEDULE ,
The attached schedule is based on FPC's preliminary assessment of the project scope. This schedule assumes that FPC will be able to procure an acceptable software program to model the AC and DC systems at CR3. If FPC must develop the software in-house, the completion date of the project may be impacted. FPC will '
keep the staff informed of this critical milestone as well as our progress on the entire program.
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ELECTRICAL CALCULATION DHWICEMENT PROGRAM ;
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PROJECT MANAGER
' ENGINEER
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i FPC FPC
- LICENSING NUCLEAR CONTRACTOR (S) CONfRACTOR(S)
ENGINEERING l
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ESTABLISH THE CR3 . SELECT SOFTWARE . PROTECTIVE RELAY DC ACTIVITIES ELECTRICAL REGULATORY . DEVELOP DATA BASE CALCULATIONS & . SHORT CIRCUIT REQUIREMENTS . AC CALCULATION CURVES & SETTINGS . VOLTAGE DROP 4
. SHORT CIRCUIT (480V & LOWER) . LOAD FLOW
. VOLTAGE DROP . CABLE AMPACITY
- . LOAD FLOW . VERIFY PROTECTIVE i RELAY SETTING (4160V .
. VERIFY PROTECTIVE AND HIGHER) l RELAY SETTING (480V l AND LOWER)
! . OL LOAD RELAY
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. VERIFY CABLE AMPACITIES l FPC/ CONTRACTOR (S) FPC FPC
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SUPPORT CONFIGURATION MANAGEMENT RELAY DEPARTMENT
- . GATHER FIELD DATA . INTERFACE . PROTECTIVE RELAY CALCULATIONS,
- CURVES, SETTING (4160V & HIGHER)~
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ELECTRICAL CALCULATION ENHANCEMENT PROGRAM ,._..
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- ACTIVITY 1989 . 1990
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START PROJECT & ASSIGN WORK' X X f REVIEW AND ESTA.BL!SH _ _ __ ._ ,_; . _ .
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SELECT SOFTWARE'AC ~ ~ ~
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BUY AND RECEIVE ._.
X .X , X _
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- GATHER ALL FIELD DATA - AC & DC X X ~
X . _ .X ._X-X X I
GATHER AL'L DESIGN DATA - AC & DC ~ X' X X X X X' ~X~X X ~ ~
VALIDATE PROGRAMS X X LOAD DATA BASE X' X ~ X X ~ ~ X ~ X [X 1
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EPUT COMPONENT DATA'INTO MODEL X X ~ X X X ' X'~~X '.
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PERFORM SHORT CIRCUIT ANdLYSIS ~~ ~ X" X^ 'X
! PERFORM VOLTAGE DROP ANALYSIS _. .__ . XiX'[X PERFORM LOAD FLOW ANALYSIS ~
X X X ~
i POWER CABLE REVIEW ~ ~ ~
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CONTROL CIRCUIT VOLTAGE DROP X X REVIEW MAJOR AC COMPONENTS X X
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- INPUT COMPONENT DATA INTO MODEL' ~X ~~ X ~~ XIXX~ ~X:X ~ ~~
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l PERFORM SHORT CIRCUIT ANA' LYSIS' ~~~
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! PERFORM VOLTAGE' DROP' NALYSIS ~ ~
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j PERFORM LOAD FLOW ANALYSIS _ _ ._, 'X[X' ._ _ [
- POWER CABLE REVIEW . . _ _ . _ _ _ _ _
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CONTROL CIRCUIT VOLTAGE DROP. , . _ _ _
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l BATTERY PROFILES .
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REVIEW MAJOR.DC COMPONENTS ._ , _ _ _. _, , .X (_ X ..
REVIEW EXISTING _DC SYSTEM _ _ _ __ _ _
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SOFTWARE ADEQUACY _
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ELECTRICAL CALCULATION ENHANCEMENT PROGRAM ',
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j ACT!VITY :1989 .1990 ~ i1991
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~ COORDINATION . _ _ . _. ..
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RELAY. DEPARTMENT (4160V)_ X ~ X X;. _ . ._ ; . . i. ,_,.i. '
VERIFICATION (4160V) X.X-.X, . . _ . . . .
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'480V SWITCHG. EAR .
VERIFICATION (480V) .
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i 480V MCC ~~
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120V AC ' . X'[X . ~
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i 125/250V DC X X-s . _
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GATHER EXISTING DOCUMENTATION 'X' X X X ~~ ^ ~ ~ ~ ~
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UPDATE EDG DOCUMENTITION TO $ '
! INCLUDE REFUEL 7 MODS . X X X: .
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f COMPARE UPDATED EDG lNFORMdTION TO RESULTS OF AC & DC REVIEWS
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REPORT _
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