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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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Power CORPOR AT TON October 29,1985 3F1085-14 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Emergency Feedwater System Reliability
Dear Sir:
The purpose of this letter is to provide the NRC with a documented summary of programs and improvements involving the Emergency Feedwater (EFW) System for Crystal River Unit 3 (CR-3).
Florida Power Corporation (FPC) shares the concern and interest the NRC has in its current review of Emergency Feedwater Systems because of recent industry events. FPC has been very active in improving its own EFW system and wants to illustrate the improvements which have been made, the actions that have been planned, and discuss our own assessment of the reliability of the CR-3 EFW system.
It should be noted that in our analysis and evaluation of the EFW, we have also identified many other support or primary systems that we consider to have equal importance. PPC is reviewing main feedwater reliability history in order to preclude demands on EFW when main feedwater trips occur. Other support systems for assuring adequate core cooling include CR-3's ability to use the " feed
& bleed" method with great success. The use of high pressure injection pumps for feed and bleed cooling of the core has been successfully tested at the Once Through integral System (OTIS) facility and during our transient of February 26, 1980. PPC believes that this procedure provides a major increase in our core cooling ability.
Florida Power Corporation is dedicated and concerned. We are determined to provide the necessary safety system reliability to assure that the health and safety of the public are maintained. We believe our program for maintaining and enhancing the CR-3 EFW and associated systems is achieving this goal.
0511040200OgobO2 o PDR ADOCK O FDR F gl GEN ERAL OFFICE 3201 Thirty fourth Street South e P.O. Box 14042, St. Petersburg, Florida 33733 e 813-866 5151
m - -
' October 29,1985
< 3F1085 Page 2
. The'following is a brief synopsis of the background, modifications, maintenance practices, Owners Group activities, and recent analysis methods developed to enhance CR-3's EFW system.
. BACKGROUND The initial requirements for modifications to the EFW system were a direct result of NRC response to the accident at TMI and the subsequent publication of NUREG-0737.. In addition to the requirement for certain EFW hardware modifications,
. there was also a requirement for an EFW system reliability study. FPC's response was in the form of BAW-1584, " Auxiliary Feedwater System Reliability Analysis",
published in December 1979. This study used the data and assumptions set forth in NUREG-0611 and 0635. It is now obsolete due to the modifications which have
. been implemented at CR-3. In June 1981, B&W completed a new EFW reliability study for FPC. It was entitled "EFW System Upgrade Reliability Analysis for CR-3", and took into account committed modifications, the dominant one being the Emergency Feedwater Initiation and Control System (EFIC). The study used Industry-representative failure rates and actual human reliability analyses for key
. operator actions. This study was sent to NRC and reviewed by Brookhaven National Laboratories (BNL). BNL's review was essentially a re-analysis using the NUREG-0611 data and assumptions, allowing no credit for EFIC. FPC does not believe the BNL review reflects the true reliability of the CR-3 EFW system. As a result, an updated EPW reliability study is being performed in conjunction with the CR-3 Probabilistic Risk Assessment (PRA) project now underway at FPC.
EMERGENCY FEEDWATER/PRA RE-ANALYSIS The new EFW study utilizes plant-specific data and takes into account all of the modifications to the system. Preliminary results indicate an EFW system unreliability of 1.7 X 10-4 for a Loss of Main Feedwater event. The potential
> exists for improvement through increased attention to the reliability of the turbine-driven EFW pump. The study will be completed by November 30,1985.
PPC is currently in the final stages of a state-of-the-art Level 1 PRA. We have contacted Science Applications International Corporation (SAIC) to perform the analysis. SAIC has considerable PRA experience and has participated in several B&W plant'PRAs including the CR-3 IREP study. Motivation for this project was provided by a desire for a replacement for the outdated CR-3 IREP study and a recognition of the increased NRC emphasis on probabilistic analysis. The new CR-3 PRA utilizes plant-specific data gathered from six years of maintenance records.
PPC plans to use the PRA to evaluate the present CR-3 design and to analyze /prioritize proposed ' modifications. The PRA is expected to be completed by early 1986, and will also be used to determine the importance of the EFW system to the core melt frequency.
EMERGENCY FEEDWATER SYSTEM MODIFICATIONS
-Over the past several years, numerous modifications have been made to improve the reliability of the Emergency Feedwater System. The most significant of these t
am
- i p ,
I
. 1 IOctober 29,1985-i 3P1085 ' Page 3 L ' modifications was_ the instalia'tlon of a safety grade ' Emergency Feedwater Initiation and Control System. This system, required by NUREG-0737, Item II.E.1.1, cost over $10 million. Other modifications to the EFW System were made
~
i ;
to ' meet the requirements of 10 CFR 50, Appendix R. . System enhancements include removal of pump suction valve internals to prevent a single failure from isolating the water source, installation of a parallel steam isolation valve to the -
EPW pump turbine, addition of supports to assure selsmic adequacy, Installation of environmentally quallfled equipment, as necessary, to assure proper post accident
- performance, and locking open and lifting the leads of all AC operated valves to prevent spurious operation. During the next refueling outage, a dedicated EFW tank will be added which will be tornado and flood protected. This new tank will also_ have full safety grade redundant instrumentation. Special evaluations have been performed which assured no missile from the EFW turbine could jeopardize other necessary EFW system equipment. In all, the modifications and studies involved the expenditure of more than $16 million.. Attachment I describes the changes and modifications in more detall.
i EMERGENCY FEEDWATER SYSTEM MAINTENANCE IMPROVEMENT ;
The Crystal River Unit 3 EFW maintenance program has been enhanced to provide a high degree of assurance that the system will operate when required. In our efforts to enhance the' maintenance program, three different areas were evaluated; namely, equipment modification, maintenance programs (including inservice
~
inspections), and operational programs.
Equipment modifications were performed to improve the system reliability which l- included the addition of a parallel steam admission valve to the turbine driven EFW pump and the addition of steam traps and pipe restraints. The parallel valve was ,
, installed for single active component failure protection. The steam traps and high energy line pipe restraints'were installed to permit steam to be maintained to the steam. admission valve thus precluding a slug of condensate from causing an overspeed trip of the turbine driven EPW pump. A modification was also made to the turbine driven EFW pump to provide pump bearing cooling from a stage of the pump discharge thereby providing simpilfled maintenance and deleting the dependence for cooling water from another system. A new type insulation (remap) j is now being used so that its removal requires less time. +
' The preventative maintenance program was enhanced to improve reliability by
'several means. An oil analysis / change program for the emergency feedwater pump ,
turbine governor was implemented as a result of past governor problems. This ,
program has resulted in improved governor reliability. The Plant Maintenance l Department has established a maintenance history from work requests for trending-L purposes.- Specialists are utilized to perform monthly vibration checks on both the motor driven and turbine driven emergency feedwater pumps. Specialists are also utilized to perform periodic infrared scans of the switchgear to locate hot t
i
s V .:
October 29 3F1085-14 Page 4 spots and/or loose connections. A surveillance is performed monthly to monitor the. flow characteristics of the EFW pumps and to demonstrate the operability of the EFW system. The motor operated valve analysis and testing system (MOVATS)
.is used periodically to test the limit switch operation and measure the torque on
' the torque switches for all motor operated valves in the EFW system. Inservice Inspections, are performed in accordance with the applicable code requirements except where specific exemptions were granted.
CR-3 plant policy states that-specific equipment requiring maintenance, which
' includes the EFW equipment, must be worked around-the-clock, seven days a week
.until the system is restored to operable status.
~ OWNERS GROUP ACTIVITIES FPC, along with the other members of the B&W Owners Group, is aggressively participating in the study and analysis of the June 9,1985 transient at the Davis Besse Nuclear Power Plant. An Owners Group Task Force was formed to review
.the Davis-Besse course of action and determine which corrective actions should be generic to all B&W plants. This review resulted in a number of specific action items to be evaluated and reported on by each plant. The Task Force will review
' these reports to determine what further actions should be taken.
Another subcommittee of the Owners Group is reviewing reactor trips at B&W plants to determine actions that can be taken to reduce the reactor trip frequency.
' The Main Feedwater System is receiving a large portion of the subcommittee's attention since it has contributed to such a large portion of the reactor trips in the past. Improvements in the Main Feedwater System could significantly reduce the number of challenges to the Emergency Feedwater System as well as improve plant availability.
PPC also has an internal trip reduction task force which has reviewed Main Feedwater System operation. This task force has reviewed the INPO Good Practice for trip reduction and assured that FPC complies wherever possible. The task force has also made several recommendations for plant modifications and o reviewed other modifications to assess trip potential.
CONCLUSION Based on the information presented, Florida Power Corporation firmly believes the enhancements performed and the work under way are providing us with a highly reliable EFW system.
I c FPC has installed systems that can automatically start and control our EFW system yet prevent over-cooling. FPC has reduced failure possibilities by removing valve i Internah; increasing preventative and predictive maintenance; providing an intensive monitoring program including MOVATS, infrared scanning, vibration and lube oil monitoring; and by performing frequent functional testing.
i
t October 29,1985
.3F1085-14 c Page 5 J
As indicated by our PRA and analytical study of the CR-3 EFW system, the reliability of the system is high and provides adequate assurance that a core melt will not occur. The ability to perform feed and bleed as a backup to our EFW system is an added benefit that requires consideration.
Our management has been heavily involved in assuring we continue to improve our-EFW system reliability and we have worked closely with the NRC In developing those enhancements that will best benefit our EFW system.
Our goals include continued evaluation and irnprovements in not only the EFW system but also in other support or companion systems, such as the Main Feedwater System. Our work with the other B&W owners is escalating on these efforts and should provide even higher plant reliability in the future. Please _ review the progress we have made and provide us with your comments.
Sincerely,
)J=
W. S. WI Vice Prpsident Nuclear Operations GRW/feb Attachment
y
-Non Safety Related
-Seismic Piping Design
-Electrical Circuits and Components not seismically designed B. SOURCES OF REQUIREMENTS
- 1. NUREG-0737 (TMI LESSONS LEARNED) 10/31/80
-Item II.E.1.1 (EFW System Evaluation / Reliability Study)
-Item II.E.1.2 (EFIC)
- 2. Generic Letter 81-14 (Seismic Review) 2/10/81
- 3. IREP (CR-3 Safety Study)
- 4. Interfaces
-Fire Protection Program 10CFR50 Appendix "R"
-Equipment Qualification Program 10CFR50.49 C. COMPLETED PROJECTS
- 1. EFIC
Description:
Emergency Feedwater System Automatit Initiation and Flow Control. This was a complete new EFW Initiation and Control system fully safety grade. The new system includes additional transient mitigation features such as Feed Only Good Generator and Automatic Flow Rate Control.
Completed: Refuel V Cost: $10,010,000
- 2. CDV-103,-104 Modifications
Description:
Remove valve internals to prevent single failure from isolating EFW Pump Suction from water source (Condensate Storage Tank) disabling the EFW system.
Completed: Ref uel V Cost: $15,000
- 3. ASV-204 (ASV-5 Bypass)
Description:
Install redundant steam admission valve for EFPT-1. Assure single failure will not prevent operation of Steam Driven EFW Pump.
Completed: Refuel V Cost: $300,000
- 4. Seismic Qualification
Description:
Perform analyses and install required piping and electrical supports. To assure EFW system will remain operational through and following a seismic event.
Completed: Refuel V Cost: $400,000
- 5. EFTB-1 Missile Evaluation
Description:
Evaluation performed to assure missiles generated as a result of a catastrophic failure of the steam driven pump turbine would not damage equipment necessary for the EFW System to function with the motor driven pump. No modification was required.
Completed: August 1984 Cost: $1000
- 6. Motor Operated Valves
Description:
All AC operated EFW Valves have been locked open and determinated to prevent short circuit spurious valve operation during a seismic event. Valves were powered from non seismic, non safety related Motor Control Centers. Spurious operation could disable EFW system.
Ref: EFIC
- 7. Appendix "R" Upgrade
Description:
Evaluate and upgrade EFW circuits to meet Appendix "R" criteria by rerouting or wrapping. Fully integrate EFIC with Appendix "R" upgrade.
Cost: $2,000,000
- 8. Environmental Qualification of Equipment
Description:
Identify and evaluate all EFW equipment located in a harsh environment. Provide detailed qualification records for existing equipment or replace the equipment to meet the EQ requirements. Full consideration of EQ requirements for EFIC design.
Cost: $250,000
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9.' : Technical Specification Revision
Description:
- A full flow test of the EFW system is performed following cold shutdowns.
D. ' ACTIVE PROJECTS -
.l. Dedicated EFW Tank -
Description:
Provide a tornado and flood protected EFW system water source. Current primary water source is not tornado or flood protected and does not have full safety grade instrumentation.
Schedule: Refuel VI Completion Cost: $2,900,000
- 2. Class 1-E Level Instrumentation -
Description:
Provide safety grade level instrumentation for new tank.
Cost: Included in tank cost.
3 Reliability Analysis (PRA)-
Description:
Provide a model to evaluate system reliability Schedule: November 1985 Completion
- Cost: $300,000 E.
SUMMARY
Total approximate cost: $16,176,000
