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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
[Table view] |
Text
eso o 6o h"ee a m 80 t . 'QOs
Florida Power C O R P O R A T IO N October 11, 1979 File: 3-0-3-a-3 Mr. Robert W. Reid Chief Operating Reactors Branch #4 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72
Dear Mr. Reid:
On October 2,1979, Florida Power Corporation responded to yor.c letter of September 19, 1979 concerning the upgrade of the anticipacory reactor trips on turbine trip or loss of main feedwater at Crystal River Unit 3.
Enc'osed is a copy of the B&W report entitled " Anticipatory Trip Functions for 177 FA Plants." This report is being submitted by Florida Power Corporation as additional information to our response to Item 9.a.
contained in our October 2, 1979 letter.
If you have any questions concerning our response, please contact us.
Very truly yours, FLOR A POWER f CORPORATION (bhe
. . oore Assistant Vice Prosident Power Production}
GCMhowR01 V
7910180 V' General Office 3201 Thirty-fourtn street soutn . P O Box 14042. St Petersburg Florda 33733 813 - 866-5151
STATE OF FLORIDA COUNTY OF PINELLAS G. C. Moore states that he is the Assistant Vice President, Power Production, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.
*/
O/)/ p Q
( '{ Y LAk G. C. Moore Subscribed anci sworn to before me, a Notary Public in and for the State and County above named, this lith day of October, 1979.
Notary Public Notary Public, State of Florida at Large, My Commission Expires: August 8, 1983 117 8 ~)23 CameronNotary 3(D12)
t ANTICIPATORY TRIP FUNCTIONS FOR 177 FA ILANTS
- 8. 1102525-00 Doctu: lent Identification
?f Prepared by '3'll bl I 7f Reviewed by !/d2 $
Approved by ; -
,, , f /, 7
/- ,
1178 124
, 86-1102525 -L; INDEX
1.0 INTRODUCTION
2.0 ASSESSMENT OF POSSIBLE ANIICIPATORY TRIPS 3.0 FUNCTIONAL ANALYSIS
4.0 CONCLUSION
S AND
SUMMARY
APPEVDIX A: LOSS OF ONh, FEEDPUMP ANALYSIS 1178 125
t 86-1102525-00 l.0 INTRODUCTION For the purposes of this report, an anticipatory trip is defined as a trip functicn that would sense the start of a loss of OTSG h at sink and actuate much earlier than presently installed reactor trip signals. Possible anticipatory trip signals indicative of changer in OTSG heat removal are: turbine trip, loss of main feedwater, low steam generator level, and low pressurizer level.
This report evaluates the effectiveness of anticipatory trips compared to the axisting high RC pressure trip for a LOFW. Qualitative and quantitative arguments are presented waich support elimination of the level trips in the pressurizer and steam generators from final design considerations of anticipatory trips.
Functional response is presented in terms of a parametric study of time to trip. Thus, irrespece.ive of the plant specific trip signale and actuat *on time, the hardware design can proceed with greater flexibility.
That is, by presentfng system parameters, such as pressurizer fill time, as a function cf time to trip, then if one plant's turbine trip signal occurs 2.1 secs after initiation of the event and another plant's trip signal occurs at 2.5 secs, this study will still be applicable to both.
Some of the results presented in this report have already veen sub-mitted to the NRC in Reference 1, the balance of the informat'an will b2 submitted by May 21, 1979. The analyses are performed with the revised setpoints, i.e., high RC pressure trip at 2300 psig and PORV setpoint at 2450 psig. It is shown that anticipatory trips provide additional margin between the peak RC pressure af ter the reactor trip and _ the PORV setpoint, but provide little additional margin in the longer term re-pressurization to the PORV setpoint with continued delay of auxiliary feedwater initiation. }}[h ))h
36-1102525-00 2.0 ASSESSMENT OF POSSIBLE ANTICIPATORf TRIPS in accordence with Directive 79-05B, an evaluation for design basis for anticipatory trips on turbine trip, loss of main feedwater, and low steam generator level has been completed. One of the trip functions investigate 6 was determined not to be anticipatory as discussed below:
Low steam generator level has not been recommended as an anticipatory trip function.
Figure 2-1 shows the OTSG start-up level from site data and the CADDS calculated OTSG mass inventory as functions of time following the TMI-2 event. The time of reactor trip on high RC pressure is noted on the figure and clearly demonstrates that a steam generator level trip would not have been anticipatory for a level setpoint that would not interfere with normal operations and maneuvers. The initial rapid fall in OTSG' level occurs as the turbine stop valves close, momentarily stopping steam flow out of the generators.
The mass inventory increases during this period due to the loss of flow friction AP. By the time the reactor trip occurs, at 8 seconds, steam flow is re-established through the bypass syste=, flow friction dF re-estab-11shes the level and both mass and measured level start to decrease uniformly.
An OTSG level trip set to trip on the initial drop shown in Figure 2-1 would need to be set restrictively high for normal plant maneuvers and/or lower power levels.
)}fh ]2!
86-1102525-00 Further ' level information (in terms of mass inventoryi ts given in the figures for the analysis in Section 3.0. The results Lur thoce cases also indicate that the steam generator low level trip function would not be suff Siently fast to be considered anticipatory.
Anticipatory trips for loss of feedvater and turbine trip can be designed to trip the reactor in a more expedient manner than the high RC pressure trip for some overheating transients. An anticipatory trip will provide more margin to PORV setpoint during the initial overpressurization retulting from loss of feedwater and/or turbine trip. These trips will provide slightly more time to PORV setpoint and pressurizer f ll for delayed auxiliary feedwater initia-tion conditions.
I178 J28
---_.__.___,_.,_m_. _ - - ~ .
_ ---m ---__mm...,-
86-1102525-00 Figure 2-1 LOFW (THi-2 EVENT) 2.0 -
i i i i 160 TRIP DN HIGH RC 1.6 r PRESSURE
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---~ TOTAL S/G MASS, CAODS
-- START-UP LEVEL, TMI-2 SITE DATA
*~"*'~uu f.
(t j 3.0 FUNCTIONAL ANALYSIS P L a.i ( u w ..
A series of LOFW evaluations was performed at 100% full power (2772 MWt) with a reactor ; rip assumed on an anticipatory signal. With the new high RC pressure setpoint of 2300 psig, a reactor trip would be expected at about 8 seconds after the LOFW. The anticipatory trip study considered reactor trips with 0.4 sec,2.5 sec, and 5 sec delays from time zero. These studies also in-cluded sensitivities to AFW failure and reactor coolant pump coastdown.
The anticipatory trip study modeled a generic 177 FA plant, and is con-sidered applicable to raised or lowered loop designs. A feedwater coastdown similar to that estimated to have occurred at the March 28th TMI-2 event was used to generate separate heat demands for each CADDS analysis. The heat demands will change as the reactor trip time is delayed, because the additional heat input will boil of f the fixed steam generator inventory at dif ferent rates.
For the casez vhere AFW flow was modeled,1000 gpm was assumed, starting at 40 seconds. With proper steam generator level and pressure control, the system parameters will begin to stabilize at 195-290 seconds, depending on trip delay time and RCP operation; see Table 3-1 and Figure 3-12. The PORV will not be actuated, nor would the pressurizer fill or empty.
1178 230 With the assumption of no AFW, the PORV will be actuated about three minutes into the event, as a result of system swell; the pressurizer fills as 10-12 minutes (see Table 3-1). A delay of reactor trip of 2-3 seconds is seen to reduce PORV time to actuate by about one minute, and pressurizer fill by about 2 minutes For PORV setpoints other than 2450 psig, the times will vary and can be determined from Figures 3-3, 3-4, 3-8, and 3-10.
In each of these cases, the mass addition and cooling effect of expected make-up system operation is not modeled. One make-up pump running will add about 10 inches per minute to pressurizer level, and %1/2% heat demand. It should be noted that the May 7 report used a heat demand which reproduced the TMI-2 LOFW event; it has been reported by the operator that two make-up pumps were running from 13 see into the event, creating a higher heat demand than i
. 86-1102525-00 the anticipatory trip studies of the report assume. This it, shown in Figure 3-12.
The steam generator heat demands, reactor power, RC system pressure, pressurizer level, and RC inlet / outlet temperatures are given in Figures 3-1 through 3-5 for the trip at time zero case and Figures 3-7 through 3-11 tor the trip on high RC pressure (t=8 secs) case. The effects of delayed auxiliary feedwater initiation are also shown on the high RC pressure trip Curves.
1178 )31
86-11025:'5-00 TABLE 3-1 LOFW EVENT (LOFW at T=0 see)
TIME OF REACTOR REACTOR AUXILIARY PORV PRESSURIZER S/G Lvl CONTRCL TRIP (" DELAY") COOLANT PUMPS FEEDWATER OPERATES FULL (400") (P stm =1025 psig) 0.4 Run at 40 see - -
195 see 2.5 Run at 40 see - -
225 see
-3. 0 Run at 40 sec - -
275 sec 0.4 Run None 235 sec 790 sec -
2.5 Run None 180 sec 685 see -
5.0 Run None 140 sec 575 see -
0.4 Coastdown at 40 see - -
255 0.4 Coastdown None 190 sec 700 see -
LOFW EVENT - TIME =0 see REACTOR TRIP AT 2300 PSIG TIME OF TRIP ..CF AFW PORV PRESS. FULL S/G LEVEL CONT.
8.0 Run at 40 see - -
260 sec 8.0 Run None 175 sec 620 sec -
) \ 18 ')52
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'i, A.
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t; co ,
g i I ,I i N O '
500 600 200 300 400 [
u 10O c,
5 M M M P M M
] G M 9]_._.
Figure 3-5 Reactor Trip at T-0. No AFW I I I i 4 660 -
w
~
= 640 -
3
~
~
fU
{ 626 -
e _
w"
, + =
- 606 - - ~
_= _
.E - -
S 580 GUTLET -
; s' ~
c -
560 t%\
. ./ -
e
/ -
a y-540 -
1 L INLET -
520 -
y g
O N 500 I I I m i i O ts 100 200 300 400 500 600 Y O
%J O
u Time, s N
a y k- .- ~
. . . .p.
. , e- 1 9 _,
f -
- . - . ~ . . . .
. a c..., ; . . . .. . . . . 4 .
um u. ; e + .
. .t . . .
t w.2 <a t_.._.
N-- $5Y--=$, $k FCAaga._ b5$_.: , s$ . . . . .. ray.a$hn talb $2$ bk._bb;u)$hLu.g t~$ 1 tb. a[. b $.) Id Figure 3-6 Steam Generator Heat Demand Vs Time Following Loss of Main Feedwater From Rated Fower E 1.0 40 S AFW GELAY 2
E .8 .
%- .6 -
E AFW , AFE LEVEL
'4 -
5 INITIAT;dN
.2 -
[ CONTROL 0 L 120 S AFW OELAY p 1.0 ,
E '.8 -
8
.6 -
= AFW AFW LEVEL g .4 -
INITIATION CONTROL g .2 -
) '
/
E a
1.0 -
INFINITE AFW OELAY =
a
.6 T
- - .6 v -
g o
N 2 O co c .4 -
g 8 .2 -
5
, i e i t o u 0'0
~~
co 100 200 300 400 500 600 Time,'s
Figure 3-7 Total Power Vs Time Following Loss of Main Feedwater for Various AFW Initiation Times I I I I i 100 . _
80 - _
o
- I e
f 60 - _
E -
o.
~
40 - -
20 j i
i N
CO
- cm u_;
T U M w 100 200 300 400 500 600 g v.
Time, s U NOTE: POWER RESPONSES ARE THE a o
SAME FOR 40,120, AND INFINITE AFW DELAY TIMES 9 9 N " " " ~ " m m ro m & p q 7- & -
b s e l Figure 3-8 RC System Pressure */s Time Following Loso of Main Feedwater From Rated Power 2600 I I I I I
L KEY 2400 --
E ,- 40 S. AFW INITIATION DELAY
--- 120 S. AFN INITIATION DELAY g
INFINITE AFW INITIATION dei.AY -
U a
2200 'a \ _
\ .
5 g k
2000 )
\
\
r*k N <'
N
% ,e y- -
1800 -
ii e,
_. i N b u
I I I I I $
C) 1600 '
100 200 300 400 500 000 $
Time, s
Figure 3-9 Pressurizer Pressure Vs Time Following Loss of Main Feedwater " rom Rated Power 2000 _
I l I I I ]'
, 2400 -
., d ,
~
KEY g
_. 40 S. AF# INITIATION DELAY y --- 120 S. AFW INITIATION DELAY
{ 2200 INFINITE AFU INITIATION DELAY -
A -
% \
g 5 % ,#
$ \
;- 2000 ,- \
p-r
% ~\y/ s_-
1800 - -
s -
M N o, AT f v 1600 1 I I I I f 100 200 300 400 500 600 Time, s $
a f O M D'
-.., . .... _ _ <~ . .,.
_ .o . , .g rs. n. s e
u Jga I
bb b bd b b bn3 b b In,a) M .-. .
I f
i Figure 3-10 Pressurizer Level Vs Titae Following 1.oss of Hain Feedwater From Rated Power I i I f~ l KEY 40 S. AFN INITIATION DELAY
---- 120 S. AFW INITIATION DELAY 00 -
INFINITE ArW INITIATION DELAY d> 300 -
t
.~
$ r 3 200 - -
L. ~w
_ . , s%
100
_ w w _ - - ____ =
N 4 co O O
v I f I I __
Oi N 100 200 300 400 500 600 8 Time, s
Figure 3-11 Core Inlet and Outlet Temperature Vs Time Following Loss of Main Feedwater From Rated Power
~
l i I I KEY 40 S. AFW !NITI ATION DELAY
- - - - 120 S. AFW INITIATION DELAY INFINITE AFE INITIATION DELAY 660 '- _
. m
. 640 - -
S B .
n a 620 - -
it -
1 500 .a -
p 0VTLET
$ 580 - - -
h g 560
_[N
-~
-- g+ gWm s 8 % n.- w ,ta.w h % m INLET 540 - -
~ 520 - -
g 4
w -
C 500
' I ' ' ' $
y a 100 200 300 400 500 600
C C i aO . . .J zmca ca == - - - - 3
. c-! 4 e, j ,
. 1. .
86-1102525-00 Figure 3-12 LOSS OF FEE 0 WATER AT T = 0 SEC NO AUXILIARY FEE 0 WATER 1 i i a i i b 800 -
PRESSUR12ER FILLS -
(RCP RONNING) 700 - -
_ RCP C0AST00NN d
a 600 - -
li e-U .
5 500 A@ -
. FLOW AS REPORTE0 IN REFERENCE I.
E v>
400 - -
~
300 PORY OPERATES (RCP RUNNING) 200 EG RCP C0AST00NN 100 -
0.4 1.0 2.0 3.0 4.0 5.0 0 lime to reactor trip (" delay") - seconds j}[8 jf4
~
86-1102525-D'
4.0 CONCLUSION
S AND SINMARY A spectrum of delay times, representing anticipatory trips, has been analyzed for the loss of feedwater 1.-- sient. The spectrum included trips at time zero, with a 0.4 second instrument delay, up to high RC pressure trip at time 8.0 seconds. Since a high RC pressure trip occurs very soon after a loss of heat sink (overpressurization) transient from 100% FP, only turbine trip and direct loss of feedwater detection trips would be considered Anticipatory.
For all tripo considered, including high RC pressure, the PORV is not actuated when normal system operations occur. The pressure rise in the primary side is less for the anticipatory trips providing additional margin to FORV lift. If auxiliary feedvater is significantly delayed, then an anticipatory trip will, at best, proviJe about 1 minute add.itional time to PORV lift and about 3 minutes additional time to filling of the pressurizer. These results can be seen in Table 4-1 which shows the sequence of events for a LOFW transient with trip on high RC pressure (2300 psig) and trip at time zero.
I178 J45
86-1102525-00 TABLE 4-1. LOFW-SEOUENCE OF EVENTS COMPARISON 40-s 120-s TRIP AT ZERO, EVENT AFW DELAY NO AFW NO AFW Loss of feedwater initiated 0 0 0 0 (trip occurs)
(0.4 delay)
High-pressure trip (2300 psig) 8 8 8 a PORV opens (2450 psig) a a 175 235 Peak RCS pressure 10 10 175 235 Pressurizer full' a a 620 790
- Does not occur for these cases 1178 )46
, 86-1102525-00
REFERENCE:
- 1) B&W Retort to the FRC, May 7, 1979, " Evaluation of Transient Behavier and Small Reactor Coolant System Breaks in the 177 Fuel Assembly Plant".
1178 J47
86-1102525-00 APPENDIX A LOSS OF ONE FEEDWATER PUMP A special analysis was perforned at the B&W Owner's Group request.
This analysis considered the loss of one main feedwater pump with the plant operating at 100% FP, RC pumps running, no power runback or auxiliary feedwater initiation and a RC high pressure trip setprint at 2300 psig. The base parameters for this study are the same as those used in the " realistic" analysis presented in Section 4.2 of the May 7, 1979, B&W Report for 177 FA plants.
The objectives of this study were two-fold:
- 1) Determine if the PORV will lift under a loss of one feedwater pump situation, and,
- 2) Determine if the OTSG 1evel would be a viable anticipatory trip, i.e., how rapidly does the steam generator inventory decrease in relation to the time a high RC pressure trip would occur.
RC system pressure and pressurizer level as functions of time are shown in Figures A-2 and A-3, respectively. Reactor trip occurs on high pressure (2300 psig) in 15.8 seconds af ter the loss of one main feedwater pump. Figure A-4 shows the steam generator mass as a function of time and only 30% of the mass is boiled off by the time the reactor trip occurs. This is insufficient inventory decrease to cause a level trip in an anticipatory mode. Figure A-2 shows that no PORV actuation results from this transient.
1178 ]41B
. 06-1102525-00 Figure A-1 FEE 0 WATER C0AST00M TO 50'4 I i i i 100 -
90 - -
80 - -
70 -- -
e E
g 60 - -
50 - -
40 -
30 - -
20 -- -
10 - -
O I f I I 20 40 60 80 100 -
O Time, seconds 7;.
36-1102525-00 Figure A-2
.FEEDWATER C0AST00RN TO 50r, 2400 ,- , , , ,
2300 -
E
.T a
a E
a E
x 2200 -
2100 l
1 2040 3 I I '
0 5 10 15 20 25 Time, seconds 1l78 250
86-1102525-00 Figure A-3 FEEDWATER COAST 00EN TO 50%
24tl i i i i 230 -
U 5
5 U -
2 N
Z 220 -
5 \.
O e
l I
210 L. -
200 1 -- 1 ' ' ll b )b) 0 5 10 15 20 25 Time, seconds
80-1102535_o9 Figure A-4 LOSS OF ONE FEE 0 PUMP-RAMP TO 50% IN 10 SEC TOTAL S/G MASS, CADDS i i i i 1.0 -
O E
.8 -
5 E
o .6 -
.4 I I I I O 5 10 15 20 25 Time, seconds 1178 252}}
