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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] |
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tue.csuas Ltr trans the following: Revised FSAR pgs with regard to " Purging for control Hydrogen Concentration" . . . . .
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, 1 Docket No. 50-302
, i Dear Mr. Sto 3 In reference to FSAR Section discussion on " Purging for Control Hydrogen Con-centration", we propose to revise certain pages to our FSAR.
Attached are the affected pages 14B-V, 14B-3, 14B-9, 14B-13, 14B-19, 143-20, 14B-23, 14B-24, 14B-35 and figures 14B-6.4 to 14B-6.2, 14B-6.5 to 14B-6.3, 14B-6.6 to 14B-6.4, 14B-6.7 to 14B-6.5 of the revision to the FSAR Section 14 Appendix B entitled "An Evaluation of Purging as a Means of Controlling Post--
Accident Reactor Building Hydrogen Concentration" to be incorporated in the next amendment. This revision affects only the intermittent purge flow rates and length of purge times and does not violate the appropriate Codes and Regulatory Guides. Figures 14B-6.2 and 14B-6.3 have been deleted, as these figures are not applicable to the changed intermittent purge conditions.
As in past procedures, these noticed changes are effective i= mediately and arc so implemented. The next amendment to our Crystal River #3 FSAR will incorporate them by appropriate change procedure.
With this submittal the item is considered closed but should you have questions or need anything further, please advise us immediately.
Very truly yours, I
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LIST OF FIGURES (At Rear of Section)
Figure No. Title 1bB-5 3A MHA Thyroid Dose at Low Population Zone (1500 GPM RB Spray Flov) lhB-5. 3 B MHA Thyroid Dose at Lov Population Zone (1200 GFM RB Spray Flow) 1hB-5.h MHA Whole Body Dose at Low Population Zone 1hB-5.5 LOCA Dose Sensitivity to Hydrogen'G-Value 1bB-5.6 MHA Dose Sensitivity to Hydrogen G-Value lhB-5 7 LOCA Dose Sensitivity to Z -H 0 Reaction r 2 lhB-5.8 MHA Dose Sensitivity to Z -H 0 Reaction r 2 lhB-5.9
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Hydrogen Purge Flow Diagram lbB-6.1 Crystal River Accident Meteorology 152 f. Ir.tc s itt;r.t h rg; "ct;;r.1;gy
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m 21c 2 lhB-6.& 2. Thyroid Dose Probability 1hB-6.9 3 Thyroid Dose Probability Distribution 1hB-6. 4 Whole Body Dose Probability Distribution lhB-6.7 5 Dose Probability Distribution Using Regulatory Guide 1.7 l Apsumptions i
IhB-v Am. 38 (3-25-Th) 4 I:
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.' flow. Fcr th2 spray flow r duction, the mora conservative etse of a constant 1200 gpm spray flow v s essum:d; otherwise, a constant spray flow of 1500 gpm was used in the analysis to determine the reactor building airborne iodine concentration.
. Analyses of both intermittent and continuous purging at the Crystal River site indicate that intermittent purging would be expected to result in much icver doses than continuous purging. Table lhB-2.1 shows a comparisen of the results obtained for intemittent and continuous purging. The initial contin-uous purge rate for Regulatory Guide 1.7 assumptions utilized in arriving at the whole body and thyroid dose calculations shown in Table lhB-2.1 was 2.8% of the containment volume per day or 38.9 SCFM. Purging was assumed to start at 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> after the MHA using Regulatory Guide 1.7 assumptions and was allowed to gradually decrease in time.
12.0 Intermittent purging was assumed to occur for a maximum of Z minutes in any l 2h-hour period. Furthermore, purging was assumed to be initiated only when vinds were blowing in an offshore direction. Continuous purging was assumed to start at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> after the LOCA and 980 hours0.0113 days <br />0.272 hours <br />0.00162 weeks <br />3.7289e-4 months <br /> after the MHA while inter-mittent purging was started 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> earlier to account for the possibility of persistent onshore vinds.
Because of the inherent advantage of attempting to utilize the high frequency of offshore vinds, the preferred mode of purging is intermittent. The alter-
~
native to containment purging (continuous or intermittent) is the use of recom-biners for post-accident hydrogen centrol. McVever, the resulting off-site incremental doses due to post-accident hydrogen control by purging for Crystal 2, River Unit 3 are so lov, even when evaluated on the very conservative basis suggested in AEC Regulatory Guide 17, that Florida Power Corporation does not believe that the addition of a recembiner system as either a primalr or backup means of control is warranted. Further, the potential for malfuncticn of a recombiner system and the possible serious secondary effects which might be produced in such an event cannot be justified in light of the lov doses that are projected as a consequence to operation of a simple and highly reliable purging system. Florida Power Corporation further believes that the favorable meteorological conditions at the Crystal River site can be used to allow intermittent purging to reduce the probable projected off-site dose.
The analyses presented in this appendix demonstrate that controlled purging can be utilized to maintain hydrogen cencentration below flammable limits without delivering excessive total doses to the public. The projected incremental whole body do.Ms for both the MHA and LOCA as a result of purging are considerably less than the average annual natural background of 125 mr in the Crystal River area. Even vten the extremely conservative Pegulatory Guide 1.7 assumptions are used, the projected incremental whole body denen are expected to be less than -1", of 10 CFR 100 limits. In all cases donc en.lculat.icns were made using conservative assumptions.
Both continuous purging and intermittent purging which utilizes favorable wind directions have been examined. Based on a comparison of the results, inter-mittent purging has been selected as the preferred purging method. Calculations have also been made in accordance with the assumptions given in AEC Regulatory Guide 1 7 and are also shown in. Table lhB.2-1.
VlBY 113 . , lhB-3 Am. 38 (3-25-Th )
j :3 la
I
.' which tra- felt by' the rIgulatory staff to be c6nservative for the various para-meters aff&cting post-Iccidsnt hydrogtn accumulation. The assumptions given in
'the guide which are more conservative than the assumptions used in lhB.3 1.and lhB.3.2 are as follows:
- a. The fraction of fission product gamma energy in the fuel rods absorbed in_the coolant is 0.1,'(calculations indicate that the fraction should vary with time from 0.lk to 0.08).
.b. The fraction of zirconium cladding reacting with water is 0.05, (calculations indicate that 0.01 is conservative).
- c. The radiolytic hydrogen yield, G(H2 ), is 0 5 molecules of hydrogen per 100 electron volts of absorbed energy in the core and sump water, (Experimental evidence indicates that G(H ) = 0.3 for the sump water). 2 To obviate selecting from a range of alumihum corrosion rates as recommended by the guide, the complete reaction of 1000 lbs of aluminum was assumed. Using these modified assumptions, purging must start at approximately 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> after the MHA. Figure lhB-3.8 shows the containment building hydrogen concentration as a function of time following an MHA using Regulatory Guide 1.7 assumptions.
If continuous purging were started at 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> and continued far a period of two months, the dose increment at the low population zone distance due to purg-ing would be 2h8 mrem.to the whole body and 581 mrem to the thyroid.
IhB.h EVALUATION OF PURGlNG FOR CONTROL HYDRCGEN CCNCENTRATION 1hB.h.1 DISCUSSION OF PURGING CONCEPT The controlled purge concept may be utilized for post-accident hydrogen cen-trol because hundreds of. hours are available for fission product decay before the purging starts. The preferred purging approach evaluated herein is to allow the hydrogen concentration to increase until the control limit of 3 5 i vol". is reached at the projected time of 313gurs; then to purge during g {
periods of off-shore winds for a maximum of ---minutes each day at a rate that J just compensates for the hydrogen being generated.* Therefore, the maximum {
delay for fission product decay is obtained, and a decrease in purge rate re- {
sults as hydrogen generation rate decreases. This method minimizes the expected radiation dose-to the public. Continuous purging (as opposed to intermittent purging) is also considered to be capable of satisfying the requirements of hydrogen control with minimal risk and is also evaluated herein.
In order to specify purge requirements, those conditions that control the contin-uous . purge. starting times and the necessary rate of continuous purge are established as follows:
Advancing the time of intermittent purge initiation by 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> allows for the possibility of as many as 13 days during which there may be no offshore vinds.
lhB-9 Am. 38 (3-25-Th) d h"- - -
, m y % -
yv
.ww
w ; m ~.
s ~.
, Addin6.these marginc nether, a totid mnrcin of' O.6 v. / (r.pproximately 12000 ft3 )
- hydro 6cn is obtained. Thus it~is established that a conservative control purging s:;t point of 3 5 vo1% provid;;s Edrqunto margin bntwun the control limit and tha
- h. . lower limit of flammability.
IhD.h.h RF. ACTOR BUILDING HYDROGEN CONCENTRATIONS WITH CONTROLLED PURGING lhB.h.h.1- During the LOCA Conditions Combining the sources of chemical hydrogen with the radiolytic hydrogen from Figure lhB-3 5, the time-dependent hydrogen concentration in the reactor build-ing following a LOCA is obtained and presented here in Figure lhB h.2. With no purging the hydrogen concentration vill reach 3 5 vo1% in 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> (63 days).
The capability to further delay purging is indicated on this figure by the dashed line stalt.ing from the purge start point. Another 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> (h6 days) are required without purging before the h.1 vol% limit is reached. This demon-strates that the low hydrogen generation rates require long periods of time to significantly affect the existing hydrogen concentration at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.
The average daily purge flow required is a function of the building hydrogen con-centration and the hydrogen generation rate. The hydrogen ceneration rate de-creases with time, thereby decreasing the required average daily purge rate. Thus, the amount of purging is minimized to that amount which is necessary to control the
' hydrogen. For the LOCA conditions, the initial average daily purge rate is approx-imately 8 SCFM (0.6 vol% per day). The initial intermittent purge rate must be higher than this v since intermittent purging vill not be continuous but vill be allowed for.only _~ minutes in any 2h hour period and because intermittent purging is to be initiated sooner than continuous purging when hydrogen generation rates are higher.
A major factor that affects this analysis is the radiolytic hydrogen generation ;
rate. -The effect of varying the energy deposited in the coolant or the G-value '
is best expressed by the change in the time to start the purge as a function of the seneration rate. Figure lhB h.3 shows a plot of continuous purge start time as a function of the hydrogen generation rate constants. It can be seen that large variations can be tolerated without forcing the continuous purging start time (a major radiological dose controlling factor) below h15 hours, the start time which results if the G-value were twice the assumed value.
lhB.h.h.2 During the MHA Conditions l Hydrogen buildup has also been examined for the MHA. Figure lhB h.h shows the higher radiolytic hydrogen generation with the concentration reaching 3.5 vo1%
in 980 hours0.0113 days <br />0.272 hours <br />0.00162 weeks <br />3.7289e-4 months <br /> (hl days) as compared to 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> for the LOCA. The time to reach h.1 vol% vith no purging is 16h0 hours as compared to 2600, hours for a LOCA. The initial purge rate required for this accident is higher than for the LOCA because of the earlier start times when hydrogen generation rates are greater. The MHA requires an initial average daily purge rate of 13 '3CFM nn compared to 8 SCFM for the LOCA. HovcVer, t.h t n purge- rnte at:m drerennen wit.h time.
The sensitivity of the MHA purge starting time to the hydrogen constant is shown on Figure lhB h.5 Because the combination value for the generation 1hB-13 Am. 38 (3-25-Th )
f.
~ -
m .m
. /
Tha tho hydrog;n purga system mnts tha single fe.ilure critcrion (IEEE) in that
- -; in;trum;ntation is d; sign;d so that a single cvent cannot r esult in multiple failures that would prevent the required protective action.
IbB.5.h.h Reactor Building Ventilation System-(MI)
The parallel flow paths rejoin and discharge to the normal reactor building purge exhaust duct downstream of the outside purge isolation valve. The discharge then passes through the purge exhaust filters (roughing, HEPA, and charcoal) to the plant vent via the purge exhaust fans. A radiation monitor (RM-A1) samples the discharge, lhB.5.h.5 System Instrumentation Hydrogen is monitored with a combustibles analyzer, calibrated for hydrogen, with range. a range of 0 - 5 percent combustibles and an accuracy of 2 percent of Radiation is monitored in this system. R4-M monitors containment atmosphere as required and R4-Al monitors purge exhaust fan discharge to the plant vent.
R4-Al indicates particulate activity, gaseous activity and iodine activity.
The range and calibration sources for these monitors are discusned in detail in Section ll.h.2.1.2.
of the actual input rate.The overall accuracy of the readout is 1 10 percent If the activity exceeds the range of the monitors, the sample bomb may be used to take " grab samples" for laboratory analyses.
,B There are three flow indicators in the discharge system. The high capacity displacement type flow indicator (FI-1) has a rance of approximately 100 to 1000 SCFM and an accuracy of 1 2 percent of full scale. The medium capacity displacement type flow indicator (FI-2) has a range of approximately 20 to 200 SCM4 and an accuracy of 12 percent of full scale. The low capacity dis-placement type flow indicator (FI,3) has a range of approximately h to ho SCFM and an accuracy of 1 2 percent of full scale.
.' h B . S . h . 6 System operation After a loss-of-coolant accident, a minimum of 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> (more than 10 days) is available before purging of the containment atmosphere is required even under the conservative assumptions of Regulatory Guide 1.7. Portable engine-driven ecmpressor(s) with an air-receiver tank of the type commonly used in construction vill be connected to the leak rate test con. ections outside the intermediate building. Several such compressor (s) with a capacity of 25 CFM or more vould be obtained to assure that a reliable compress.ed air supply could be maintained in the receiver tanks. These types of air compressor (s) are readily available and, in an emergency, can be obtained in sufficient time from anywhere within the United States to permit. ric1d connection to existing piping provided for this purpone. The enntainment monitoring sub-system contairment. vill be used to monitor the activity and hydrogen concentration of the Prior to ecmmencement of purging, the ccmpressor(s) vill be used to raise and maintain the reactor building pressure to approximately + psig 2 l G
lhB-19 Am. 38 (3-25-7h )
6->
'(during the entirc. purging period) The operator vi)) monitor vind speed nnd direction in the control room and direct control of the purge rate in accordance with a specific purge plan. The makeup sub-system vill be operated as necessary #
to maintain adequate reactor building pressure. Compressor (s) in sufficient '
number and capacity are available for rental at numerous locations within 100 miles cf the site.
This type of equipment has been previously rented from the followinC companies for construction and maintenence.
- 1. Air Component & Equipment, St. Petersburg, Florida
- 2. Compretsed Air Products, Tampa, Florida 3 Hert: Rental Equipment, Tampa, Florida
.Additicnally, Florida Fover Corporation owns and operates within its operational divisions sufficient available compressor capacity.
Conventionally these compressors are engine or electric motor driven equipment.
Sufficient numbers of equipment units are available to provide backup alternate c:pacity for reliable operation.
IhB.6 INTERMITTEMT FUBG1!!G
-1hB.6.1 INTERMITTENT PURGING CONCEPT.
Purging to control. post-accident containment building hydrogen concentratiens can be conducted either continuously or intemittently. Intemittent purging is the preferred mode due to the inherent ability to purge selectively, under favorable meteorological conditions (offshore vinds). The banic premise of thed of - gtermittent purge procedure to be employed is to purge for a maximum l -minutes each day, in the presence g o Beginning at midnight,theoperatorvillinitiatea._goffshorevinds. minute purge as soon as sustained offshore winds are observed. '#' 77 . i '. r 'd r. , th , -
"Il : ' i--
f-- - M17 e. , . ,..'1_:: c " ; ; _ .. i'. ' . . . . i r '_ . n._ ' -
I'; ' " " ' ' .
If.no offshore vinds are detected on a given day, there vill be no purce on that day. The purge rate for a given day vill be detemined by the observed rate of
-increase in the hydrogen concentration in the containment building, and vill be datemined such that as much hydrogen vill be released asds generated that day.
l Tha required purge rate for intemittent purging vill be ~ times the required purge rate for continuous purging. Table lLB-6.1 presents the required contin-uous purge rate to stabili:e containment building hydrogen concentrations, as a function of time, for the LOCA and MHA.
Analysis of on-site meteorolegical data collected during calendar year 1972 indi-cates-that there vere h9 days out of a total of 366 in which no offshore vinds vare recorded. Thi; total includes 3 days in which no data was recorded.
The annlysis of the doses resulting from intermittent purcing in bnned on the radiologien1' impact produer*<1 by the firnt 60 purcen. An dincunned beltu, done o.nnlysis resulto nre obtained first for the initial 30 purges, during which most of the radiciodine either decays or is released. These results are then cxtended by extrapolation to include the first 60 purges. The 197;' meteorolo-gical data indicates that the createst time _ span required to includo 60 dnys in which offshore vinds were observed is 73 days. Thus, intermit tent purging is initiated 13 days (312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />) in advance of the required initiatien time lhE-20 Am. 38 (3-25-Th) h
. m .g- -
/~
Potential dosec due-to purges on days where n=? are connidered um11r,1ble. As
' the everaga offshora vind spsd is about 6.9 miles per hour, an offshore vind durs. tion of 1.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> (n=2) indicates a mean transport distance, for the midpoint of the plume - given a direct reversal .of almost 19 miles to the LPZ radius. . This transport distance is almost h times the LPZ radius, used in evaluatin6 doses where-n=1. Thus, there were 20 da/s in the year 1972 where, if an intermittent purge had been executed, the resultant doses at the LPZ radius would be considered non-negligible under the above assumptions. These are the 20 days where the value of the parameter n was determined to be equal to one.
The potential doses at the LPZ distance due to intermittent purges on days where n=1 have been conservatively evaluated utilizing the following' assumptions:
12 0 1). The entire -99 minute purge is assumed to be released into the l
following onehore vind characterized by the actual recorded vind speed, direction, and stability class.
2). The plume center-line X/Q at the LPZ distance (calculated using the recorded vind speed, direction, and stability class of the following onshore vind) is utilized to calculate doses.*
3). Adult thyroid I-131 inhalation deses are calcula maximum 8houraveragebreathingrate3.h7x10gedusingthe m3/ sec.
h). External whole P dy doses are caleJated using the semi-infinite sphere model and are based upon the total average beta and gamma energy released per disintegration.
Table lhB-6.3 presents the pertinent meteorological data and the calculated center-line of the plume X/Q values for each of the 20 days of 1972 where t ." n=1 and the folleving onshore vind is not out of the southeast. The activity estimated to be released in each of the first 30 purges, for both the LOCA and !GA, is presented in Table lhP-6.h.
In order to further illustrate the calculational procedure utilized in this analysis, assume that it was necessary to initiate intermittent purging (following a LOCA) on the h0th day of 1972. Examinatien of the metecrological data indicates that radiological impact (n=1) would result from the fifth, eighth, and seventeenth purges. This is because the parameter n was determined to be equal to one on days h5, h8, and 65 of the year 1972.** The doses due to the fifth purge vould be evaluated using the value of X/Q calculated for day h5, (as in Table lhB.6-3) and the activity releases appropriate for the fifth purge (asinTablelhB.6-4) The same evaluation is then performed for the eighth and seventeeth purges. If the doses occur in the same onshore sector, they are summed, and the dose totals due to the first 30 purges are then ecmputed for each onshore sector. The dose totals by sector are then compared and the maxi-mum doses (thyroid and whole body) at the LPZ radius due to the first 30 purges, assuming intermittent purge initiation on day 40, are obtained. The above pro-cedure was repeated for each day of the year 1972, for both the LOCA and MHA, and the results presented in Table lhB-6.2 vere obtained.
The equation used to cciculate the required X/Q valucu is: X/Q = 1/(ne y g ad No offs!---- vinds were observed on days hh , h9, 50, 51, 55, 56, 57, 58 and 63 of the year 1972. Therefore an intermittent purge would not have (w%). been executed on these days.
lhB-23 Am. 38 (3-25-Th )
la '>
m -
'lh B". 6. 3 DOSF. SEtlSITIVITY -
The sensitivity of dose resulting from variations in those parameters considered in Ecction lhB.5.3 vi31 show similar behavior to that demonstrated previously for continucus purcing. Such similarity is to be expected since dose is determined by the activity in the containment building at the time purge starts and the purge rate requirec.
Since neither of these is affected by the purging method used it may be concluded that the dose sensitivity vill be similar.
lhB.6.h INTERMITTFNT FURGING FROCEDURE-The system described under Section 1hB.S.h is operated as previously described except conditions. that an intermittent purge vill be initiated only under certain specified In Appendix lbC, an offshore vind is defined as a vind blowing from any sector frcm north, eastward to the east-southeast cector. Purging of the containment building tc centrol hydrogen, if required, vill be initiated only when the vind is bleving frcm these sectors. Purging, once started .:1 continue for a period of Nminutes. may In the event of an accident which could result in substantial hydrogen generation, the operator vill observe the hydrogen cccumulation rate and vill continually project the time required for the concentration v 3 increase from its present value to 3 5 vol%
When the projected time to reach 3 5 vol% .-comes 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> or less, purging is started as soon as the vind direction permits. The cperator vill set the purge rate at l gtimesthedailyrateofchangeofthehydrogenccicentration.
l As the rate of hydrogen generation decreases, the purge flow for any -12+0 minute purg-ing episode is also correspondingly decreased based en the obcerved rate of hydrogen increase in the interval prior to purging.
Information required by the operator to purge according to the procedure outlined above is identified as follows:
- 1. Containment pressure, psig
- 2. Centainment temperature, F
- 3. Purge flow, CFM (actual)
- h. Hydrogen concentration, volume percent 5
Elapsed' time frem initiation of previous purge
- 6. Wind velocity and direction lhB.7 EVALUATION OF INTERMITTENT VS. CONTINUOUS PURGING In Sectionn'1hD.5 and lhB.6 the doses resulting recm continuous and int.cr-mittent purging are evaluated. These results are procent.cd in Table lhli-2.1 where it may easily be observed that doses estimated to result frcm inter-mittent purging are only small fraction of those estimated to result from continuous purging. There is a decided advantage in favor of intermittent purging, in terms of reduced radiological impact to the public.
lhB-2h Am. 28 ( 3-25-74 )
[-
@ 3 0 '
t Table lhB-6.h Activity Releases by Purge for First 30 Intemittent Purges Tice After Accident Activity Releases by Purge. c'uries Required'Intercittent-Purge Until Purge, hrs I-131 Kr-85 Xe-133 Purge Rate, cfc Number IEA LOCA MHA LOCA MHA LOCA MHA LOCA MHA LOCA 3* 6L8 1176 5.10-1 1.71-3 1.40+2 6.38+1 9.77+2 1.98 8%-6 21).2 L 7; . 2 t/8,8 2 672 1200 h.62-1 1.51-3 1.38+2 5.95+1 8.h5+2 1.62 OL'. 0 2 f l.2 LLC. L ill .6 3 696 1224 L.19-1 1.38-3 1. 3 7+2 5 91+1 7.32+2 1.h1 CLL . 0 2i t. 2.L LC . L ill. 4 4 720 12b8 3.49-1 1.26-3 1.2h+2 5.87+1 5.83+2 1.23 777. S l94.4Li!. ' Ill. 6 5 TEL 1272 3.17-1 1.15-3 1.23+2 5.83+1 5.06+2 1.07 7. 7. 0194.4 LL C. L/ / /. /
6 768 1296 2.87-1 1.04-3 1.21+2 5.79+1 h.38+2 9.34-1 777. 5194.4W+Allt. t )
7 792 1320 2.61-1 8.89-h 1.20+2 5.38+1 3.80+2 7.60-1 777.6194.4. L;7. :/Of.4 8 816 134h 2.18-1 8.11-4 1.09+2 5.3h+3 3.03+2 6.62-1 71; . 2176.8 L17. 0/of. 4 9 840 1368 1.98-1 7.39-4 1.08+2 5.31+1 2.63+2 5.77-1 71; . 2: 78.8L 17. !/0 f.4-10 86L 1392 1 79-1 6.74-h 1.07+2 5 27+1 2.28+2 5.03-1 71; . 217&.8 L;7. 5/04.4-11 888 1h16 1.63-1 5.80-h 1.06+2 4.9h+1 1.98+2 4.13-1 71;.2178.8 ;3;.5 9 8.1-12 912 1h40 1.36-1 5.29-4 9.59+1 h.91+1 1.58+2 3.60-1 e n -6164 8 :33. C 98.4 13 936 1h6h 1.24-1 h.83-4 9 50+1 4.88+1 1.37+2 3.1h-1 C; . ld>4.8 ,,_,.C 9 8 4' e lh 960 1488 1.12-1 4.ho-b 9.40+1 h.85+1 1.19+2 2.73-1 C;7. C f 64'.8;;;. : 98 4 5 15 98L 1512 1.02-1 3.77-4 9.31+1 h.53+1 1.03+2 2.2h-1 G;7. C lG4.8 7C, . 92.4-16 1008 1536 8.59-2 3.bh-h 8.5h+1 h.50+1 8.31+1 1.95-1 C;;.:#52 47:;.: 92. 4 17 1032 1560 T.81-2 3.1h-h 8.h7+1 h.48+1 7.22+1 1.70-1 60:.:152.4769-6 92.4-18 1056 1584 7.11-2 2.87-4 8.39+1 4.45+1 6.27+1 1.h8-1 CC .:'52 47:3.; 92. 4 19 108; 1608 6.46-2 2.h8-4 8.31+1 h 20+1 5.L5+1 1.23-1 4 fe% /52.1;;; . '. 87.6 20 110L 1632 5.47-2 2.27-4 7.66+1 h.16+1 h.Lo+1 1.07-1 :::. LI4I. 6 ;L. ; 87.4 21 1125 1656 h.97-2 2.07-h 7.59+1 h.16+1 3.83+1 9 35-2 964A/11 6;%. '. 87.6 22 1152 1680 h.53-2 1.89 h 7.53+1 h.13+1 3.33+1 8.15-2 9 9 /4/.4;L.'. 87 's '
23 1176 170h h.12-2 1.63-h 7.01+1 3.89+1 2.89+1 6.72-2 566A/4/. 4;;1. 2 82.v 2h 1200 1728 3.52-2 1.h9-h 6.96+1 3.87+1 2.37+1 5.86-2 999-e/33.2 ;;1. 2 82.8 25 122L 1752 3.21-2 1.36 h 6.90+1 3.85+1 2.06+1 5.11-2 ;;:.;t3 3.2;;1.2 82.8 y 26 12L8 1776 2.92-2 1.24-4 6.8b+1 3.83+1 1.79+1 4.46-2 5;; . 3/53.1;;1.2 82.8 27 1272 1800 2.66-2 1.08-h 6.79+1 3.6h+1 1.56+1 3.72-2 999-e/53.1;_:.: 79.2.
g 28 1296 182h 2.42-2 9.89-5 6.73+1 3.62+1 1.35+1 3.25-2 532. 2/ 53.2.;1C. 2 79.2.
_ 29 1320 1848 2.07-2 9 03-5 6.26+1 3.60+1 1.10+1 2.83-2 499-e/24.8;;;. : 79.2.
y 30 13ht 1872 1.88-2 8.25-5 6.21+1 3.58+1 9.61 2.h7-2 W/>.4.8 E+:d 79.2.
N v
- The first purge is assumed to occur h9 days after a LOCA and 27 days after an MHA.
O
Percentage 15 20 80 85 C
5 10 30 40 50 60 70 90 95 98%
- I I II I I I I I I -I ' I :
THYROlO DOSE PROBABILITY
/ --
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I I l l I l l 10-8 J.5 4.0 4.5 50 5.5 6.0 6.5 Probability Dose 5 0 THYROID DOSE PROBABILITY CRYSTAL RIVER UNIT 3 2.
ET FIGURE 148 6 *-
(AM. 38 3 25 74)
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.- N 1
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1 De-MHA 10-3 m-
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- 5 -
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o 10 4
_ LOCA 10-5 f ' ' ' ' ' ' ' ' ' ' ' ' ' '
10-2 10-1 1 Probability Dose Will Exceed 0 '
THYROID DOSE PROBABILITY DISTRIBUTION CRYSTAL RIVER UNIT 3 3-
=-
FIGURE 148-6+
, (AM. 38 3 25 74) g
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.', 10-2
_ MHA 10-3 ~
E LOCA 8 _
~
s 3
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10-2 10 -3 I Probability Ocse Will Exceed D' WHOLE BODY DOSE PROBABILITY DISTRIBUTION CRYSTAL RIVER UNIT 3 4-ga; FIGURE 148-6+
~
A (AM. 38 3-2$ 74) 4 -7
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- g. .: . .-
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8 22 10-2
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' ' ' ' ' ' ' ' ' ' ' ' l 10-3 g 10 -1 10-2 Probability Dose will Exceed O' DOSE PROBABILITY DISTRIBUTION U$lHG REGULATORY GUIDE 1.7 ASSUMP GONS CRYSTAL RIVER UNIT 3g
_ FIGURE 148-6.1-6!
E** '(AM. 38 3-25 74) m