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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
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1 1
\,
, Ficrida Power
? A "ST 8",.'OI."d mn hnuary 5,1998 3F019812 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Respnse to Generic Letter 97-04, "Asrurance of Suflicient Net Positive Suction licad for Emergency Core Cooling and Containment Heat Removal Purnps"
Dear Sir:
Genetic Letter (GL) 97-04, " Assurance of Suflicient Net Positive Suction liead for Emergency Core Cooling and Containment IIcat Removal Pumps," dated October 7,1907, requested specific infonnation be provided to the Nuclear Regulatory Commission (NRC) wit W n 90 days of the date of the GL Florida Power Corporation (FPC) is hereby submitting the requested infomtation relative to the Crystal River Unit 3 Nuclear Generating Plant (CR-3). The information is provided in the Attaciiment to this letter. No commitments are made in this submittal.
Should you have any questions or requ re additional infomation conceming this response, please contact Mr. David Kunsemiller, Manager, duelear Licensing at (352) 563-4566.
Sincerely,
[tb -
Amh J. Iloiden Director Site Nuclear Operations /
/
.IJil.kdw Attachment xc: . Reponal Administrator, Region 11 Lf / f//
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NRR Project Manager Senior Resident inspector j)'****.'I.
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- 9801000045 980105 PDR ADOCK 05000302 p PDR CRifSTAL RIVER ENERCY COMPT.EX: 15760 W. Power Line Street
- Crystal River, Floritsa 34428 6708 e 0521795-6486 A ARwins Progress Company
l e r i U.S. Nuclear Regulatory Commission
- 3F0198-12 Page 2 of 2 STATE OF FLORIDA COUNTY OF CITRUS John J. liolden states that he is the Director, Site Nuclear Operations for Florida Power Corporation, that he is authorized on the part or'said company to sign and fi!e with the Nuclear Regulatory Commission the information attached hereto; and that all cuch statements made and matters 4 set forth therein are true and correct to the best of his knowledge, information, and belief.
IL Jo J. lioiden Director Site Nuclear Operations Sworn to and subscribed before me this 6 _Mday of d4 a ve T 1998,by John J. Holden. y Signature ofNo$ary Public State of Florida USA ANN MCBRIDE Notary Public, State of Floride l
My Comm. Exp. 0ct. 25, IM9 C*""". no Cc mse }y, ggn f77 cg,, Jg (Print, type, or stamp Commissioned Name of Notary Public)
Personally Produe::d Known
[_ -OR Identification l
l
' U.S. Nuclear Regulatory Commission Attachment -
3F019812 Page 1 of 9 ATTACilMENT RESPONSE TO GENERIC LE' ITER 97-04 Generic Letter (GL) 97-04 requested specific information regarding the available NPSH for the emergency core cooling (incleding core spray and decay heat removal) and containment heat removal pumps that meet either of the fewing criteria:
(1) pumps that :ake suction from the containment sump or suppression pool following a design-c- basis loss-of-coolant accident (LOCA) or secondary line break. or (2) pumps used in " piggyback" operation that are necessary for recirculation cooling of the reactor core and containment (that is, pumps that are supplied by pumps which take suction directly from the sump or suppression pool):
The following pumps at CR-3 meet the specified criteria and are, therefore, within the defined scope of GL 97-04:
APPL.lCABLE GidEIT11RIA P_UA1E 1 Building Spray Pumps (BSP) l A/lB 1 Decay lleat Pumps (DilP) l A/lB 2 Makeup Pumps (MUP) I AllB/IC The requested information is provided below, as applicable, for the pumps within the defined scope of GL 97-04:
NRCINFORA(A110NREQUEST:
(1) Specify the general methodok>gy used to calculate the head lou associated with the ECCS suction strainers.
FPCRESPONSE:
Building Spray Pump and Decay llent Pump Evaluation The NPSII evaluation looked at the worst case conditions from an NPSH standpoint, and combined different accident scenarios to be bounding. The following general assumptions were used to calculate the most limiting NPSH values for the BSPs and the DIIPsi
- 1. Minimum Reactor Building (RB) pressure
- 2. Minimum RB sump level
- 3. Maximum pump flow rates (this obtains the maximum piping losses)
. 4. Maximum vapor pressure expected at time of sump recirculation
9 l' .
U.S. Nuclear Regulatory Commission Attachment 1F019812 Page 2 of 9 The LOCA scenario used is such that the break is in the Reactor Coolant System (RCS) piping at a high enough elevatian that no RCS volume is available for flooding. The break is also of a size that would result in the highest expected flows (including instmment error) from the Decay Hect Pumps (DHPs), the Building Spray Pumps (BSPs), and the Makeup Pumps (MUPs) in the " piggyback" mode of operation. Although Low Pressure injection (LPI)is in operation (which would require that RCS pressure be below the Core Flood (CF) system actuation point), no credit is taken for the CF tank inventory. The maximum expected temperature with no pressure in the RB (212" F) is used at the time of sump recirculation which willincrease the afTect of vapor pressure. This is a conservative assumption because the duration of a temperature at 212" F is short, and as temperature drops so will the affect of vapor pressure. Details regarding the methodology uted to calculate NPSH values follow.
The basic equation for calculating available NPSH (NPSH.) is:
NPSH. = h. - h, + h - hr.
where:
- h. = absolute pressure on the surface of the liquid supply level.
h, = head corresponding to the vapor pressure of the liquid at the temperature being pumped.
h, = static height that the liquid supply levelis above the pump centerline.
hr. = all suction line losses including entrance losses and friction losses.
Additional detail regarding each term is prov;ded below.
- h. = abrolute pressure on the surface of the liquid supply level This absolute pressure is made up of:
- 1. Atmospheric pressure present prior to the postulated loss of coolant accident (ho.).
- 2. Increase in containment pressure that results from the postulated loss of coolant accident (ht.oca).
, .onsistent with Regulatory Guide 1.1, " Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps," FPC applies the regulatory position that the emergency core cooling and containment heat removal systems should be designed so-that adequate NPSH is provided to system pumps assuming maximum expected temperatures of pumped fluids and no increase in containment pressure from that
U.S. Nuclear Regulatory Commission Attachme.nt 3F0198-12 Page 3 of 9 present prior to postulated loss of coolant accidents (LOCAs). This results in hun = 0 ft; therefore, h. = h.i = 33.9611 (14.7 psi).
Note: The partial pressure of air would be higher than 14.7 psi due to the elevated temperatures, but is not credited for conservatism.
hy, = head corresponding to the vapor pressure of the liquid at the temperature being pumped FPC uses satursted fluid at a temperature of 212" F when drawing santion from the sump.
This is the expected temperature at the time of swapover from the Borated Water Storage Tank (BWST) to the Reactor Building (RB) sump asauming no pressure in the RB. Fluid temperature is expected to decrease soon after swapover which decreases the effect of vapor pressure. At a fluid temperature of 212 ' F, hy . = 33.96 ft (14.7 psi). This equals the pressure present prior to the postulated LOCA (h.im = h,) and leaves only static head above the pump centerline to provide adequate NPSH.
h., = static height that the liquid supply level is above the pump centerline j
FPC calculates a minimum static height using the following assumptions:
- 1. The minimum Improved Technical Specifications (ITS) BWST level. The BWST is the primary contributor to RB sump level.
2 Initial BWST temocrature is assumed to be at its highest allowable temperature to minimize the afTect ofincreased level due to fluid expansion.
- 3. Inventory iam the makeup tank contributes to the available inventory (very small percentage).
- 4. The minimum RB flood level assumes saturated fluid at 212" F which takes into account evaporation of water due to the elevated temperatures. t
- 5. Additional iaventory unavailable for recirculation is accounted for from cavities that act as holdup volumes and prevent contribution to the static beight.
- 6. No credit is taken for the inventory in the Core Flood Tanks.
- 7. No credit is taken for RCS inventory that would contribute to the available static height due to flow through the break.
hr, = all suction line losses including entrance losses and friction losses FFC calculates suction line and friction line losses using the following assumptions:
U.S. Nuclear Regulatory Commission Attachment 3F019812 Page 4 of 9
- 1. The pipe and fittings are 304 stainless steel. The pipe roughness is assumed to be that of clean commercial steel pipe. This is a reasonaMe assumption because typically there are not extended periods of flow through this section of pipe.
- 2. The length of piping accounted for is from the sump intake to the pump inlet.
- 3. Flow rates for the BS, DH, and MU pumps were assumed at the maximum flow rates when taking suction from the RB sump, with worst case instrument errors added. Credit fer Emergency Operatmg Procedures (EOP) is taken to throttle flows to the designed flows when taking suction from the RB sump.
- 4. Vendor data for all of the valves in :he suction lines was used in the NPSH calculation including the check valves just upstream of the BS pumps. Flow coeflicient (C,) values were provided at the apphcable flow rates to account for the insuflicient flow to maintain the check valves in the full open position.
Suction head losses were calculated using Reference 10. In addition, FPL p-dormed a test and evaluation an the system head losses for the BS system. The results of the test clearly show the calculated line losses to be conservative when compared to the actual results from the test (Reference 3).
The following approach was used for sump screen losses:
- 1. An assum9 tion of I fVsec through the screen is used to calculate the head loss, which accounts for an area reduction of approximately 53% from blockage of debris that may be present. This area reduction is consistent with Regulatory Guide 1.82, Rev. O, " Sumps for Emergency Core Cooling and Containment Spray Systems,"
which was used as a guide in the calculation of sump screen losses- Regulatory Guide 1.82, Rev. O states that, "The available surface area used in determining the design coolant velocity should be based on one-half of the free surface area of the fine inner screen t conservatively account for partial blockage."
- 2. The hydraulic loss through the inner sump screen accounts for the actual open area of the screen.
- 3. The .esultant head loss through the inner sump screen using the above approach is on the order of 0.0M ft Makeup Pump Evaluation The NPSH evaluation for the MU pumps was done separately from that of the SS and DH pumps since, when the MU pumps are m the " piggy-back" mode of operation, they are subject to the discharge pressure of the DH pumps. As a result, some simplifying assurrptions can be made.
4 U.S. Nuclear Regulatory Commission Attachment 3F0198-12 Page 5 of 9 MU pump NPSil values were calculated using the following assumptions:
- 1. RB pressure was assumed to be 0 psig. No credit was taken for RB overpressure. -
- 2. MU pump flow rate was assumed to be at a maximum value (600 gpm).
- 3. DilP ficw rate was maximized (this obtains maximura piping losses and minimum pressure rise across the Dil pumps).
The analysis was performed assuming that sli three MU pumps have the same NPSil characteristics A calculation of each individual MU pump NPSil value was not performed because the pumps are similar and the NPSil margin is greater than 200 feet.
NRCINFORAfA110NREQUEST:
(2) Identify the required NPSH and the amilable NPSH.
FPC RESPONSE.
The required NPSil and the available NF3!I values for the BSPs, DilPs and the MUPs are identified in the following table. The available NPSil valt.u were calculated using the methodologies outlined in the above response to NRC Information Request (1) and result in the calculation of the miriimum values for the available NPSil and the NPSil margin.
The required NPSil values were determined from f H applicable pump curves. Ilowever, it should be noted that the required NPSil value used for the calculation of the BSP IB eva.lable margin is a bounding value based on the most limiting BSP impeller.
MINIMUM MINIMUM REQUIRED AVAILABLE MARGIN NPSil (fl 1];0)
NPSil(f1 ll:0j (fUb Q BSP1A 12.5 14.5 2.0 BSPIB 12.5 13.8 1.3 DilP1A 13.5 15 0 1.5 DIIP IB 13.5 14.9 1.4 M UP 1A/lB/lC 34.0 ~240 >200 NRCINFORAfAllONREQUEST:
(3) Specify whether the current design-basis NPSH analysis differs from the most recent analysis reviesced and approved by the NRCfor schich a safety evaluation vras issued.
4 l
U.S. Nuclear Regulatory Commission Attachment 3F0198-12 Page 6 of 9 FPCIMSPONSE:
The current CR-3 design-basis NPSH analysis coes differ from the most recent analysis reviewed and approved by the NRC for which a safety evaluation was issued. References 3,4 and 5 represent the most recent analyses revie ved and approved by the NRC for which a safety evaluation was issued. In addition, Section 6.4.2, " Summary of Post-Accident Recirculation" and Table 6-12, " Post-Accident NPSH Requirements" of the CR-3 FSAR have been revised since the time of the mos: recent SER (Reference 6) to reflect the current NPSH values. Revision 24 to the FSAR will revise Table 6-12 to reflect the most current NPSH values consistent those provided in the FPC response to NRC Information Request (2) above. Details follow regarding the CR-3 licensing basis for the BSPs and the DHPs when in the recirculation mode of operation.
Building Spray Pumps Licensing Basis On July 5,1974, the NRC issued a Safety Evaluation Report to CR-3 (Reference 1).
Section 6.2.2 of the SER, " Containment Heat Removal Systems," states that, "NPSH requirements for the reactor building spray pumps can be met during the post-accident p recirculation phase by throttling pump flow during recirculation from 1500 gpm to 1200 gpm." The SER stated that, "We h .ve reviewed the containment heat removal systems far conformance to the GDC Noa. 38, 39, and 40, and Regulatory Guide 1.1, " Net Positive Suction Head for Emergency Core Cooling and Heat Removal System Pumps" dated November 2,1970. We conclude that the systems meet the requirements of these criteria and are acceptable."
It should be noted that this SER acknraledged that CR-3 was not designed and constructed to the General Design Criteria published in 1971 (10 CFR 50 Appendix A),
stating that, "This facility was designed and constructed to meet the AEC's GDC, as originally proposed in July 1967. The Commission published the revised G" in 1971 just before the FSAR was Fled. We conducted our technical review ag .ae present version of the GDC and we conclude that the plant design acceptably conforms to the current criteria."
Prior to the issuance of the CR-3 SER, the NRC published Regulatory Guide (RG) 1.79, "Preoperational Testing of Emergency Core Cooling f>ystems for Pressurized Water Reactors," (Reference 2) describing an acceptable test program for Emergency Core Cooling Systems (ECCS)in Pressurized Water Reactors (PWR). By letter dated February 11,1976 (Reference 3), in response to specmc NRC questions relative to CR-3 compliance with RG 1.79, FPC submitted a copy of the 13abcock & Wilcox Line Loss Calculations for Reactor Building Spray and Decay Heat Removal Pump Suction Piping During the Recirculation Mode from the Reactor Building Sump.
In addition, on October 11,1976 (Reference 4), FPC submitted a copy of the report 3
entitled, " Evaluation of Calculated System Head Losses and Reactor Bui: ding Sump Test ,
l
U.S. Nuclear Regulatory Commission Attachment 3F0198-12 Page 7 of 9 System liead Losses Relative to Crystal River Unit No. 3." This report presented the results of a design review and evaluation performed to compare the calculated fluid frictionallosses with the reactor building sump flow test data relative to the DHP and BSP suction systems from the building sump at CR-3.
As documented in Reference 5, "FPC made modifications to the Reactor Building Spray System to preclude a runout condition on the containment spray pumps or to prevent exceeding the margin available for net positive suction head to the pumps." In Section 6.2.2 of Supplement No. 3 to the CR-3 SER (Reference 6), the NRC concluded that, based on the review of the FPC modifications to the reactor building spray system and the results of the preoperational tests, the modifications will preclude pump runout conditions and will prevent exceeding the margin available for net positive suction head and are, therefore, acceptable.
In Reference 7, the NRC Integrated Performance Assessment Process (IPAP) inspection team concluded that, "the cavitation free operation of the building spray pump IB during post-LOCA recirculation phase is questionable due to various non-conservative assumptions made in the calculation." The assessment team idemified this issue as Unresolved item UR-96-201-02.
FPC subsequently (Reference 8) stated its plans for addressing the BSP-1B NPSH issue, as well as other design-related issues, prior to restarting the plant from the current forced outage. Reference 8 stated that, "FPC plans to conduct factory testing and/or modify the pump impeller to improve the margin between required and available NPSil" In Reference 9, the NRC confirmed its understanding that FPC would resolve the design issues delineated in Reference 8, including the BSP-1B NPSH issue.
To resolve the BSP-1B NPSH issue, FPC sent all four BSP impellers (including 2 spares) to the pump vendor where a modi 6 cation to the impellers was performed. Post modification testing demonstrated acceptable results of a reduction in the required NPSH, with no impact on head capacity performance. The post modification margin for the BSPs, when taking a suction from the RB sump, is as identified in the response to NRC Information Request (2) above.
Decay IIcat Pumps Licensing Basis On July 5,1974, the NRC issued a Safety Evaluation Report to CR-3 (Reference 2).
Section 6.3 of the SER, " Emergency Core Cooling Systera (ECCS)," states that, "When a predetermined amount of water in the borated water storage tank has been injected, or-receipt of a low-level alarm for the BWST, suction will be transferred manually to the containment sump for the recirculation mode of operation provided by the LPIS [ Low Pressure Injection System). The ECCS will then provide the long-term core cooling requirements by recirculating the spilled reactor coolant collected in the containment sump back to the reactor vessel through the core flooding line nozzles." The SER concluded ,
I.
U.S. Nuclear Regulatory Commission . Attachment 3F0198-12 Page 8 of 9 ;
4 "that th'e performance of the ECCS is in accordance with the Commission's Interim Acceptance Criteria" for the performance of the ECCS for light-water coaled nuclear power reactors. ,
I Test Description C.3.b of RG 1.79, "Prec serational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors" (Reference 1), includes a description of an -
acceptable recirculation- test for Low Pressure Safety injection (LPSI) Systems that i
, includes the demonstration of the capability to realign valves-and ' injection pumps to :
recirculate from the containment floor or sump into the reactor coolant system. -Test Description C.3.b.(2) of RG 1.79 includes verification that the available net positive suction head for LPSI is greater than that required at accident temperatures.
By letter dated February 11,1976 (Reference 2), in response to specific NRC questions
- relative to CR-3 compliance with RG 1.79, FPC submitted a copy of the Babcock &
Wilcox Line Lors Calculations for Reactor Building Spray and-Decay. Heat Ren oval Pump Suction Piping During the Recirculation Mode from the Reactor Building Sump. In addition, on October 11,1976 (Reference 3), FPC submitted a copy of the report entitled,
" Evaluation of Calculated System Head Losses and Reactor Building Sump Test System Head Losses Relative to Crystal River Unit No. 3." This report presented the results of a
-design review and evaluation performed to compare the calculated fluid frictional losses with the reactor building sump flow test data relative to the DHP and BSP suction systems from the building sump at CR-3.
Section 6.3 of Supplement No. 3 to the CR-3 SER indicated that FPC modified the ECCS to include automatic flow control; err in the discharge of the DHPs to preclude the need
'for the operator to control pump runout which could result in insuflicient NPSH for the pumps. The NRC concluded that, in recognition of the modifications and preoperational tests, the ECCS is in accordance with Appendix K to 10 CFR Part 50, with the exception of the analysis with regard to return to nucleate boiling after critical heat flux conditions have been reached.
NRCINFORMATIONREQUEST:
(4)^ Specify uhether coruainment overpressure (i.e., containment pressure above the mpor pressure of the sump or suppression poolfluid) um credited in the calculation of amilable NPSH. - Specify the amount ofowrpressure neededand the minimum overpressure amilable.
FPCRESPONSE:
. Containment overpressure was not credited in the calculation of the available NPSH at
. CR-3.
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.a , ' ^ -- ., , ..
1
U.S. Nuclear Regulatory Commission
Attachment:
13F0198 l? Page 9 of 9 i
N4CINR)RMA110NREQUEST:
i (3) When containment overpressure is credited in the calculation of available NPSH, conprm that an appropriate containment pressure analysis was done to establish the minimum containmentpressure. ,
. FPC RFSPONSE:
As indicated in FPC response to NRC Information Request (4) above, containme.nt i overpressure was not credited in the calculation of the. available NPSH at CR-3.
Therefore, Information Request (5)is not applicable to CR-3.
i P9FERENCES:
- 1. NRC to FPC letter, 3N0774-01, dated July 5,1974, " Safety Evaluation by the Directorate of.
Licensing"
- 2. Regulatory Guide 1.79, "Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors" i
- 3. FPC to NRC letter,3F0276-06, dated February 11,1976
- 4. FPC to NRC letter,3F1076-03, dated October 11,1976
- 5. FPC to NRC letter,3F1276-07, dated December 10,1976 L
- 6. N AC to FPC letter,3N1276-10, dated December 30,1976, " Supplement No. 3 to the Safety Evaluation Report" 1 7. .NRC to FPC letter, 3N0896-12, dated August 23,1996, " Crystal River Unit 3 Integrated Performance Assessment Process (IPAP) Final Assessment Report"
- 8. . FPC to NRC letter, 3F1096-22,- dated October 28,1996, " Crystal River Unit' 3 Forced Outage" 9l NRC to FPC letter,3N0397-07, dated March 4,1997, " Confirmatory Action Letter" 10.' " Internal Flow Systems," D. S. Miller, Second Edition b
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