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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] |
Text
,
Florida l Power l C'2"L9 .
November 19,1997.
3F1197 48 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 0001
Subject:
Request for Additional Information Related to Emergency Operating Procedures Technical Specifications Change Request tiotice (TSCRN) 210 (TAC No. M93991)
Referances: 1. FPC Letter to NRC (3F0697-10), dated June 14,1997
- 2. NRC Letter to FPC PN1197-04), dated November 4,1997
- 3. FPC Letter to NRC (3F0997 31), dated September 17,1997
Dear Sir:
The enclosure to this letter and attachments comprise Florida Power Corporation's (FPC) response to the request for additional information (RAll contained in Reference 2. These questions pertain to operator actions described in emergency operating procedures (EOPs) involving mitigation of certain small break Loss of Coolant Accident (LOCA! scenarios.
In addition to the information requested in Reference 2, FPC's notes from the October 22, 1997 meeting-in Rockville, Maryland indicate that the NRC staff is interested in FPC's position regarding the assessment required to be performed of completed EOPs to determine the need int additional operator 1:aining and/or simulator validations. Also, the staff requested er'
- a -I simulator validation information relative to the subject operator actions. This info. .on is included in our enclosed responae and the attachments.
Two new regulatory commitments are established by this letter and are reflected in Attachment O. Please contact Mr. David F. Kunsemiller, Manager, Nuclear Licensing at (352)563-4566 if you have any questions.
Sincerely, g b
Charles G. Pardoa
%dlce \
g \
Ye-N Director, Nuclee.r Plant Operations CGP/TWC Attachments cc: Regional Administrator, Region 11 Senior Resident inspector lM]ll$ll$${ll,l!}l r . o M nNRR Project Manaaer _
9711210186 971119 PDR ADOCK 05000302 P PDR t,MYul AL MIVhN ENERGY COMPLEX: 15760 W. Power Line street . Crystal River, Florida 34428-6708 . (352)795-6486 A Florida Progress Company
2 U.S. Nucitar Regulatory Commissi:n Enclosure -
' 3F1197 48 Page 1 of 2
-1 REQUEST FOR ADDITIONAL IN, ARMATION 1 EMERGENCY OPERATING PROCEDURES
' 1.- ' FPC stated that high pressure injection (HPI) flow throttling would be used when in recirculation mode (low-pressure injection taking suction from containment sump and feeding HPl pumps). -The staff questioned whether FPC has been approved to use flow throttling ano requested that FPC provide a reference to the staff's approval for the use of flow throttling.
FPC Resoonst:
In response to the NRC Confirmatory Order for Crystal River Unit 3 dated April 14, 1980, FPC letter to NRC dated May 23,1980 submitted HPl usage guidelines for small break or overcooling transients. FPC's submittat discusses added flexibility for HPl throttling to lessen th ; possibility for reactor coolant system (RCS) overfill.
NRC letter to FPC dated November 16,1381 refers to FPC letter dated May 23, 1980 and recognizes the use of HPl throttling above the low pressure engineered safety feature actuation system (ESFAS) setpoint if there is adequate subcooling.
- 2. The staff rcquested all the applicable EOP steps for all the operator actions required for the small break LOCA scenarios included in the submittal.
FPC Response:
/sttachments A and B of this submittal are updated tables 3A and 3B of Attachment F from the TSCRN 210 submittal (Reference 1) with the corresponding steps that appear in Crystal River's emergency operating procedures (EOPs) for the operator actions required for mitigation of small break LOCA scenarios. Attachment C is a matrix of the results of two simulator runs performed on November 7 and November 12,1997 which encompass a majority of the required operator actions for TSCRN
- 210. Additional simuletor runa are expected to be performed during the second week of NRC :nspection 97-12 to be conducted the week of December 8,1997.
Results will be availablu for NRC staff review if necessary.
- 3. The staff requested that FPC submit a p<oposed final version of the EOPs applicable to TSCRN 210 to ensure the staff's approval of the opeator actions are based on EOPs that will be in place at restart.
FPC ReSAQnst:
Copies of EOPs used in the mitigation of small break LOCAs are provided as Attachments D through N of this submittal. EOP 2, EOP-3, EOP-4, EOP 13, and EOP-14, Enclosures 2,7,11,17,18 and 19 are proposed final versions. EOP-8 is
- being final: zed. The proposed final version will be provided no later than November 26,1997.
U.S. Nucirr R:gulatory Commission Enclosura .
; 3F1197 48 Page 2 of 2 Also, ouring the October 22,1997 meeting described in Reference 2, the NRC staff was interested in FPC's position regarding the need for any additional training required to be performed on the final versions of EOPs. " Draft" versions o, the procedure revisions were provided for the NRC staff's review in Reference 3.: The proposed final versions, attached, and' draft versions previously provided, are essentially the same as the draf t versions used for operator training and annual
- exams. The procedures are at the point in the completion process which involves - "
review by the Plant Review Committee (PRC). When all EOPs are in their final form -
)
(i.e., have PRC review and are ready for issuance), meetings will be held with representatives of FPC operations, training and the EOP group staffs. The differences between the "as trained" eind "as issued" versions for each procedure will be identifivi, and a training assessment performed. The purpose of the.
assessment will be to identify any additional training needs, the appropriate , setting for the training (classroom, simulator, classroom and simulator, or an Operations Study Book entry), the rieed for additional evaluations and whether or not the training is required. Based on the results of the assessment, training will be developed and conducted prior to restart (Mode 4).
- . 1.ist of Attachments Attachment A - Table of Operator Actions Less Than 20 Minutes Attachment B - Table of Operator Actions After 20 Minutes Attachment C - Simulator Validations Attachment D - EOP 2, " Vital System Status Verification," Revision 4 Attachment E EOP 3, " inadequate Subcooling Margin," Revision 5 Attachment F - EOP-4, " inadequate Heat Transfer," Revision 4 Attachment G - EOP-8, "LOCA Cooldown," Revision 5(P)
Attachment H - EOP-13, " Rules," Revision 3 Attachment I - EOP 14, Enclosure 2, "PPO Post Event Actions," Revision 2 Attachment J - EOP-14, Enclosure 7, "EFP 2 Management," Revision 2 Attachment K - EOP-14, Enclosure 11, "EDG A Load Management," Revision 2 Attachment L - EOP-14, Enclosure 17, " Control Complex Emergency Ventilation," Rev. 2 Attachment M - EOP-14, Enclosure 18, " Control Complex Chiller Startup," Revision 2 Attachment N - EOP-14, Enclosure 19, ."ECCS Suction Transfer," Revision 2 Attachment O - List of Ramlatory Commitments
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4 U.S. Nuc!scr Regulatory Commission Attachment A'-
3F1197-48 . Page 2 Table 3A Operator Actions Less Than 20 Minutes OA Operator Action Time ' Basis Prior NRC Reference
, Reviews 4 leolate RCP sealinjecbon (USQ6) 20 rrunutes Required to No FPC letter to NRC dated 2/28/79, answers a prevous maximize HPI question of whether or not it was necessary to isolate I flow to reactor - any flow paths in the makeup system after a LOCA_- -
(As a contingency acDon, if power is lost to FPC refers to RCP seal injecteon and normal makeup i MUV-27 (normal makeup) and MUV-18 (RCP and refers to a Gilbert Associates report that .
seal injection), transfer to an energized bus condudes adequate HPl flow is achieved without I i
and close valves) these knes isorated. NRC letter to hcensees with .- ~
B&W desgned systems (Genenc Letter 8&OS) dated 5/29/86 states the cooling water sources supportog
, the RCP with the potential of being isolated are seat injechon seal bleedoff, component coohrq water to '
seal Ime coolers, and h w mni cooling water to RCP motors and oil coolers The need to isolate !
RCP Seal Injection was discovered in 1995 to be q necessary due to descovery that operators relied on - ;
non-Peg Guide 1.97 instrumentation to measure this ]
flow when determerung HPI pump ruruut flow limits' ;
(see LER 95-026). Seal injechon isolation was also ;- .i determmed necessary du.ing Refuel 10 in.1996 upon discovery that worst case instrument error may result ;
in inadequate HPl flow (see LER 96-006). FPC letter H dated July 7.1997 (NOV 96-07) descusses the add.tional need for closure of RCP seal controlled ,
bleed +ff (CBO) valves after 90 seconds if seal 'I injection has not been restored. See OA-2." I I
See EOP- 3 Step 3.8
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U.S. Nuclear Regulatory Commission Attachment A Page 3 3F1197-48 Table 3A Operator Actions Less Than 20 Minutes Operator Action Time Basis Prior NRC Reference OA Review 5 Ensure adequate HPl flow (USQ6)(rsotate a 20 rrunutes Required only Partial FPC letter to NT dated 10/27/89 states HPI must be broken enjectron fine using new isolation for break in HP1 successfu!!y balanced to support SBLOCA rnedgaton line as described in various B&W topical reports accepted cnteria) by NRC. Subsequent FPC letter dated 10/31/89 states that mittgaton strategy employed from the late 1970's through the reviews done in response to NUREG 0737 reled on balancing HPI flow for breaks in HPl injecten lines. These letters relate to LER 89-037, issued in November 1989 reporting a design basis condition in which instrumentation used for balancing HPl flow was inadequate. NRC letter dated 12/20/89 confirmed verbal concurrence to resume power operabon with the HPl instrumentaton problems One condition was operator acton for HPI '
flow balancing. NRC letter dated 2/17/95 from Gary Holahan to Ed Jacks (BWOG Operator Support Committee) states staff has completed its rev% of BWOG response to NUREG 0737 ftem I.C.1 regarding EOP Guidelines and is finalizing an SER on the topic. Balancing HPI fic*s was a past of the ATOG/TBD guidelines irwipviatw! into FPC procedures. FPC issued LER 96-007 on 3/15/96 to report another design basis conditson involving HPl fbw instrumentation. The flow deficiencies desenbed therein were addressed by revised SBLOCA analyses provided by F~amatome Technologies in April 1996 which required ' solation of the affected HPI line versus balancing. Most recent FTI analyses have provided new isolaton cnteria.
See EOP - 3. Step 3.6
U.S. Nuclear Regulatory Commission Attachment A 3F1197-48 Page 4 Table 3A Operator Actions Less Than 20 Minutes OA Operator Action Time Basis Prior NRC Reference Review 6 Ensure adequate EFW flow (USOS) 20 msnutes Rarse OTSG Yes B&W (Taylor) letter to NRC (Baer) dated 5/1/78 levels to ISCM provides topical report 10104, "B&Ws ECCS (EFIC was inrtiated in OA2; therefore, setpoint (90%) Evaluation Model," which notes operator acbon is ensuring EFW flow is a confirmation step only) necessary during early stages of the accident to mitigate consequences and meet 10 CFR 50.46.
This step manually raises OTSG levels to the Auxiliary feedwater is assumed to be available. NRC Inadequate Subcooling Margin, ISCM level letter to FPC dated 7Ait79 provxles a SER for actions taken in respmse to Commission Order dated 5/16/79. The SER states that a generic review of B&W analyses entitled "Evaluatson of Trar.sient Behavior r; Small RCS Breaks in the 177 Fuel Assembly Plant" resu!!ed in a principle finding that reconfirms SBLOCA analyses demonstrate a combination of heat removal by the steam generator O.7d the HP1 system combined with operator actxm to er'sure adequate core cooling. These results are applicable to CR-3 considering the ability to manua:ty start the .edundant EFW pumps and HPI pumps from the control room, assummg failure of automatic EFW actuabon. NRC letter to FPC dated 8/30/85 provides a SER for NUREG 0737 item li.K.3.30,"SBLOCA Methods." Sechon Ill.5.a of the SER states "the timing of operator action to raise the secondary system water level to 95% was found not to be entical_"
See EOP - 3. Step 3.9
U.S. Nucl=:r Regulatory Commission Attachment 8 -
3F1197-48 Page 1 Table 3B Operator Actions A*ter 20 Minutes OA Operator Action Failure Cycle 11 Only Basis Reference Scenario 7 Ensure Control Complex Ventilatm is running in LOBA No To assure control room EOP - 3, Step 3.12 requires concurrent emergency mode LOBB operator dose is not exceeded pakin.ance of EOP 14. Enclosure 17 EFP-2 and to provide control complex " Control Complex Emergency Venidata cooling Required to be Sys,em.*
accomplished within 30 minutes 8 If at any time BWST is < 20 ft, transfer ECCS pump LOBA No To ensure sufficent source of EOP - 3. Step 3.13 directs pc,b n e w suction to RB sump LOBB borated water for injecbon by of EOP - 14. Enclosure 19 *ECCS EFP-2 HPl!LPl. Depending on break Suctm Transfer.*
size, action may be required between 25 minutes and 1-1/2 hours 9 If 'B' DC power is lost, crosstie EFP-2 to A train (EFV-12) LOBB EFP-1 can only provide flow EOP - 3. Step 3.16 directs performance Yes for a specfic time penod, then of EOP-14. Enc;osure 11, *EDG A Load AND EFP-2 must be aligned to Management,* (Steps 11.6 and 11.7) ensure sufficient margin is Secure EFP-1 maintained on the 'A' EDG for later adding of Control Cor '. dex Chiller 10 Put EFIC in manual permissive LOBB Yes Required to prevent cychng of EOP - 3. Step 3.9 estabhshes the limited duty motors on the apphcability of EOP - 13. Rule 3, *EFW AND EFW block valves Control.* Also EOP - 3. Step 3.16 directs performance of EOP - 14 Close EFW block valves (deenergized after dosure) Enclosure 11, *EDG A Load Management
- Step 11.4 requires the normal EFP-2 discharge path to be isolated 11 Manage EDG load in order to extend EFP-1 operatton by EF P-2 Yes Defense in Depth action for EOP - 3. Step 3.16 and EOP - 8 Step postulated single failure of the 3.7 direct performance of EOP-14,
. Shutdown SWP-1 A & RWP-2A after venfying loss of EFP-2. These actions Enclosure 11,*EDG A Load redundant pumps are operating and plachg extend the time EFP-1 is Management * (Steps 11.12,11.13 switches in Pull-to-Lock to prevent reactuation of available for OTSG cooling 11.14).
pumps (EDG loading) e Place EFP-1 Trip Defeat Switch in defeat position to prevent automatic trip of EFP-1 on RCS pressure of !
500 psig
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U.S. Nucl::ar Regulatory Commis>. n Attachment B 3F1197-48 ' Page 2 Tatde 3B Operator Actions After 20 Minutes OA Operator Action Failure Cycle 11 Only Basis Reference Scenario 12 Venfy Control Complex Chdier is runrung LOBA No Required within 80 rrunutes to EOP - 3. Step 3.17 and EOP - 8. Step LOBB ensure contros complex 3.8 provide instruebons to concurrently EFP-2 instrumm.id.06 remains within perform EOP - 14. Endosure 18.
analyzed temperature ranges
- Control Complex Chiller Startup" i for instrument accuracy 13 Isolate the R83 sump by placing RB sump pumps in Pull- LOBA No Required to isolate unneeded EOP - 8. Steps 3.11 and 3.12 to-Lock, dosing RB sump pump discharge valves, and LOBB penetration flow paths. These
, dosing waste gas header isolation valves EFP-2 penetrations go to the waste '
gas header and the ,
Miscellaneous Waste Storage tank. Isolating the RB sump
- penetratic i will maintain i inventory in the containment j for possible ECCS pump ;
suchon for long term recirculation 14 If only EFP-2 is supplying feedwater to the OTSG, the LCBA No To maintain EFP-2 as an EOP - 8. Step 3.17 directs use of EOP-RCS cooldown will be stopped prior to reaching an EFP- available rwrce of feedwater 14. Endosure 7.*EFP-2 Management *:
2 operationallimit. Manage operation of EFP-2 by and opera.o the pump within - (see Steps 7.14, 7.15. and 7.16) dosing ASV-5 and ASV-204 on low OTSG pressure analyzed regions. Use of This may involve entry into EOP-4 and (Cyde EFW) and restart EFP-2 when pressure FWP-7 provides additional retum to EOP - 8.'
increases. resources available to operators during a LOOP (Mitigation strategy indudes operation of diesel backed FWP-7 as a Defense in Depth actnn. Isolation valves located in the interme 1iate building may be opened to allow use of FWP-7) 15 If EFP-2 is not operating when in a LOOP condition with EFP-2 Yes if EFP-2 is not available, steps EOP - 3. Step 3.16 derects psium.-6c.e inadequate subcooling. limit cooldown prior to EFP- must be taken to ensure EFP- of EOP- 14. Enclosure 11 *EDG A Load 1/LPl. 1 operates as long as needed Management * (see Step 11.14) 16 Establish RCS Cooldown using TBVs or ADVs LOBA No initiates RCS cooldown to EOP - 8. Steps 3.18 and 3.19.
LOBB achieve end point of event EFP-2 (start of decay heat) t
I' U.S. Nuclear 'Regulatory Commis ion - ' Attachment' O 3F1197-48 Page 3 Tatde 38 -
Operator Actions After 20 Minutes ' ,
OA Operator Acton Failure Cycle 11 Only . Basis - Reference Scenario 17 Penodscally re-evaluate HPI Inne break cntena on RCS LOBA No Requwed for spec.3c HPI kne . EOP-3, Step 3.22 transabons to EOP-recessurization LOBB~ pinch areas to ensure a 4 on inadequate heat transfer. EOP -4,'
' EFP-2 broken line will be isolated if .' Step 3.58 is an *1f at any time' step and ~
isolabon cntena is not met requwes closure of the affected HPt lins !
early in the event while in - on ISCM EOP-3 h,
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U.S. Nuciser R:gulatory Commission Attachment C 3F1197-48 Page 1
~
Simulator Validations '
OA# ACTION EOP1 STEP REQUIRED TIME VALIDATED TIME ' VALIDATED TIREE Scenario 88 Scenario 111 hr: min:sec tr. min:sec 1 TRIP RCPS < 2 MIN. COP-3 STEP 2.1 < 2 MNUTES 00:00:23 00:00:20 2 MANUAL HPL'RBBC EOP-13 RULE 1 < 10 MNUTES 00:00:42 00:01:39 3 ENSURE 4 HPl VALVES OPEN EOP-3 STEP 3.3 < 10 MINUTES C0:02:57. - 00:02:56 4' ISOLATE RCP SEAL INJECTION EOP-3 STEP 3.8 < 20 MINUTES 00:08:37 00:08:51
! 5 ISOLATE BROKEN HPI LINE EOP-3 STEP 3.6 < 20 MINUTES 00:07:12 00:07:34 6 ENSL9E EFIC ACTUATES EOP-3 STEP 3.10 < 20 WNUTES 00:09:05 00:09:32 7 START CONTROL COMPLEX EOP-3 STEP 3.12 DIRECTS USE OF EOP- < 30 MNUTES - 00:22:44 00:22:00 VENTILATION 14. ENCLOSURE 17 8 TRANSFER BWST TO RB SUMP EOP-3 GTEP 3.13 DIRECTS USE OF EOP- >20 WNUTES Not validated by this Discontmuod 14, ENCLOSURE 19 scenario due to size sceneno at 02:12-00 +
, of break with BWST >40 ft :
9 CROSS TIE EFP-2 TO A-TRAIN AND EOP-3 STEP 3.16 DIRECTS USE OF EOP- > 20 MINUTES 00:32:57 N/A for this scenario SECURE EFP-1 14. ENCLOSURE 11 (STEP 11.7) f 10 PLACE EFIC IN MANUAL PERMISSIVE EOP-3 STEP 3.16 DIRECTS USE OF EOP- > 20 MNUTES 00:32:57 ' N/A for this scenario AND CLOSE EFW BLOCK VALVES 14 ENCLOSURE 11 (STEP 11.4) 11 MANAGE EDG LOADS: EOP-3 STEP 3.16 DIRECTS USE OF EOP- > 20 MMUTES . N/A for this scenano 00:29:49 S/D SWP-1 A & RWP-2A 14, ENCLOSURE 11 EFP-1 TRIP DEFEAT (STEP 11.12;11.13;11.14) 12 START CONTROL COMPLEX CHILLER EOP-3 STEP 3.17 DIRECTS USE OF EOP- < 80 MNUTES 00:47:12 00:42:32 14 ENCLOSURE 18 .
13 STOP RB SUMP PUMPS EOP-8 STEP 3.11:3.12 > 20 MINUTES Not validated by this 00:45:37 .
14 IF ONLY EFP-2 IS AVAILABLE THEN EOP-8 STEP 3.17 DIRECTS USE OF > 20 MINUTES Not validated by this N/A for this scenano STOP COOLDOWN BEFORE REACHING EOP-14, ENCLOSURE 7 (STEP 7.16) scenario
- OPERATIONAL LIMIT OF EFP-2
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U.S. Nuclear Regulotory Commission : Attachment C 3F1197 ' L Page 2
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Sunulator Validations .
OA# ACTION EOPISTEP- REQUIRED TIRIE - VAUDATED TIINE . VAUDATED TIRE Scenado SS Scenedo 111 hr min:sec ' ' hr:miresec !
15 IF EFP-2 IS NOT OPERATING, Uts!T EOP.3 STEP 3.15,IN CONJUNCTION WITH >20RAINUTES Not validated try Weis intadock was .
COOLDOWN PRIOR TO EFP-1/LPI EOP-14. ENCLOSURE 11,IS A PERFORGE scenerlo defeated 00:29:14 INTERLOCK STEP WHICH ROUST BE COREPLETED tesfore cooldown was i PRIOR TO PROCEEDING TO COOLDOWN iratiated ,
GUIDANCE IN EOP4.
16 : ESTABUSH COOLDOWN USING TBVs EOP4 STEP 3.18,3.19 >20 ANNUTES Not vm tpy this 00:50:03 AND ADVs scenario l 17 PERIODICALLY RE-EVALUATE HPl UNE EOP-4 STEP 3.58 >20 REINUTES Not validated try this . Not validated try this BREAK ISOLATION CRITERIA ON RCS scenario '
scenerlo REPRESSURIZATION ,
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, Validated 1117197 with one operator at the controls and one operator reading the procedures. "
EOP.03, Draft R was used.. -
Scenario ended when EOP4 was entered.
Scenario 88 was used (SBLOCA & Loss of 'B' DC Bus).
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Validated 11112/97 with one operator at the controls and one operator reading the procedures. =
EOP43, Draft R and EOP48, Draft P were used.
Scenario ended at 2 hours,12 minutes at EOP4, Step 3.35 - RCS pressure g 650 psig. ,
Scenario 111 was used (SBLOCA & EFP-2 Failure).
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