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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F9941999-10-15015 October 1999 Discusses FPC 970819 Request for Temporary Relief from ASME Code Section XI Requirements to Repair ASME Class 3 Nuclear Service & Decay Heat Sea Water System Piping.Forwards SE Containing Results of Staff Review ML20217J5171999-10-13013 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Plant,Unit 3 & Did Not Identify Any New Areas That Warranted More than Core Insp Program.Previously Planned Regional Initiative Insp of safety-related Mod Will Be Performed 3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999 Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed 3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999 Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made ML20212L0771999-10-0404 October 1999 Forwards SER Accepting Licensee Relief Requests 98-012 Through 98-018 Involving Containment Insps at Crystal River Unit 3 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(a)(3)(ii) ML20217D6551999-10-0101 October 1999 Requests That Natl Communication Sys Arrange for Licensee Participation in Government Emergency Telecommunications Service,Per NRC Info Notice 99-025 ML20212J8481999-10-0101 October 1999 Forwards Safety Evaluation Re Second 10 Yr Interval ISI Program Requests for Relief 98-009-II.Reliefs Granted for 98-009-II,Parts B & C & 98-010-II & 98-011-II 3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999 Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment 3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999 Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331 ML20212F7251999-09-23023 September 1999 Discusses Staff Review of Util 980330 Response,As Suppl on 990514,to GL 97-06, Degradation of SG Internals. Staff Concludes That Licensee Responses to GL Provide Reasonable Assurance That Condition of SG Internals Acceptable ML20212F7331999-09-23023 September 1999 Discusses Util Licensing Action for GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants. NRC Ack Efforts Util Completed to Date in Preparing Crystal River,Unit 3 for Y2K Transition 3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999 Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46 ML20212E6741999-09-21021 September 1999 Forwards Safety Evaluation Accepting Proposed EAL Changes Submitted by ,As Supplemented by 981120,990713 & 0831 Ltrs,Incorporating Guidance in NUMARC/NESP-007,Rev 2, Methodology for Development of Eals 3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999 Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv) 3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999 Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief ML20212F3141999-09-13013 September 1999 Forwards Insp Rept 50-302/99-05 on 990704-0814.Violations Noted,But Being Treated as non-cited Violations ML20211L9081999-09-0303 September 1999 Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Crystal River Unit 3 ML20211Q7581999-09-0101 September 1999 Forwards Summary of 990812-13 Training Managers Conference in Atlanta,Georgia Re Recent Changes to Operator Licensing Program.List Conference Attendees,Copy of Presentation Slides & List of Participant Questions Encl 3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999 Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals ML20211G7111999-08-30030 August 1999 Modifies Approval of 980521 Request for Exception to 10CFR50.4(b)(6) & Grants Util Approval to Submit Copies of Future Updates to FSAR as Listed ML20211G7031999-08-30030 August 1999 Informs of Approval of Util 980521 Request for Exception to 10CFR50.4(b)(6),allowing Util to Submit Updates to Plant Ufsar.Ltr Modifies That Approval & Grants Util Approval 3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999 Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002 ML20212C1351999-08-27027 August 1999 Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input 3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999 Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71 3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999 Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3 3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999 Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05 3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999 Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal 3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999 Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2 3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value 05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999 Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented ML20210Q4511999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 ML20210P0741999-08-0505 August 1999 Forwards SE Accepting Licensee 980416 & 1130 Ltrs Re Third 10-year Interval ISI Program Plan & Associated Requests for Relief for Plant,Unit 3 3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999 Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603 ML20210G8551999-07-27027 July 1999 Forwards Insp Rept 50-302/99-04 on 990523-0703.One Violation Identified & Being Treated as Noncited Violation 3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999 Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments ML20209H5211999-07-16016 July 1999 Forwards Request for Addl Info Re Licensee Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in CR-3 once-through Steam Generators in Order to Complete Review ML20209G3231999-07-15015 July 1999 Forwards Biological Opinion Issued by Natl Marine Fisheries (NMFS) of Dept of Commerce.Nmfs Concluded That Operation of Cw Intake Sys of Crystal River Not Likely to Jeopardize Existence of Species Listed in Biological Opinion ML20209G3481999-07-15015 July 1999 Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon 3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999 Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl 3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999 Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl 3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999 Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl 3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999 Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held 3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21 3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21 ML20196L1261999-07-0707 July 1999 Discusses Closeout of TAC MA0538 Re License Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Unit 3 3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999 Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3 ML20196J4991999-07-0101 July 1999 Advises That Info Contained in ,Which Included TR BAW-2346P,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20209C0811999-06-25025 June 1999 Forwards Overdue Controlled Document Transmittals for Listed Documents 3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999 Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl 1999-09-03
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999 Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed 3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999 Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made 3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999 Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment 3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999 Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331 3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999 Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46 3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999 Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv) 3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999 Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief 3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999 Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals ML20212C1351999-08-27027 August 1999 Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input 3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999 Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002 3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999 Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71 3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999 Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3 3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999 Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal 3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999 Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05 3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999 Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2 05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999 Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented 3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value 3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999 Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603 3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999 Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments ML20209G3481999-07-15015 July 1999 Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon 3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999 Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl 3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999 Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl 3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999 Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl 3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999 Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held 3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21 3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21 3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999 Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3 ML20209C0811999-06-25025 June 1999 Forwards Overdue Controlled Document Transmittals for Listed Documents 3F0699-12, Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested1999-06-23023 June 1999 Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested 3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999 Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl 3F0699-08, Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments1999-06-21021 June 1999 Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments 3F0699-09, Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl1999-06-0404 June 1999 Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl 3F0599-21, Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads1999-05-28028 May 1999 Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads 3F0599-10, Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl1999-05-26026 May 1999 Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl ML20207E4341999-05-25025 May 1999 Submits 30-day Written Rept on Significant PCT Changes in ECCS Analysis for ANO-1.CRAFT2 Limiting PCT for ANO-1 Was Bounded by 1859 F PCT Calculated at 2568 Mwt for Crystal River 3 Cold Leg Pump Discharge Break Size of 0.125 Ft 3F0599-22, Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs1999-05-21021 May 1999 Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs 3F0599-18, Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM1999-05-14014 May 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM 3F0599-17, Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments1999-05-14014 May 1999 Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments 3F0599-07, Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 19781999-05-14014 May 1999 Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 1978 3F0599-03, Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR1999-05-12012 May 1999 Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR 3F0599-05, Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl1999-05-12012 May 1999 Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl 3F0599-08, Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments1999-05-0303 May 1999 Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments 3F0599-09, Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 19981999-05-0101 May 1999 Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 1998 3F0499-24, Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent1999-04-30030 April 1999 Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent 3F0499-09, Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 9907301999-04-30030 April 1999 Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 990730 3F0499-23, Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements1999-04-23023 April 1999 Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements 3F0499-18, Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl1999-04-20020 April 1999 Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl 3F0499-05, Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin1999-04-16016 April 1999 Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin 3F0499-08, Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 19981999-04-16016 April 1999 Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 1998 1999-09-27
[Table view] Category:UTILITY TO NRC
MONTHYEAR3F0990-11, Forwards Final Status Update Re Design & Operations Verification for Instrument Air Sys Per Generic Ltr 88-141990-09-20020 September 1990 Forwards Final Status Update Re Design & Operations Verification for Instrument Air Sys Per Generic Ltr 88-14 3F0990-05, Forwards 1990 Inservice Insp Summary Rept. Rept Contains Owners Data Rept,Data Summary Sections for Class 1,2 & 3 Components,Rept for Repair & Replacements & Listing of Exams1990-09-14014 September 1990 Forwards 1990 Inservice Insp Summary Rept. Rept Contains Owners Data Rept,Data Summary Sections for Class 1,2 & 3 Components,Rept for Repair & Replacements & Listing of Exams 3F0990-08, Forwards Response to Violations Noted in Insp Rept 50-302/90-23.Corrective Actions:Training Session Conducted to Stress Importance of Attachments Being Part of Work Package When Required by Procedure1990-09-13013 September 1990 Forwards Response to Violations Noted in Insp Rept 50-302/90-23.Corrective Actions:Training Session Conducted to Stress Importance of Attachments Being Part of Work Package When Required by Procedure 3F0890-23, Discusses Decommissioning Financial Assurance Rept Dtd 900726.Amount Util Collecting Exceeds Amount Necessary Based on NRC Formula & Does Not Include Estimated Cost of Removal & Disposal of Nonradioactive Structures & Matls1990-08-30030 August 1990 Discusses Decommissioning Financial Assurance Rept Dtd 900726.Amount Util Collecting Exceeds Amount Necessary Based on NRC Formula & Does Not Include Estimated Cost of Removal & Disposal of Nonradioactive Structures & Matls ML20028G8251990-08-29029 August 1990 Advises That Supplemental Response to Insp Rept 50-302/89-18 Will Be Submitted by 901030 ML20059G1721990-08-24024 August 1990 Submits Info Re Change in Operator License Status.Re Rawls & Wa Stephenson Senior Reactor Licenses Should Be Terminated, Effective 900817 Due to Reassignment from Position Requiring Licenses 3F0890-15, Forwards Fitness for Duty Program Performance Data for Period of Jan-Jun 19901990-08-23023 August 1990 Forwards Fitness for Duty Program Performance Data for Period of Jan-Jun 1990 3F0890-21, Forwards Semiannual Radioactive Release Rept Jan-June 1990 for Crystal River Unit 3 & Rev 15 to Crystal River Unit 3 Odcm1990-08-23023 August 1990 Forwards Semiannual Radioactive Release Rept Jan-June 1990 for Crystal River Unit 3 & Rev 15 to Crystal River Unit 3 Odcm ML20059A0031990-08-16016 August 1990 Responds to NRC 900613 Request for Addl Info Re Util 871222 Response to Violations Noted in Insp Rept 50-302/87-30 3F0890-03, Forwards Rev 11 to Inservice Insp - Pump & Valve Program, Crystal River Unit 31990-08-16016 August 1990 Forwards Rev 11 to Inservice Insp - Pump & Valve Program, Crystal River Unit 3 3F0890-10, Advises That Util Completed Mods to Comply w/10CFR50.62 Requirements Re Reduction of Risk from ATWS Events1990-08-16016 August 1990 Advises That Util Completed Mods to Comply w/10CFR50.62 Requirements Re Reduction of Risk from ATWS Events 3F0890-05, Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 1741990-08-10010 August 1990 Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 174 ML20058L2001990-08-0202 August 1990 Provides Current Status of Reg Guide 1.97 Activities. Pressurizer Heater Status & Main Steam Safety/Relief Valve Position Indications Completed 3F0790-10, Forwards Justification for Continued Operation Re Emergency Diesel Generator Block Loading Voltage Dips.Util Will Install Higher Accuracy Relays to Improve on Accuracy & Repeatability of Load Intervals1990-07-18018 July 1990 Forwards Justification for Continued Operation Re Emergency Diesel Generator Block Loading Voltage Dips.Util Will Install Higher Accuracy Relays to Improve on Accuracy & Repeatability of Load Intervals 3F0790-06, Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-81990-07-12012 July 1990 Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-8 ML20055D5561990-06-29029 June 1990 Forwards 890505 & s to Be Placed in Plant File 3F0690-15, Informs That Tech Spec Actions Identified in Util Addressed as Part of Tech Spec Improvement Program,Per 900518 Request for Programmed Enhancements for Generic Ltr 88-171990-06-29029 June 1990 Informs That Tech Spec Actions Identified in Util Addressed as Part of Tech Spec Improvement Program,Per 900518 Request for Programmed Enhancements for Generic Ltr 88-17 3F0690-22, Forwards Annual Financial Repts for 1989 for Orlando Utils Commission & Cities of Bushnell,Leesburg,Ocala & Tallahassee,Per 10CFR50.71(b)1990-06-27027 June 1990 Forwards Annual Financial Repts for 1989 for Orlando Utils Commission & Cities of Bushnell,Leesburg,Ocala & Tallahassee,Per 10CFR50.71(b) 3F0690-19, Responds to Deviations Noted in Insp Rept 50-302/90-15. Corrective Actions:All Reg Guide 1.97 Category 1 Instruments on Main Control Board Marked & Engineered Safeguards Matrix Indicating Lights Arranged in Unique Array1990-06-25025 June 1990 Responds to Deviations Noted in Insp Rept 50-302/90-15. Corrective Actions:All Reg Guide 1.97 Category 1 Instruments on Main Control Board Marked & Engineered Safeguards Matrix Indicating Lights Arranged in Unique Array ML20043H5781990-06-21021 June 1990 Responds to Generic Ltr 89-06, Spds. All Open Issues Identified in NRC SER & Plant SPDS Satisfies NUREG-0737, Item I.D.2 & Suppl 1 ML20044A6121990-06-21021 June 1990 Forwards Payment of Civil Penalty,Per NRC 900524 Order Based on Findings in Insp Rept 50-302/89-09 ML20043J0221990-06-21021 June 1990 Submits Info in Support of Tech Spec Change Request 175,Rev 1,Suppl 1 Re Spent Fuel Pool Storage Capacity at Plant ML20043H4151990-06-21021 June 1990 Forwards Response to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. 3F0690-18, Responds to Violations Noted in Insp Rept 50-302/90-09. Corrective Action:Temporary Lettering Placed on Index Plates for Consistency W/Previous Markings Immediately Following Discovery of Error1990-06-20020 June 1990 Responds to Violations Noted in Insp Rept 50-302/90-09. Corrective Action:Temporary Lettering Placed on Index Plates for Consistency W/Previous Markings Immediately Following Discovery of Error ML20043H2901990-06-15015 June 1990 Forwards Results of Refuel 7 once-through Steam Generator (OTSG) Eddy Current Insp,Per Tech Spec Section 4.4.5.5.Eight Defective Tubes & Two Administratively Plugged Tubes in OTSG a Resulted from Review of Insp Data ML20044A0641990-06-13013 June 1990 Forwards Rev 5 to Physical Security Plan,Replacing Currently Approved Rev 4 W/Amends.Rev Withheld (Ref 10CFR73.21) ML20043G2271990-06-12012 June 1990 Suppls 900604 Ltr Describing How Control Room Habitability Dose Would Be Adversely Affected by Elimination of Reactor Bldg Flood Vol Unless Overly Conservative Failure Postulations Also Changed.Quarterly Updates to Be Provided ML20043G3711990-06-12012 June 1990 Forwards 1990 Internal Cash Flow Projection for Plant Which Updates Utils Utilization of Alternative (E) ML20043G2361990-06-12012 June 1990 Forwards Info Re Fire Protection Sys Reliability for Providing Water to Intermediate Bldg Following High Energy Line Break.B&W Issued Contract to Verify Mass/Energy Release & Motor Starters & Terminal Blocks Insulated ML20043F1601990-06-0404 June 1990 Provides Supplemental Info on Reactor Bldg Flooding,Per Util 900517 Ltr Describing Resolution Plan Being Pursued.Util Has Limited Vol of Water Contributed by Borated Water Storage Tank & Sodium Hydroxide Tank to Flood Level ML20043C8721990-05-31031 May 1990 Forwards Rev 0 to Crystal River Unit 3 Cycle 8 Core Operating Limits Rept, Per Tech Spec 6.9.1.7 ML20043B8431990-05-24024 May 1990 Describes Alternative Testing of Reactor Bldg Spray Suction Valves BSV-1 & BSV-8,per Generic Ltr 89-04.At Least One Valve Will Be Disassembled & Inspected During Each Refueling Outage Using Alternate Insp Method ML20043B2771990-05-18018 May 1990 Advises of Mod to Original Commitment & Plans to Store Seal Ring in Original Storage Location During Plant Operations, Per 790606 Ltr.Mod Minimizes Personnel Exposure & Enhances Seal Plate Leak Tightness Due to Less Handling ML20043B0321990-05-17017 May 1990 Provides Details of Resolution Util Will Pursue Re Reactor Bldg Flooding Detailed in Encl LER 90-005.Mod Will Be Installed to Add Alarm in Main Control Room to Indicate When Flood Level Reaches Point & Operator Action Begins ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML20042G7681990-05-10010 May 1990 Submits Unsatisfactory Performance Testing Incident Repts, Per 10CFR26, Fitness for Duty. Results of Three Positive Blind Test Samples Certified to Contain No Drugs ML20043A4931990-05-10010 May 1990 Forwards Executed Amend 8 to Indemnity Agreement B-54 ML20042G2101990-05-0707 May 1990 Provides Notice of MW Kirk Permanent Reassignment from Position & Requests Termination of Senior Reactor Operator License 20481-1,effective 900505 ML20042E8611990-04-26026 April 1990 Forwards Annual Financial Repts for Six Participating Owners of Plant ML20012F2941990-03-30030 March 1990 Forwards Nonproprietary Rev to 51-1176431-02, Crystal River 3 Reactor Vessel...Temp Overpressure Protection, in Support of Tech Spec Change Request 174,Suppl 1 Re Response to Generic Ltr 88-11 ML20042D8321990-03-30030 March 1990 Provides Supplemental Response to Station Blackout Rule Implementation & Affirms That Diesel Generator Target Reliability Will Be Maintained ML20012E2041990-03-23023 March 1990 Requests Temporary Waiver of Compliance Granted on Tech Spec 3.9.8.2 Re DHR Power Source Requirements ML20012D9471990-03-21021 March 1990 Requests Approval of Capsule Withdrawal Schedule in Table 3-19 of BAW-1543,Rev 3, Master Integrated Reactor Vessel Surveillance Program to Allow Plant Refuel 7 Outage Plans to Continue on Schedule.Changes Needing NRC Approval Listed ML20012D7371990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47. Util Will Implement Appropriate Sys to Protect Against Overfill Concerns ML20012C4501990-03-13013 March 1990 Forwards Listing of Insurance Policies in Place for Plant as of 900225 ML20012B4821990-03-0707 March 1990 Forwards Inservice Insp Pump & Valve Program Relief Request V-371 Proposing Alternate Acceptance Criteria Requirements for IWP-4150 for Fluctuations in Hydraulic Instrument Readings ML20012B3651990-03-0101 March 1990 Lists Five Addl Drugs Included in 10CFR26 Re fitness-for- Duty Testing Program.Specimens Identified as Positive on Initial Screening Will Be Confirmed Using Gas Chromatography or Mass Spectrometry at Listed cut-off Levels ML20012A4041990-02-27027 February 1990 Forwards 1989 Annual Rept of Personnel Exposure in Accordance w/10CFR20.407 & Tech Spec 6.9.1.5.(a) & Annual Rept of Facility Changes,Tests & Experiments in Accordance w/10CFR50.59 ML20006G1731990-02-23023 February 1990 Advises That Util Voluntarily Agrees to Participate in Emergency Response Data Sys Proposed in Generic Ltr 89-15 ML20011F2411990-02-21021 February 1990 Provides Followup on & Documents Discussion in 900116 Meeting Re Emergency Diesel Generator Loading 1990-09-20
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Power COR PO R Af ION December 23, 1985 3F1285-17 Director of Nuclear Reactor Regulation Attention: Hugh L. Thompson, Jr.
Director, Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Dncket No. 50-302 Operating License No. OPR-72 Licensed Operator Requalification and Replacement Operator Training Programs Additional Information
Dear Sir:
Florida Power Corporation (FPC), with this letter, is responding to the NRC's November 5,1985 request for additional information on FPC's Licensed Operator Requalification and Replacement Operator Training Programs (letter No. 3N1185-05 received 11/12/85). The NRC's request is related to the following specific FPC submittals:
- 1. FPC letter March 15, 1985, (3F0385-12) G. R. Westafer to J. Nelson Grace, re: Licensed Operator Requalification Training Program.
- 2. FPC letter July 23,1985,(3F0785-27) G. R. Westafer to Hugh L.
Thompson, J r. , re: Replacement Operator Trainirg Program Revision.
- 3. FPC letter July 23, 1985, (3F0785-15) G. R. Westafer to llugh L. Thompson, Jr. , re: Licensed Operator Requalification Training Program Commitmant Clarification.
- 4. FPC letter July 23,1985,(3F0785-16) G. R. Westafer to llugh L.
Thompson, J r. , re: Replacement Operator Training Progran; NUREG-0737, Items 1.A.2.1(4) and II.B.4.
8512270296 851223 kg
{DR ADOCK 05000302 PDR \
GEN ERAL OFFICE 3201 Thirty-fourth Street South e P.O. Box 14042, St. Petersburg. Florida 33733 e 813-866-5151
l December 23, 1985 3F1285-17 Page 2
- 5. FPC letter July 23,1985,(3F0785-13) G. R. Westafer to Hugh L.
Thompson, Jr. , re: Instructor Qualifications Clarification.
The following Training Department Procedures (TDP's) are utilized by FPC in responding to the specific queries and are therefore included as references, for information only, with this transmittal.
REFERENCES:
A. TDP-109, Rev 4, Training Records Management B. TDP-112, Rev 0, Training Waivers C. TDP-117, Rev 1, Scheduling and Tracking Training D. TDP-201, Rev 3, Non-Licensed Operator Training Program E. TDP-202, Rev 3, Replacement Operator Training Program F. TDP-203, Rev 4, Licensed Operator Requalification Training Program G. TDP-209, Rev 1, Operations Instructor Qualification Program The attached ADDITIONAL INFORMATION RESPONSE is provided with confidence that the current implementation of the Licensed Operator Requalification Training and Replacement Operator Training Programs meet applicable requirements. We note, that while the NRC's Standard Review Plan, Section 13.2.1, Part II and/or Section 13.2.2, Part II ( Acceptance Criteria), pro-vides review guidance and acceptability criteria, they are not substitutes for Regulatory Guides or Commission Regulations.
$ A W4 Y r G.R. Westafer Manager, Nuclear Operations Licensing and Fuel Management ERC/LCK/GRW/dfs cc: Dr. J. Nelson Grace Regional Administrator Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, NW Atlanta, Ga. 30323
Enclosure:
TDP References A thru G ADDITIONAL INFORMATION RESPONSE J
Enclosure to FPC letter 3F1285-17 Page 1 of 24 ADDITIONAL INFORMATION RESPONSE 1.0 Licensed Operator Requalification Training (March 15, 1985, letter 3F0385-12)
FPC OVERVIEW:
The Licensed Operator Requalification Training Program description was reassembled and submitted per request of Region II (March 15, 1985) and subsequently reincorporated in the FSAR. It is not intended to describe the program to the detail and depth implemented by the Train-ing Department Procedures (TDP's). For this reason, the appropriate TDP and respective part/section number is referenced in our responses to provide additional clarifying information. The referenced TDP's are provided for information only.
__ -)
Enclosure to FPC letter 3F1285-17 Page 2 of 24 NRC QUERY: 1.1 In Section 1 of the Requalification Training Program description, the licensee states that the content of the lecture sessions is based on the audit and annual examinations. - Please provide clarification to address the use of examination results to determine the scope and depth of coverage only and not content. The lecture series curriculum outline or syllabus should be submitted to show that requalification program lecture content is designed to meet the requirements of 10 CFR
- 55 Appendix A and applicable portions of NUREG-0737.
FPC RESPONSE 1.1
- a. Please refer to Training Department Procedure (TDP) 203, Section 6.1.1.4 for clarification on using the results of the annual requalification written exam to determine the breadth and depth of topic coverage for the lecture series portion of the Requali-fication Program. Noce that in FPC's description of the program, the term " Content" is 'used to encompass the attributes of sub-topics, breadth, and depth relative to topic coverage,
- b. Please refer to TDP-203 Section 6.1.1.1 for the Requalification Program curriculum outline. It meets the requirements of 10CFR55 Appendix A and applicable portions of NUREG-0737.
F Enclosure to FPC letter 3F1285-17 Page 3 of 24 NRC OUERY: 1.2 In Section 4 of the progran description, the licensee should clarify that annual requalification examinations include written examinations and systematic observations and evaluation. Parentheses should be deleted.
FPC RESPONSE 1.2
- a. Sections 4.1 and 4.2 of our 3/15/85 submittal " Licensed Operator Requalification Program" description do address both aspects of the requalification program, that is, written exams as well as
', systematic observation and evaluation.
l' Additionally, please refer to TDP-203 Section 6.1.3 which clearly indicates that written examinations as well as systematic obser-vation and evaluations are integral parts of the Requalification Program. '
l
- b. FPC intends to issue a revision to the " Licensed Operator Requal-ification Program" description, submitted on 3/15/85, in early 1986 This revision will more clearly introduce Section 4 of the !
- program description, t i
s i
i i
I
Enclosure to FPC letter 3F1285-17
. Page 4 of 24 NRC QUERY: 1.3 The licensee should provide clarification in Section 5.1.2 that topics for preplanned and regularly scheduled lectures are based on 10 CFR 55, Appendix A requirements. Only depth and scope of coverage but not topic selection may be determined based on annual examination results.
FPC RESPONSE 1.3 In order to maintain consistent use of terminology, the next Licensed Operator Requalification Program description revision will change
" topic" to " content" in the lead-in paragraph to Section 5.1.2.
In addition, refer to the response 1.1.
Enclosure to FPC letter 3F1285-17 Page 5 of 24 NRC QUERY: 1.4 It is not clear how a preplanned lecture series is scheduled taking into account unanticipated events. How does the licensee schedule anything accounting for unanticipated events?
FPC RESPONSE 1.4:
The query apparently relates to the lead-in paragraph to Section 5.2. This paragraph simply indicates a need to " account" (or provide) for some measure of " unanticipated events" which can be expected to be disruptive to a preplanned lecture series schedule.
Requalification Training, as is all training, is scheduled in accor-dance with TOP-117. It is planned that there will be five training i cycles for each of the six shifts, which will require only thirty weeks of the available fifty-two weeks, thereby, allowing contingency
. for unforeseen events. This flexibility will accorinodate some measure 5
of schedule slips and unanticipated occurrences.
4 e
i 4
1
! l l
E Enclosure to FPC letter 3F1285-17 Page 6 of 24 NRC QUERY: 1.5 Licensed personnel may not be exempted from attendance at all requali-fication program lectures since a requalification program based solely on self-study is not an acceptable substitute for a lecture series per 10 CFR 55 Appendix A. The licensee should clarify Section 5.3 to describe the method used to ensure that an individual's entire requal-ification program is not accomplished through self-study and that lecture topics are covered as required by 10 CFR 55 Appendix A.
FPC RESPONSE 1.5:
Please refer to TDP-203 Section 6.1.1.5 for clarification o, program waivers and self-study. As the procedure indicates, no more than 50%
of the required lecture series may be completed by self-study. This is verified by the Nuclear Operations Training Supervisor as stated in TDP-203 Section 6.6.3. FPC does not agree that the program descrip-tion needs to be amplified since the detaileu implementation is con-trolled by the TDP.
Enclosure to FPC letter 3F1285-17 Page 7 of 24 NRC QUERY: 1.6 Sections 6.3.1 and 6.3.1.1 do not describe how the Operational Profi-ciency portion of training will be evaluated to comply with require-ments for " written examinations which provide a basis for evaluating knowledge of abnormal and emergency procedures" per 10 CFR 55 Appendix A 4.b. The licensee should clarify how the Operational Proficiency Training Program is designed to provide coverage of required informa-tion taking into consideration the results of annual examinations as well as plant drills.
FPC RESPONSE 1.6:
TDP-203 Section 6.1.2.3 clarifies the Operational Proficiency Training portion of the Requalification Program. The content of this portion is relatively constant as indicated by the requirements checkoff lists found in Attachment 501-5Q4.
Please refer to TOP-203 Section 6.1.3.1 " Annual Written Examination" which specifically complies with the 10CFR55 Appendix A 4 b require-ment for " written examination which provides a basis for evaluating knowledge of abnormal and emergency procedures." Plant drills, simu-lator evaluations, and semiannual evaluations are also used to assess operator competency.
m Enclosure to FPC letter 3F1285-17 Page 8 of 24 NRC QUERY: 1.7 The licensee should provide clarification in Section 6.3.1.1 that pro-cedures are reviewed on a regularly scheduled basis per 10 CFR 55 Appendix A 3.d.
FPC RESPONSE 1.7:
Please note, as clarification, that the " Licensed Operator Requalifi-cation Program" description (submitted to the NRC on 3/15/85) Section i 6.3.1 leading into Section 6.3.1.1, requires that all AP's and EP's and applicable normal operating and administrative procedures be reviewed annually.
Additionally, please refer to TDP-203 Section 6.1.2.3 which states that " normal operating procedures, all abnormal procedures (AP's), all emergency procedures (EP's), and applicable administrative procedures" are reviewed on an annual basis. These procedure reviews have been divided into quarterly requirements for convenience and are documented using TDP-203 Attachments 501-504.
A _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ m ____ ___ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ . _ _ _ _ . _ _ _ _ _ _
Enclosure to FPC letter 3F1285-17 Page 9 of 24 NRC QUERY: 1.8 The licensee should clarify whether and how trainees will be evaluated as required for the instructional sessions as described in Section 6.3.1.1.
FPC RESPONSE 1.8:
The instructional sessions on-shift are an integral part of the Requalification Program. Refer to TDP-203 Section 6.1.2.3 for clari-fication on how these instructional sessions are evaluated.
Additionally, the trainees' understanding of the information covered by these instructional sessions is evaluated through drills, simulator evaluations, lecture series quizzes, and the annual written exam-ination.
- Enclosure to FPC letter 3F1285-17 Page 10 of 24 NRC QUERY: 1.9 The licensee should clarify whether and how the trainees will be evaluated for the plant drills as described in Section 6.3.2.
FPC RESPONSE 1.9:
Please refer to TDP-203 Section 6.1.2.3 and Attachment SR, which explains how trainees are evaluated for plant drills; also, recognize that drills and evaluations are performed on the simulator as well, where evaluations of trainee perfomance are required. Additionally, the knowledge required to perform well on drills is also tested and evaluated through semiannual evaluations, lecture series quizzes, and the annual written examination.
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letter 3F1285-17 Page 11 of 24 NRC QUERY: 1.10 The licensee should clarify how the trainees will be evaluated for the feedback of operating experience training as described in Section 6.3.3.
FPC RESPONSE 1.10:
The trainees receive training on industry experience and operational feedback as explained more fully in TDP-203 Section 6.1.1.2, Section 6.1.2.3, and Attachment 5 This experience and feedback are also factored into procedure revisions, the traininc of which is covered as described in TDP-203 Section 6.1.2.3. The evaluation of this training occurs in the simulator evaluations, semi-annual evaluations, lecture series quizzes, and the annual written exam.
Enclosure to FPC letter 3F1285-17 Page 12 of 24 NRC QUERY: 1.11 The licensee should describe the eriteria to be used for granting exemptions from portions of the Requalification Training Program for backup licensees as described in Section 6.4.
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FPC RESPONSE 1.11: ,
TDP-203 Section 6.2 " Backup Licensees" refers to TDP-112 which describes in detail how " Training waivers" and exemptions are
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Page 13 of 24 NRC QUERY: 1.12 Sections 9.1 and 9.2 make a distinction between requalification train-ing for instructors maintaining an active license and certified instructors. All certified and licensed instructors must be enrolled in appropriate Requalification Training that meets the requirements of 10 CFR 55 Appendix A, including the required reactivity control manip-ulations. The licensee should clari fy the method by which all instructors meet the requalification requirements of NUREG-0737, I.A.2.1 (March 28, 1980, H.R. Denton letter).
FPC RESPONSE 1.12:
It is FPC's position that NUREG-0737 I.A.2.3 (not I.A.2.1 nor 10CFR55 Appendix A) states the requirements for certified instructors.
Specifically, Denton's 3/28/80 letter, Enclosure 1 A.2.d & A.2.e and NUREG-0737 !.A.2.3 deal with instructor certification.
Please refer to the enclosed TDP-209 " Operations Instructor Qualifica-tion Program" Section 6.6, which addresses Instructor Requalification Training, for more details and clarification of FPC's position on this matter.
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i Enclosure to FPC
! letter 3F1285-17 l Page 14 of 24 e
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NRC QUERY: 1.13 l
All licensed and certified instructors should take an annual requali-fication examination as part of the annual requalification program.
l Exemptions for instructors who write and grade annual requalification l examinations may be granted on a limited basis. The licensee should clarify that instructors meet requalification examination requirements and passing criteria, FPC RESPONSE 1.13:
FPC disagrees with the recommendation that all certified instructors should take an annual exam. NUREG-0737 I.A.2.1 or I. A.2.3 makes no l such recomendation or requirement. FPC has chosen to make each certified instructor a subject matter expert who is responsible for
! teaching specific topics; to require an annual exam of the scope, breadth and depth of a licensed person is defeating the purpose of assigning specialty subjects to certified instructors. The Certified Instructor Requalification Program meets NUREG-07371.A.2.3. ;
For additional clarification on this matter see Response 1.12.
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Enclosure to FPC letter 3F1285-17 Page 15 of 24 NRC QUERY: 1.14 The licensee should specify what simulator is used for annual simula-tor training and evaluation and whether that simulator complies with Regulatory Guide 1.149. Note that the use of a simulator for meeting the requirements of 10CFR 55 Appendix A is allowable if the simulator reproduces the general operating characteristics of the facility involved and the arrangement of the instrumentation and controls of the simulator is similar to that of the facility according to 10 CFR 55 Appendix A.
FPC RESPONSE 1.14:
As stated in TDP-203 Section 6.1.2.2 and Appendix A, the simulator used is the PowerSafety International Simulator (B&W simulator). This simulator meets the requirements of 10CFR55 Appendix A; the require-ments of Regulatory Guide 1.149 are met with the exception that it is not an exact replica of the CR-3 Control Room. FPC is currently in the process of procuring a plant-specific simulator which will meet all . requirements of ANS 3.5 and Regulatory Guide 1.149, and exceed those of 10CFR55 Appendix A.
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Enclosure to FPC letter 3F1285-17 Page 16 of 24 NRC QUERY: 1.15
-The licensee should clarify in Section 7.2 that records of the requal-ification program must be maintained for a period of two years from the date of the training to document the participation of each licensed operator and senior operator in the Requalification Prugram according to 10 CFR 55 Appendix A. These records must be available for review for hRC evaluation of license renewal.
FPC RESPONSE 1.15:
Section 7.2 of the Requalification Program description states that
" Training records for current members of plant staff will be retained for the duration of the CR-3 operating license," which exceed 10 CFR 55 Appendix A requirement.
Also, please refer to TDP-203 Section 8.0 which states that the train-ing records will be maintained for the lifetime of the plant. This exceeds the two-year requirement of 10CFR55 Appendix A. Also TDP-109
" Training Records Management" specifically states how training records are processed and stored for review for NRC evaluation of license renewal.
Enclosure to FPC letter 3F1285-17 i Page 17 of 24 l
- NRC QUERY
- 1.16
" Quarterly Procedure Review Sheets" as described in Section 6.3.1 con-stitute a list of procedures to be reviewed as on-the-job performance
, items. The licensee should describe how these same sheets are to be l used to document and evaluate " plant drills" training in the topics described in Section 6.3.1.1. It is not clear how topics such as i
" Radiation Protection Manual" and " Emergency Plan" are trained and
- evaluated on-the-job using the procedure review sheets.
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FPC RESPONSE 1.16:
- a. Please refer to TOP-203 Section 6.1.2.3 and Attachment SR for i information on how plant drills are conducted, evaluated and l documented.
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- b. The on-shif t Instructional Sessions cover many topics such as
" Radiation Protection Manual" and " Emergency Plan" which are documented using the Procedure Review Record Sheets (Attachments 5Q1-5Q4). The evaluation of the trainees' knowledge occurs dur-l ing drills, simulator training, semiannual evaluar.uns, lecture l
series quizzes, and the annual written examinations. For l additional clarification please refer to TOP-203 Section 6.1.2.3 l
and Attachments 501-5Q4 and SR.
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Enclosure to FPC letter 3F1285-17 Page 18 of 24 NRC QUERY: 1.17 The licensee should clarify in Section 6.1.1 that credit for reactiv-ity manipulations should be limited to significant baron changes which result in a change of reactor power or movement of control rods.
FPC RESPONSE _1.17:
The requirement for and wording of this reactivity manipulation is directly from NUREG 0737 I.A.2.1 (Denton's 3/28/80 letter, Enclosure
- 4) which does not make such stipulations and limitations.
This reactivity manipulation is one of many control manipulations as evident in TOP-203 Attachments 3 and 4 and FPC's 3/15/85 " Licensed Operator Requalification Program" description. In light of the other required manipulations, there appears to be ample opportunity for trainees to demonstrate their ability to control plant reactivity and respond accordingly.
In the next revision to TDP-203 FPC will stipulate acceptance criteria for "significant reactivity changes" which would apply to boron addition / dilution activities.
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Enclosure to FPC letter 3F1285-17 Page 19 of 24 2.0 Replacement Operator Training Program (July 23, 1985 letter 3F0785-27)
NOTE: This letter revised FPC's Connitment for training in Heat Transfer, Fluid Flow and Thermodynamics.
NRC QUERY: 2.1 The ifcensee should provide a description of the course syllabus or curriculum outline for the Replacement Operator Training Program and the ' Non-Licensed Operator Training Program and identify the segments of those training programs required for initial license training (i.e., reactor operator), senior reactor operator training, and non-licensed operator training.
FPC RESPONSE 2.1:
Please refer to TDP-201 "Non-1.icensed Operator Training Program" Attachments 1, 2 and 3 which identifv the training that must be com-pleted for non-licensed operator qualification.
Also, TDP-202 "Replacenent Operator Training Program" Appendices A and B define the training requirenents for initial R0 and SRO license training and Appendix C for the course curriculum for initial license training.
Specifically, the following Heat Transfer, Fluid Flow and Therno-dynamics Training must he completed:
ANA0-10; HTFF Introduction (TDP-201 Attach.1)
ANAO-11; Measuring Devices (TDP-201 Attach.1)
NAO-50 through 59; HTFF (TDP-201 Attach. 2)
Reactor Operator - Heat Transfer, Fluid Flow. Thernodynamics (TDP-202,Page31of74)
Senior Reactor Operator - Heat Transfer, Fluid Flow.
Thermodynamics (TOP-202, Pago 38 of 74)
I Enclosure to FPC letter 3F1285-17 Page 20 of 24 NRC QUERY: _2. 2 The licensee should describe how Heat Transfer, Fluid Flow and Thermo-dynamics Training is addressed "as necessary' in the Replacement Operator Training Program and how the need is determined.
FPC RESPONSE 2.2 Please refer to TOP-202 Section 6.2.2.1 and Appendix C which clarify the Heat Transfer, Fluid Flow, and Thermodynamics Training required in the Replacement Operator Training Program. The depth, breadth, and sequencing of the training needed in these subjects has been deter-mined through detailed job and task analyses.
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Enclosure to FPC letter 3F1285-17 Page 21 of 24 NRC QUERY: 2.3 The licensee should provide the curriculum outline and identify how the required training for lleat Transfer, Fluid Flow and Thermodynamics is provided in the Replacement Operator Trainng Program for instant SRO candidates.
FP_C RESPONSE 2.3_:
Please refer to TOP-202 Section 6.2.2.1 and Appendix B section 2.0 -
2.3.5 for clarification of Heat Transfer, Fluid Flow, and Thermodynan-ics Training for instant SRO candidates.
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Enclosure to FPC letter 3F1285-17 Page 22 of 24 3.0 Licensed 0)erator Requalification Training Program Commitment Clarifi-cation (July 23,_198.5 letter 3F6755-15)
NRC OVERY: _
3 ._1, The licensee should clarify that selection of topics listed in 10 CFR I 55 Appendix A for Requalification Training is not optional. Only the depth and scope of coverage of required topics may be varied based on i trainee requalification examination results. The licensee should !
clarify that training in Heat Transfer, Fluid Flow, and Thermodynam-ics, as well as mitigation of accidents involving a degraded core, are required topics for Requalification Training. "
FPC RESPONSE 3.1:
Please see Response 1.1 and 1.3 for clarification.
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Enclosure to FPC letter 3F1285-17 Page 23 of 24 4.0 Replacement Operator Training Program (July 23, 1985, letter _
3F0785-16)
NRC QUERYi '4.1 The licensee should provide the Replacement Operator Training Program syllabus or curriculum outline which identifies how training for mitigating core damage is covered in regularly scheduled training for licensed operator and senior operator trainees.
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FPC RESPONSE 4.1:
Please refer to TDP-202 Section 6.2.2.1 and Appendix C Parts A.1 and B.1 which clarify the training on mitigating core damage du ring initial training for operator and senior operator trainees.
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Enclosure to FPC letter 3F1285-17 ' ^
Page 24 of 24 5.0 Instructor Qualifications Clarification (July 23, 1985, letter 3F0785-13)
NRC QUERY: 5.1 The licensee should clari fy the Crystal River 3 certification and licensing requirements and procedures for instructors and instructor requalification training requi rements. All instructors who teach systems, integrated response, transients and simulator courses should be licensed or certified by the NRC on a same type facility (i.e.,
another B&W facility). Licensed and certified instructors shall be enrolled in Requalification Training in accordance with NUREG-0737 I.A.2.3 and should take annual requalification examinations. Documen-tation of instructor participation in Requalification Program Training and evaluation is also required. The licensee's description of instructor certification and requalification in the July 23, 1985, letter does not appear to meet applicable requirements.
FPC' RESPONSE 5.1:
FPC does not agree with the recommendation that all instructors shculd be licensed or certified by the NRC on the same type facility (i.e. , another B&W facility). The Operations Instructor Qualification Program, as described in TDP-209, meets the requirements for licensed or certified instructors as stated in NUREG-0737 I.A.2.3 and Denton's 3/28/80 letter Enclosure 1 - A.2.d & A.2.e (the only NRC source for such requirements) in that FPC procedures require Operations Instruc-tors to "be licensed 'or certified by the' NRC on a PWR facility."
NUREG-0737 states " ... facility instructors...shall demonstrate their competence by successful completion of a senior operation examina-tion," without specification of type of facility requirements.
With regard to requi ring certified instructors to take an annual requalifications examination, please see our response to Query 1.13.
Please refer to TDP-209 Section 8.0 which clearly states that docu-mentation of appropriate instructor participation and evaluation in the requalification program is required.
Contrary to this Query, FPC concludes that the Instructor Certifica-tion and Requalification Programs do meet the applicable requirements, that is, NUREG-0737 I.A.2.3.