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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F9941999-10-15015 October 1999
Discusses FPC 970819 Request for Temporary Relief from ASME Code Section XI Requirements to Repair ASME Class 3 Nuclear Service & Decay Heat Sea Water System Piping.Forwards SE Containing Results of Staff Review
ML20217J5171999-10-13013 October 1999
Informs That on 990930,NRC Staff Completed mid-cycle PPR of Plant,Unit 3 & Did Not Identify Any New Areas That Warranted More than Core Insp Program.Previously Planned Regional Initiative Insp of safety-related Mod Will Be Performed
3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999
Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed
3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999
Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made
ML20212L0771999-10-0404 October 1999
Forwards SER Accepting Licensee Relief Requests 98-012 Through 98-018 Involving Containment Insps at Crystal River Unit 3 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(a)(3)(ii)
ML20217D6551999-10-0101 October 1999
Requests That Natl Communication Sys Arrange for Licensee Participation in Government Emergency Telecommunications Service,Per NRC Info Notice 99-025
ML20212J8481999-10-0101 October 1999
Forwards Safety Evaluation Re Second 10 Yr Interval ISI Program Requests for Relief 98-009-II.Reliefs Granted for 98-009-II,Parts B & C & 98-010-II & 98-011-II
3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999
Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment
3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999
Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331
ML20212F7251999-09-23023 September 1999
Discusses Staff Review of Util 980330 Response,As Suppl on 990514,to GL 97-06, Degradation of SG Internals. Staff Concludes That Licensee Responses to GL Provide Reasonable Assurance That Condition of SG Internals Acceptable
ML20212F7331999-09-23023 September 1999
Discusses Util Licensing Action for GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants. NRC Ack Efforts Util Completed to Date in Preparing Crystal River,Unit 3 for Y2K Transition
3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999
Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46
ML20212E6741999-09-21021 September 1999
Forwards Safety Evaluation Accepting Proposed EAL Changes Submitted by ,As Supplemented by 981120,990713 & 0831 Ltrs,Incorporating Guidance in NUMARC/NESP-007,Rev 2, Methodology for Development of Eals
3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999
Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)
3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999
Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief
ML20212F3141999-09-13013 September 1999
Forwards Insp Rept 50-302/99-05 on 990704-0814.Violations Noted,But Being Treated as non-cited Violations
ML20211L9081999-09-0303 September 1999
Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Crystal River Unit 3
ML20211Q7581999-09-0101 September 1999
Forwards Summary of 990812-13 Training Managers Conference in Atlanta,Georgia Re Recent Changes to Operator Licensing Program.List Conference Attendees,Copy of Presentation Slides & List of Participant Questions Encl
3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999
Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals
ML20211G7111999-08-30030 August 1999
Modifies Approval of 980521 Request for Exception to 10CFR50.4(b)(6) & Grants Util Approval to Submit Copies of Future Updates to FSAR as Listed
ML20211G7031999-08-30030 August 1999
Informs of Approval of Util 980521 Request for Exception to 10CFR50.4(b)(6),allowing Util to Submit Updates to Plant Ufsar.Ltr Modifies That Approval & Grants Util Approval
3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999
Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002
ML20212C1351999-08-27027 August 1999
Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input
3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999
Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71
3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999
Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3
3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999
Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05
3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999
Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal
3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999
Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2
3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value
05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999
Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented
ML20210Q4511999-08-0505 August 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006
ML20210P0741999-08-0505 August 1999
Forwards SE Accepting Licensee 980416 & 1130 Ltrs Re Third 10-year Interval ISI Program Plan & Associated Requests for Relief for Plant,Unit 3
3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999
Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603
ML20210G8551999-07-27027 July 1999
Forwards Insp Rept 50-302/99-04 on 990523-0703.One Violation Identified & Being Treated as Noncited Violation
3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999
Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments
ML20209H5211999-07-16016 July 1999
Forwards Request for Addl Info Re Licensee Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in CR-3 once-through Steam Generators in Order to Complete Review
ML20209G3231999-07-15015 July 1999
Forwards Biological Opinion Issued by Natl Marine Fisheries (NMFS) of Dept of Commerce.Nmfs Concluded That Operation of Cw Intake Sys of Crystal River Not Likely to Jeopardize Existence of Species Listed in Biological Opinion
ML20209G3481999-07-15015 July 1999
Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon
3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999
Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl
3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999
Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl
3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999
Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl
3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999
Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730
3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999
Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held
3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21
ML20196L1261999-07-0707 July 1999
Discusses Closeout of TAC MA0538 Re License Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Unit 3
3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999
Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3
ML20196J4991999-07-0101 July 1999
Advises That Info Contained in ,Which Included TR BAW-2346P,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20209C0811999-06-25025 June 1999
Forwards Overdue Controlled Document Transmittals for Listed Documents
3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999
Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl
1999-09-03
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEAR3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999
Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed
3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999
Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made
3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999
Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment
3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999
Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331
3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999
Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46
3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999
Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)
3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999
Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief
3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999
Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals
ML20212C1351999-08-27027 August 1999
Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input
3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999
Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002
3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999
Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71
3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999
Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3
3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999
Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal
3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999
Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05
3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999
Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2
05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999
Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented
3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value
3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999
Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603
3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999
Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments
ML20209G3481999-07-15015 July 1999
Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon
3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999
Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl
3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999
Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl
3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999
Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl
3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999
Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730
3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999
Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held
3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999
Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3
ML20209C0811999-06-25025 June 1999
Forwards Overdue Controlled Document Transmittals for Listed Documents
3F0699-12, Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested1999-06-23023 June 1999
Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested
3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999
Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl
3F0699-08, Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments1999-06-21021 June 1999
Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments
3F0699-09, Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl1999-06-0404 June 1999
Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl
3F0599-21, Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads1999-05-28028 May 1999
Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads
3F0599-10, Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl1999-05-26026 May 1999
Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl
ML20207E4341999-05-25025 May 1999
Submits 30-day Written Rept on Significant PCT Changes in ECCS Analysis for ANO-1.CRAFT2 Limiting PCT for ANO-1 Was Bounded by 1859 F PCT Calculated at 2568 Mwt for Crystal River 3 Cold Leg Pump Discharge Break Size of 0.125 Ft
3F0599-22, Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs1999-05-21021 May 1999
Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs
3F0599-18, Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM1999-05-14014 May 1999
Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM
3F0599-17, Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments1999-05-14014 May 1999
Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments
3F0599-07, Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 19781999-05-14014 May 1999
Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 1978
3F0599-03, Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR1999-05-12012 May 1999
Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR
3F0599-05, Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl1999-05-12012 May 1999
Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl
3F0599-08, Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments1999-05-0303 May 1999
Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments
3F0599-09, Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 19981999-05-0101 May 1999
Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 1998
3F0499-24, Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent1999-04-30030 April 1999
Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent
3F0499-09, Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 9907301999-04-30030 April 1999
Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 990730
3F0499-23, Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements1999-04-23023 April 1999
Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements
3F0499-18, Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl1999-04-20020 April 1999
Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl
3F0499-05, Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin1999-04-16016 April 1999
Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin
3F0499-08, Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 19981999-04-16016 April 1999
Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 1998
1999-09-27
[Table view]
Category:UTILITY TO NRC
MONTHYEAR3F0990-11, Forwards Final Status Update Re Design & Operations Verification for Instrument Air Sys Per Generic Ltr 88-141990-09-20020 September 1990
Forwards Final Status Update Re Design & Operations Verification for Instrument Air Sys Per Generic Ltr 88-14
3F0990-05, Forwards 1990 Inservice Insp Summary Rept. Rept Contains Owners Data Rept,Data Summary Sections for Class 1,2 & 3 Components,Rept for Repair & Replacements & Listing of Exams1990-09-14014 September 1990
Forwards 1990 Inservice Insp Summary Rept. Rept Contains Owners Data Rept,Data Summary Sections for Class 1,2 & 3 Components,Rept for Repair & Replacements & Listing of Exams
3F0990-08, Forwards Response to Violations Noted in Insp Rept 50-302/90-23.Corrective Actions:Training Session Conducted to Stress Importance of Attachments Being Part of Work Package When Required by Procedure1990-09-13013 September 1990
Forwards Response to Violations Noted in Insp Rept 50-302/90-23.Corrective Actions:Training Session Conducted to Stress Importance of Attachments Being Part of Work Package When Required by Procedure
3F0890-23, Discusses Decommissioning Financial Assurance Rept Dtd 900726.Amount Util Collecting Exceeds Amount Necessary Based on NRC Formula & Does Not Include Estimated Cost of Removal & Disposal of Nonradioactive Structures & Matls1990-08-30030 August 1990
Discusses Decommissioning Financial Assurance Rept Dtd 900726.Amount Util Collecting Exceeds Amount Necessary Based on NRC Formula & Does Not Include Estimated Cost of Removal & Disposal of Nonradioactive Structures & Matls
ML20028G8251990-08-29029 August 1990
Advises That Supplemental Response to Insp Rept 50-302/89-18 Will Be Submitted by 901030
ML20059G1721990-08-24024 August 1990
Submits Info Re Change in Operator License Status.Re Rawls & Wa Stephenson Senior Reactor Licenses Should Be Terminated, Effective 900817 Due to Reassignment from Position Requiring Licenses
3F0890-15, Forwards Fitness for Duty Program Performance Data for Period of Jan-Jun 19901990-08-23023 August 1990
Forwards Fitness for Duty Program Performance Data for Period of Jan-Jun 1990
3F0890-21, Forwards Semiannual Radioactive Release Rept Jan-June 1990 for Crystal River Unit 3 & Rev 15 to Crystal River Unit 3 Odcm1990-08-23023 August 1990
Forwards Semiannual Radioactive Release Rept Jan-June 1990 for Crystal River Unit 3 & Rev 15 to Crystal River Unit 3 Odcm
ML20059A0031990-08-16016 August 1990
Responds to NRC 900613 Request for Addl Info Re Util 871222 Response to Violations Noted in Insp Rept 50-302/87-30
3F0890-03, Forwards Rev 11 to Inservice Insp - Pump & Valve Program, Crystal River Unit 31990-08-16016 August 1990
Forwards Rev 11 to Inservice Insp - Pump & Valve Program, Crystal River Unit 3
3F0890-10, Advises That Util Completed Mods to Comply w/10CFR50.62 Requirements Re Reduction of Risk from ATWS Events1990-08-16016 August 1990
Advises That Util Completed Mods to Comply w/10CFR50.62 Requirements Re Reduction of Risk from ATWS Events
3F0890-05, Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 1741990-08-10010 August 1990
Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 174
ML20058L2001990-08-0202 August 1990
Provides Current Status of Reg Guide 1.97 Activities. Pressurizer Heater Status & Main Steam Safety/Relief Valve Position Indications Completed
3F0790-10, Forwards Justification for Continued Operation Re Emergency Diesel Generator Block Loading Voltage Dips.Util Will Install Higher Accuracy Relays to Improve on Accuracy & Repeatability of Load Intervals1990-07-18018 July 1990
Forwards Justification for Continued Operation Re Emergency Diesel Generator Block Loading Voltage Dips.Util Will Install Higher Accuracy Relays to Improve on Accuracy & Repeatability of Load Intervals
3F0790-06, Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-81990-07-12012 July 1990
Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-8
ML20055D5561990-06-29029 June 1990
Forwards 890505 & s to Be Placed in Plant File
3F0690-15, Informs That Tech Spec Actions Identified in Util Addressed as Part of Tech Spec Improvement Program,Per 900518 Request for Programmed Enhancements for Generic Ltr 88-171990-06-29029 June 1990
Informs That Tech Spec Actions Identified in Util Addressed as Part of Tech Spec Improvement Program,Per 900518 Request for Programmed Enhancements for Generic Ltr 88-17
3F0690-22, Forwards Annual Financial Repts for 1989 for Orlando Utils Commission & Cities of Bushnell,Leesburg,Ocala & Tallahassee,Per 10CFR50.71(b)1990-06-27027 June 1990
Forwards Annual Financial Repts for 1989 for Orlando Utils Commission & Cities of Bushnell,Leesburg,Ocala & Tallahassee,Per 10CFR50.71(b)
3F0690-19, Responds to Deviations Noted in Insp Rept 50-302/90-15. Corrective Actions:All Reg Guide 1.97 Category 1 Instruments on Main Control Board Marked & Engineered Safeguards Matrix Indicating Lights Arranged in Unique Array1990-06-25025 June 1990
Responds to Deviations Noted in Insp Rept 50-302/90-15. Corrective Actions:All Reg Guide 1.97 Category 1 Instruments on Main Control Board Marked & Engineered Safeguards Matrix Indicating Lights Arranged in Unique Array
ML20043H5781990-06-21021 June 1990
Responds to Generic Ltr 89-06, Spds. All Open Issues Identified in NRC SER & Plant SPDS Satisfies NUREG-0737, Item I.D.2 & Suppl 1
ML20044A6121990-06-21021 June 1990
Forwards Payment of Civil Penalty,Per NRC 900524 Order Based on Findings in Insp Rept 50-302/89-09
ML20043J0221990-06-21021 June 1990
Submits Info in Support of Tech Spec Change Request 175,Rev 1,Suppl 1 Re Spent Fuel Pool Storage Capacity at Plant
ML20043H4151990-06-21021 June 1990
Forwards Response to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions.
3F0690-18, Responds to Violations Noted in Insp Rept 50-302/90-09. Corrective Action:Temporary Lettering Placed on Index Plates for Consistency W/Previous Markings Immediately Following Discovery of Error1990-06-20020 June 1990
Responds to Violations Noted in Insp Rept 50-302/90-09. Corrective Action:Temporary Lettering Placed on Index Plates for Consistency W/Previous Markings Immediately Following Discovery of Error
ML20043H2901990-06-15015 June 1990
Forwards Results of Refuel 7 once-through Steam Generator (OTSG) Eddy Current Insp,Per Tech Spec Section 4.4.5.5.Eight Defective Tubes & Two Administratively Plugged Tubes in OTSG a Resulted from Review of Insp Data
ML20044A0641990-06-13013 June 1990
Forwards Rev 5 to Physical Security Plan,Replacing Currently Approved Rev 4 W/Amends.Rev Withheld (Ref 10CFR73.21)
ML20043G2271990-06-12012 June 1990
Suppls 900604 Ltr Describing How Control Room Habitability Dose Would Be Adversely Affected by Elimination of Reactor Bldg Flood Vol Unless Overly Conservative Failure Postulations Also Changed.Quarterly Updates to Be Provided
ML20043G3711990-06-12012 June 1990
Forwards 1990 Internal Cash Flow Projection for Plant Which Updates Utils Utilization of Alternative (E)
ML20043G2361990-06-12012 June 1990
Forwards Info Re Fire Protection Sys Reliability for Providing Water to Intermediate Bldg Following High Energy Line Break.B&W Issued Contract to Verify Mass/Energy Release & Motor Starters & Terminal Blocks Insulated
ML20043F1601990-06-0404 June 1990
Provides Supplemental Info on Reactor Bldg Flooding,Per Util 900517 Ltr Describing Resolution Plan Being Pursued.Util Has Limited Vol of Water Contributed by Borated Water Storage Tank & Sodium Hydroxide Tank to Flood Level
ML20043C8721990-05-31031 May 1990
Forwards Rev 0 to Crystal River Unit 3 Cycle 8 Core Operating Limits Rept, Per Tech Spec 6.9.1.7
ML20043B8431990-05-24024 May 1990
Describes Alternative Testing of Reactor Bldg Spray Suction Valves BSV-1 & BSV-8,per Generic Ltr 89-04.At Least One Valve Will Be Disassembled & Inspected During Each Refueling Outage Using Alternate Insp Method
ML20043B2771990-05-18018 May 1990
Advises of Mod to Original Commitment & Plans to Store Seal Ring in Original Storage Location During Plant Operations, Per 790606 Ltr.Mod Minimizes Personnel Exposure & Enhances Seal Plate Leak Tightness Due to Less Handling
ML20043B0321990-05-17017 May 1990
Provides Details of Resolution Util Will Pursue Re Reactor Bldg Flooding Detailed in Encl LER 90-005.Mod Will Be Installed to Add Alarm in Main Control Room to Indicate When Flood Level Reaches Point & Operator Action Begins
ML20043A5441990-05-16016 May 1990
Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project
ML20042G7681990-05-10010 May 1990
Submits Unsatisfactory Performance Testing Incident Repts, Per 10CFR26, Fitness for Duty. Results of Three Positive Blind Test Samples Certified to Contain No Drugs
ML20043A4931990-05-10010 May 1990
Forwards Executed Amend 8 to Indemnity Agreement B-54
ML20042G2101990-05-0707 May 1990
Provides Notice of MW Kirk Permanent Reassignment from Position & Requests Termination of Senior Reactor Operator License 20481-1,effective 900505
ML20042E8611990-04-26026 April 1990
Forwards Annual Financial Repts for Six Participating Owners of Plant
ML20012F2941990-03-30030 March 1990
Forwards Nonproprietary Rev to 51-1176431-02, Crystal River 3 Reactor Vessel...Temp Overpressure Protection, in Support of Tech Spec Change Request 174,Suppl 1 Re Response to Generic Ltr 88-11
ML20042D8321990-03-30030 March 1990
Provides Supplemental Response to Station Blackout Rule Implementation & Affirms That Diesel Generator Target Reliability Will Be Maintained
ML20012E2041990-03-23023 March 1990
Requests Temporary Waiver of Compliance Granted on Tech Spec 3.9.8.2 Re DHR Power Source Requirements
ML20012D9471990-03-21021 March 1990
Requests Approval of Capsule Withdrawal Schedule in Table 3-19 of BAW-1543,Rev 3, Master Integrated Reactor Vessel Surveillance Program to Allow Plant Refuel 7 Outage Plans to Continue on Schedule.Changes Needing NRC Approval Listed
ML20012D7371990-03-19019 March 1990
Responds to Generic Ltr 89-19 Re Resolution of USI A-47. Util Will Implement Appropriate Sys to Protect Against Overfill Concerns
ML20012C4501990-03-13013 March 1990
Forwards Listing of Insurance Policies in Place for Plant as of 900225
ML20012B4821990-03-0707 March 1990
Forwards Inservice Insp Pump & Valve Program Relief Request V-371 Proposing Alternate Acceptance Criteria Requirements for IWP-4150 for Fluctuations in Hydraulic Instrument Readings
ML20012B3651990-03-0101 March 1990
Lists Five Addl Drugs Included in 10CFR26 Re fitness-for- Duty Testing Program.Specimens Identified as Positive on Initial Screening Will Be Confirmed Using Gas Chromatography or Mass Spectrometry at Listed cut-off Levels
ML20012A4041990-02-27027 February 1990
Forwards 1989 Annual Rept of Personnel Exposure in Accordance w/10CFR20.407 & Tech Spec 6.9.1.5.(a) & Annual Rept of Facility Changes,Tests & Experiments in Accordance w/10CFR50.59
ML20006G1731990-02-23023 February 1990
Advises That Util Voluntarily Agrees to Participate in Emergency Response Data Sys Proposed in Generic Ltr 89-15
ML20011F2411990-02-21021 February 1990
Provides Followup on & Documents Discussion in 900116 Meeting Re Emergency Diesel Generator Loading
1990-09-20
[Table view] |
Text
_ _ _ _ _ _ .
U.S. NOCLI. AR HEC.ULATOR Y CoF ,sioH CoCKET NU"f3C P. I T Penc , oru 195 *%
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t Mr. John F. Stolz, Chief N Light Water Reactors Branch No. 1 p; ,\
Division of Project Management / :';// (i .l f'c i'. ;- w
- CM,.' (- h U.S. Nuclear Regulatory Commission '
Washington, DC 20555 Es
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In re: Florida Power Corporation y,( ;,3,4 ' . ,; .'
\vi./N D '# '
Crystal River Unit No. 3 Docket No. 50-302 -
(NQ, 7. ;--
Dear Mr. Stol:
- C This submittal is in response to your letter of January 25, 1977, regarding the Crystal River Unit No. 3 Operational QA Program.
Appended to this letter is a revised comparison matrix and supporting explanatory proposed FSAR revisions. As you will recall, a comparison matrix with supportive notes was sub- ,
mitted with our September 22, 1976, letter. The enclosed !
in fo rma tion , in addition to the proposed revisions which you found acceptable in our earlier transmittal of September 22, 1976, should provide a sufficient description for your staff to verify that our Operational QA Program does meet the re-quirements of ANSI N18.7-1976, and the Regulatory Guides (Nos. 1.8, 1.30, 1.37, 1.38, 1.39, 1.54, 1.58, 1.64-Rev. 1, 1.74, 1.88 and 1.94) which endorse the ANSI standards re-ferenced therein, except those areas for which alternative I controls are provided. I Please advise if additional discussion or information is desired.
rd _~
Very truly yours, ,(
- c. 1 J. .
O Rodgers is;. M3/jf. N ~
\
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Asst. Vice President - - o,._
JTR/iw .
,g Attachment -'
General Office 3201 Thirty-fourtn street soutn . P.O. Box 14042. st. Petersburg. Ficrida 33733 e 813-866-5151
a . l' t
COMPARIS0N ANALYSIS MATRIX ANSI N18.7-1976 FPC FSAR NOTE REFERENCE TO REFERENCE SECTION REFERENCE SECTION DETAILED COMMENT (2)
(1) Sept. 22,1976 March 3, 1977 Note No. Note No.
1 1.7.6.7.1 and 13.4 1
- 2. 1.7.7 1 3.1 1.7.6.7.1 (last Paragraph, Page1-58q) 2 3.2 1.7.5.1.1, 1.7.5.1.2, 1.7.6.7.1.3, and 1.7.6.7.1.b 3.3 1.7.6.7.1.b 3.4.1 12.1 3.4.2 Appendix 12.A, Sections 12.1.3, 1?.2.4, 1.7.5.6.1.j 12 4.1 1. 7. 6. 7.1. r, 1. 7. 6. 7. 3, 1. 7. 6. 7. 4, and 1.7.6.7.5 4.2 1.7.6.7.1.r 4.3.1 1. 7. 6. 7. 2, 1. 7. 6. 7.4, and 1. 7. 6. 7. 5 3 4.3.2 1.7.6.7.5 3 4.3.3 1. 7. 6. 7. 3, 1. 7,6. 7. 4, 1. 7. 6. 7. 5, and 1.7.6.7.1.q 3 4.3.4 12.6 and 1.7.6.7.5 3 4.4 , 12.1.1 4.5 1.7. 6.7.1. r, 12.1.1 and 12.6 3
'5.1 1.7 5.2 12.1.2 and 1.7.6.7.2 5.2.1 12.1.2 and 1.7.6.7.1.a 5 5.2.2 1.7.6.7.1.e and 12.4 6 5.2.3 12 (all) 4 5.2.4 12.4 7 5.2.5 12.4 4 5.2.6 12.4 9 5.2.7 12.1.1, 1. 7. 6. 7.1. r and 1. 7. 6. 7. 2 10 12 5.2.7.1 1.7.6.7.1.j,1.7.6.7.1.k,and
- 1. 7. 6. 7.1 10 12.1.1 5 5.2.7.2 12.1.1, 1. 7. 6. 7.1. r , 1. 7. 6. 7.1. c ,
and 1.7.G.7.2 10 11 5.2.8 12.4 12 5.2.9 12.3 5.2.10 12.4 6 5.2.11 1.7.6.7.1.e 5.2.12 1.7.6.7.1.q 7 5.2.13 1.7.6.7.1 9 8 5.2.13.1 1.7.6.7.1.d,1. 7.6.7.1 (Page 1-58g, last paragraph) 5.2.13.2 1.7.6.7.1.g 5.2.13.3 1. 7. 6. 7.1. h 5.2.13.4 1.7.6.7.1.m 9 5.2.14' 1.7.6.7.1.o and 1.7.6.7.2 5.2.15- 1.7.6.7.lf and 12.4 5.2.16- 1.7.6.7.1.L 10
5.2.17 1.7.6.7.2.b and 1.7.6.7.1.j 12 5.2.18 1.7.6.7.1.j 5.2.19 1.7.6.7.1.k and 13. (all) 5.2.19.1 13.4 l 5.2.19.2 13.4 l 5.2.19.3 1.7.6.7.1.k 5.3 1.7.6.7.1.e and 12.4
- 6. Not Applicable i
! Fcutnotes (1) This column shows the notes which were submitted in the FPC letter of September 22, 1976. and found acceptable as indicated in the NRC letter of January 25, 1977.
(2) These notes are proposed in response to the NRC letter of January 25, 1977 l
t
! (Note: In places where both columns have been left blank, it is I
intended that adequate compliance with ANSI N18.7-1976 is met by the
! Florida Power Corporation Quality Program.)
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Noto 1 - Ratcr:nca ANSI N. 7-1976, Seet, ion 2,.
The terms and their definitions as presented within Section 2 of ANSI U18.7-1976 and the other terms and their definitions as contained within ANSI Nk5.2.10 have been compared with the glossary of terms as contained within FSAR Section 1.7.7 The following amendments to FSAR Section 1.7.7 vill be incorporated:
A. Page 1-62, Section 1.7.7 which currently reads: "The following glossary describes the terms used in Section 1.7 Quality Program."
will be amended to read:
"The following glossary describes terms used in the Quality Progra=
and specifically within Section 1.7 These terms and their definitions and others utilized throughout the Quality Program are endorsed by ANSI 18 7-1976."
4
- 3. Page 1-64 which currently reads:
"Non-Cenformance: A condition of any article, material, or service in which one or more characteristics do not conform to requirements.
Includes failures, dicerepancies, deficiencies, defects, and malfunctions."
will be amended to read:
"Non-conformance: A deficiency in characteristic, docu=entation, or procedure which renders the quality of an item unacceptable or indeterminate. This includes physical d6fects, test failures, incorrect or inadequate documentation or deviation from prescribed processing, inspection or test procedures."
C. Page 1-64 which currently reads:
"Qualifica*. ion: Meeting required tests or examinations to show that a velder, inspector, or other personnel are qualified based upon specific requirements which state acceptance criteria for an adequate perfor=ance."
will bs amendsd to raad:
" Qualification: The characteristics or abilities gained through training or experience or both that enable an individual to perform a required function."
D. Page 1-65 Delete:
" Qualification Data: Specified requirements which state what constitutes performance."
Add:
" Qualified Procedure: A procedure which incorporates all applicable codes and standards, =cnufacturer's parameters, and engineering specifications and has been proven adequate for its intended purpose."
E. Page 1-65 Delete:
" Repair: Approved operations performed on a non-cenforming article to Add:
" Repair: HThe process of restoring a non-conforming characteristic to a condition such that the capability of an item to function reliably i
and safely is unimpaired, even though the item still may not conform to i the original requirer-ents."
F. Page 1-65 delete the paragraphs entitled SYSTDI and SYSTEMS INTEGRATION and replace with the following: l
" SUBSYSTEM: A. group of assemblies or components or both ccmbined to perform a single function.
SYSTEM: A group of subsystems united by some interaction or inter-d2pendence, performing many duties but functioning as a single unit.
(A' system may relate to hardware items or may be an organized and disciplined approach to acccmplish a task; e.g., a failure reporting system)." i i
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Note 2 - Reference ANSI N18.7-1976, Section 3.1 The last paragraph of Section 17 6.71 on page 1-58q will be amended to read as follows:
"The objective of the program is to maintain managerial and administrative control over operation of and action relative to safety-related structures, systems, equipment, and components through documenting the adherance to approved procedures without unnecessarily hindering the functioning of the plant. Florida Power Corporation is committed to comply with ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants," with alternative controls identified in the program description which fulfill the requirements but which differ slightly in specific implementation. When the ANSI standards referred to in ANSI N18.7-1976 are superceded by a revision approved by ANSI, the revision vill be reviewed by Florida Power Corporation with alternate controls provided, or the standard vill be utilized as revised."
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Note 3 - Reference ANSI N18.7-1976, Sections h.3 and 4.5 Section 1.7.6.7.5 of the FSAR will be revised to read as follows:
"1.7.6.7 5 Independent Review Program The Nuclear General Review Committee (NGRC) is a standin6 committee within Florida Power Corporation which reports to the Senior Vice President, System Engineering and Operations. The NGRC is responsible for independently reviewing the operational activities of Crystal River Unit No. 3.
The NGRC is structured and performs its functions in accordance with the requirements of ANSI N18.7-1976."
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Note h - Reference ANSI N18.7-1976, Section 5.2.5 Section 12.h shall be amended to read:
" Procedures within the Plant Operations Quality Assurance Manual are permanently or temporarily amended via use of a Procedure Review Record (PRR) on which guidance is established and approved by an established approving authority. Temporary changes are designated for a prescribed time fraae. The change is documented, reviewed by the Plant Review Committee and approved by the Nuclear Plant Manager within fourteen (14) days of i=plementation."
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1 Note 5 .- Reference ANSI N18.7-1976, Section 5.2.7 1 i
Section 5.2 71 of AUSI N18.7-1976 requires'a preventive maintenance program. The following paragraph vill be added in FSAR Section 12.1.1, as a second paragraph on Page 12 h:
"Under the provisions of 10CFR50.55(a), Florida Power Corporation shall provide an Inservice Inspection Program. This program and a Preventive Maintenance Program are in compliance with the ASME Boiler and Pressure Vessel Code and the requirements of Section 5.2.'(.1 of ANSI U18.7-1976.
The program will encompass the nuclear plant systems required to meet safe shutdown criteria and to return the plant to service, folicving plant outages in a safe and expeditious manner. The Program contains mandatory examinations, testing and inspections to evidence adequate safety, as well as defines the frequency and type of naintenance to be performed."
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Note 6 - Reference ANSI N18.7-1976, Sectica 5.2.10 FSAR Section 1.7.6.7 1.e shall be amended to read:
" Detailed specific requirements for housekeeping and cleanliness controls are implemented throu6h procedures contained in the Plant Operating Quality Assurance Manual. This inplementation is in compliance with the requirements of ANSI N18.7-1976, Section 5.2.10."
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Nota 7 - Rafertnca ANSI N18.7-1976, Szetion 5 2.12 A.. Section 1 7.6.7 1.q of the FSAR shall be amended in the first paragraph to read:
" Florida Power Corporation has established and implemented a system for the collection, storage, and maintenance of Quality Assurance Records as required by the design documents, procurement documents, and Regulatory Guide 1.88. All records transmitted to the quality files shall be done so in accordance with established written pro-cedures. Florida Power Corporation, Quality Programs Department audits all quality activities to assure that records within their possession are kept in accordance with written procedures".
JB . Section 1 7.6.7 1.q shall be amended in the second paragraph to read:
" Florida Power Corporation's Quality Program centains provisions which require that:
- 1. Two categories of Quality Assurance Records are established as Lifetime and Non-permanent. (Non-permanent records are required to show evidence that an activity was performed in accordance with applicable requirements but need not be retained for the life of the item. Lifetime records are required to be maintained for the life of the particular ite while it is installed in the plant or stored for future use).
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- 2. Quality Assurance Records are those records that furnish documentary evidence of the quality of items and of activities affecting quality. (A document is considered a Quality Assurance Record when the document has.been completed). These records include the results of review, inspections, tests, audits, monitorin6 of work performance and material analysis, the qualification of personnel, procedures, and equipment, design drawings and subsequent modifications, specification reports,
. procurement documents, calibration procedures and reports, and nonconformance and corrective action reports. The records are identifiable and retrievable as defined in AHSI N18.7-1976, Section 5 2.12.
-3 The inspection and test records contain the following:
a) Description of the types of operation.
b) Evidence of completing and/or verifying a manufacturing
- inspection or test operation.
- 4. Records are stamped, initicled, signed, or otherwise authenticated and dated by authorized personnel.
5 Storage facilities are constructed, located, and secured to prevent destruction and minimize deterioraticn or loss of records. Florida Power Corporation maintains a duplicate set of microfilmed information at a remote facility."
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' Nota 8 - Rmfersnca ANSI N18.7-1976, Section 5 2.13 l A. The first paragraph in FSAR Section 1.7.6.71.g, page 1-58g will be amended to read:
" Vendor evaluation surveys to qualify potential bidders in accordance with established Florida Power Corporation written procedures and in compliance with the ANSI N18.7-1976, Section 5 2.13, are conducted by FPC Engineering and Quality Programs Department personnel or through qualified consultants. Florida Power Corporation's Quality Programs Department will audit purchasing activities to assure compliance with procedures. In addition, Florida Power Corporation will assure that all Quality requirements of the purchase document have been met, utilising random audits of the document files in accordance with established written procedures".
B. Delete the second paragraph under FSAR Section 1 7.6.7 1.g on page 1-58g and delete, also, Subparagraphs 1 7.6.T.l.g.1, 1 7.6.7.1.g.2 and'l.7.6.7 1.g.3
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. Noti 9 - Rafer:nca ANS1 W18.7-1976, Sectica 5 2.13.4 2 FSAR Section 1.T.6.7.1.m vill be revised to read as follows:
"m. Handling, Storage, and Shipping The Florida Power Corporation Material Systems & Stores (MS&S)
Department staff are responsible for material handling, storage, and shipping activities for plant spare parts and operating supplies in accordance with detailed written procedures contained within their MS&S Quality Operating Manual. These procedures provide full conformance with ANSI 318.7-1976, Section 5 2.13.h, with the'following exceptions:
- a. Section 2.4 - Receiving and in-storage inspection vill be performed by experienced senior stores personnel trained and knowledgeable in the MS&S quality operating procedures,
- b. Section 3 - Packaging of all stored material vill be in accordance with sound storage principles assuring the integrity of the stored item. Periodic in-storage f
( inspections vill be performed to assure proper condition of material packaging.
- c. Section 5.2.2 - Receiving inspection for level A material vill be performed in the receiving area of the storeroom and assurances provided that the material meets the specifications of the Purchase Order (P.O.) or Requirement
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Outline (R.O.). Special electrical testing is conducted when specified.
The activities of 'the Material Syste=s and Stores Department associated with handling, storage and shipping of Crystal River Unit #3 material are audited by the Quality Programs Department."
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ilote 10 - Reference ANSI N18.7-1976, Section 5.2.16 The following paragraph will be added as the third paragraph of the FSAR Section 1.7.6.7.1.1:
" Calibration records and controls are provided for within the Plant Operations Quality Assurance Manual which complies with ANSI nl8.7-1976, Section 5.2.16."
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Nots 11 - Rafertnca ANSI N18.7-1976, Section 5.2.T.2.
A. FSAR Section 17.6.7.1.c, first paragraph shall be amended to read:
" Florida Power Corporation's Production Engineering Department vill provide an independent review for all safety-related modifications
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which f'volve development of, or changes to, design data or documentation.
This review will include verification of compliance with ANSI N18.7-1976, Section 5.2.7 2. Generally, all modifications vill undergo an Engineering review resulting in the establishment of a complete modification package. For non-safety-related modifications, an Engineering review may take place after the fact due to the necessity of getting the work acecmplished in a timely manner. The Plant Manager i
shall decide whether Engineering approval is required prior to installation. Florida Power Corporation's Quality Programs Department vill audit the design quality control function."
B. FSAR Section 1.7.6.7.1.c, delete the second paragraph and Subparagrc,hs 1.T.6.7.1.c.1 through 1.7.6.7.1.c.13 O
w f Note 12 - Reference ANSI N18.T-1976, Section 3.h.2, 5.2.7 and 5.2.17 FSAR Section 1 7.6.7 1.j, page 1-58j, shall~be-amended to delete the first'two paragraphs entirely as now written and replace with the following:
" Florida Power Corporation's Production Department Plant Staff and all participating contractors are required to provide written procedures for the performance of in-process inspection. Florida Power Corporation Quality Programs Department audits these activities to assure compliance to the procedures.
l Inspection personnel are qualified in compliance with ANSI N18.7-1976, Sections 3.h.2, 5.2 7, and 5.2.17, as follows:
- 1. On-site plant personnel including contractors and personnel filling temporary positions who are performing inspection and examination activities shall have appropriate experience, training, and retraining to assure competence as required by ANSI N18.1-1971.
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- 2. Quality Programs Department personnel or their contractors performing inspection and examination activites shall be qualified to ANSI Nh5.2.6-1973 with the following exceptions:
a, ' Personnel vill be qualified in accordance with the re- l quirements of individual FFC position descriptions in lieu of subsection 3.1 of ANSI Nh5.2.6-1973.
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b ~. Specific requirements as defined in Subsection 3.2 of j MiSI Nk5.2.6-1973 vill be met only in those areas found applicable by Quality Program procedures.
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- c. Section h and Table I of MISI Nh5.2.6-1973 are not applicable within the FPC Quality Program as procedure approval and quality control functions may be performed by staff supervisory personnel.
f . 3. Other Florida Power Corporation support personnel performing inspection and examination activities vill be qualified through experience evaluation and by formal training programs. Imple-1 l mentation'of quality control functions is audited by the Quality Programs Department on a periodic basis."
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