|
---|
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
i 3 .
9 '
i r
t Florida Power
,o, ,. .
July 20, 1979 File: 3-0-3-a-3 ,
Mr. J. P. O'Reilly, Director Of fice of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, GA 30303
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 IE Bulletin 79-02, Rev. 1
Dear Mr. O'Reilly:
Enclosed is a supplement to our response of July 13, 1979 to IE Bulletin 79-02, Rev. 1, dated June 21, tit 79, and our response to six (6) informal questions raised by members of your staff.
This supplement revi.ses our earlier submittal in order to reflect correctly the completed hanger inspection at CR #3. Specifically, this response identifies which hangers are being upgraded to an appropriate safety factor during the present outage and which hangers will be upgraded at a later date. Enclosed is the Table III which provides a detailed schedule for each hanger not being modified during the present outage.
As of this submittal, FPC has responded to all NRC questions and adequately responded to IE Bulletin 79-02 such that Mode 2 operation of Crystal River 3 is justified. The completion of the modification to hangers identified in this submittal for this outage is presently scheduled for July 22, 1979.
If you have any further questions on this subject, please contact us as soon as possible in order that Mode 2 operation of CR #3 can be achieved without further delay.
Sincerely, 2393 318 FLORIDA POWER CORPORATION bl W. P. Stewart Manager, Nuclear Operations WPSemhF01 D43 79081709 59 ,
OpyECLAL COF z r
33733 813 -866 5151 General Off ce 32o1 Tngygurtn sireet soutn . P O Bos 14042. st Petersbu g Fiorida
SUPPL.Ef1ENT TO Jul. 13, 1979 RESPONSE Our response of . inly 13, 1979 identi' ed, in Table II. 191 h a n y.o r - t h.it re-quired undatication to bring them to elthin an acceptable saiet v tietor.
i Hanger DCR-59 was inadvertently left off the table and has now be. n includ-ed on the attached iable II bringing the total of the table to 192 ha u,;e rs.
llowe ve r , you will notice that 5 of the 11 hangers with Indication of ove r-stressed plates have been deleted t r ou t i.c attached Table II (maiked in red ink). These f ive ha nge rs are DCR-68, l>CR-6 9, SWil-10, Swil-125A a n,1 SWR-90.
These were deleted from the list of hangers requiring mo.lification as additional detailed plast ic analysis h is shown that the plates for these five hangers are not ove rs t ressed. This deletton now brings the total number of hange rs requi ri ni; modi f ica t ion , as a result of the completed inspection, to 181.
Of the 187 hangers, 93 will be upgraded to an acceptable safety lactor dor-ing this outage prior to ent erin;; !!vde 2 operat ion at G # 3. The remaining 94 hangers will be upgraded to the appropriate .itety tacte- In accor.lanc.
~
with the attached schedule (Table 111). The breakdown of the 93 nangers is as follows:
76 - moditled because Fs <2 15*- modi f i ed to brin,; hange rs with F3 <2 <4 up to the e<pi l va le nc e of 3 hangers with a safety f actor greater than 4 both upst rea.a an.1 dounstream 2**- moditi"d to bring all hangers in the.pOS column up to the equiva.ence of 3 hangers with a sa fety f actor greatei than a both upstream and downstream of a hanger with an ove r ,t ressed plate.
~39
- Taole 11 of our submittal of July 13, 1979 identified 32 hangers with a safety factor between 2 and 4 and not having 3 hangers with a safety factor 13 ater than 4 both upstream and downstream. By modi f yini; 15 of the 32 hangers, we were able to provide 3 hangers with a safety factor greater than 4 both upstream and downstream of any hanger with a safety tietor be t wee n 2 a nd 4. The 15 ha nge rs that were modifled are
!!Uil-5 57 SW!!-40 3, 40 2, 17]A, 475 Ddll-514, 585, 529 DilR-19, 18A, 53, 25, 9 DitC-106 DCR-19 ..
- Of the 6 hangers ident if ied with overstressed plates, 2 (SUH-:;1A o 163) did not have 3 hangers with a safety f actor greater than 4 both upstream and downstream. This required the modification of SWil-161 A 6 165 or the modification of adjacent hangers to provide 3 hangers with,a safety factor greater than 4 both upstream and downstream of SWit-161 A 6 165. It was decided to modi fy hange rs Sull-162 & 166 during %is outago in order to pro-vide 3 hangers with a safety factor >4 up and down f rom SWit-lbl A & 165.
WpSeahF01 khh) hlh D43 .
-9
TABLE il llULLETIf4 79-02 & 02A IIAfiGLR CliAfiGl 5 RLQUIRLD BY 1)LSIGfl COULS:
RDR - REDESIGfi REQULST f4CR - fiOfiC0!iFORMAfiCE REQULLI FS - SAFETY FACTOR POS - PLATE OVLRSTRLSSED R!l - RED llEAD fillii - fiUMBER OF llAfiGERS TO IllL liEXT llA iGER WITil A SAFETY F Ar, TOR >2 and <4 UP - Upstrea:a D4 - Downstream ,
239'] 320 1BA - One llanger an Anchor A - Anchor is flext E - End of System
Baynard(BULL 9-02 )0 /1 k
EllGINLLRING SAFLLUARD SYSILMS l'ag" 1 of 6 SYSTEM AS BUILT RED [ SIGN NilN NO. RDR Nd. NCR NO. F 3
F 3 F3 fe' ?<f 3<4 P05 UP DN USil-
$14 133 4 G' . 0 im.8
$41 135 5 2.9 8.3 * >3 A BSR-11 134 4 1.5 2 7. '
- 33 83 - 3.67 13.4 * >3 >3 DCli-99 30 -
1.3 12.0
2.1 12.0 * >3 >3 101 32 -
0.6 12.0
- 106 180 15 2.3 10.4 * >3 1 112 1/1 14 3.6 21.5
- 3 >3 113 110 9 1.9 3.3 ,o 115 131 15 1.5 8.8
- 116 182 15 2.9 14 * >3 119 103 15 2.2 10.4 * >3 >3 151 185 15 4.7 1/.5 Rl! >3 >3 3.3 9.7 * >3 >3 164 153 -
210 38 9 1.5 19.0
- 1rA 19 34 9 3.9 9.1 3 14 16.4
2.5 3 1DA 148
- 25 -
9.i -
C.1
- ^ . O.; 2.;
132 174 14 2.8 9.4 >3 1BA 0 1111 -
12 11
- 13 162 11 2.6/ 2/.1 *, >3 A 36 69 - <4.0 8.4/ * >3 >3 43 70 -
1.M 4.69
- 504A 44 9 3.0 32.3 * '3 >3 509 68 14 4./ 13.0 Ril ., >3 >3 511 4 9 1.4 5.93
2.1 4.02 .* 2- >3 529 157 2.8 8.1
- 3 >3 536A 139 9 <2.0 .1. 7
- Boynard(BUL79-02)D/5 "2393.52i
'I
ENGINLLRif;G SAf t t.UARD 5Y5f LM5 l' age 2 of 6 SYSTtM AS liUILT RLDLSIGfi filiN fiO. RDR T40. Nt;R f;0. F 3 Is i 3
<7 ?<l s<4 P o$, im DN
(> ti H-535A 140 9 < !.0 15.8
- 3 >3 549 168 6 3.28 17.4 * >3 A 561 115 9 3.8 10.8
0.33 8.24 >
6 f'O 94 9 3.6 1.0
3.1 26.0 * 't $3 DHR-9 111 11 3.6 19.8
- s3 2 17 160 13 2.96 8.2 * >3 3 19A 41 1 2.3 6.7
- 1 A 19 14 3 3.8 9.5 * >3 3 20 lb. 3 <2.0 9.5 .
25 117 6 2.8 17.6 * >3 3 27 106 6 <2.0 78.0 e 36 153 12 3.7 10.1 * >3 >3 39 105 6 3.3 10.4 * >3 3 43 14/ 4 1.9 23.8
3.09 14.R * >3 3 54 15/124 -
1.4 8.0
- 3 >3 63 125 6 3.7 9.9 * '3 >3 E f ii-128 119 3 <l.0 27.0
- 136 118 3 2.4 9.8 * >3 >3 528 130 IC 2.0 12.0
- 530 154 1C 3.9 12.3 * >3 A
~
EGH- :
27 116 Il <2.0 2/0
- FWH-138 121 1 2.1 9.0 * , >3 >3 140 112 11 1.5 10.8
- 143 109 11 3.0 10.3 * >3 >3
}' ..**
Baynard(BUL79-02)D75 -
,5 2390 322
t10ft-Ef;Gifill.RifiG SA!! GUARD SYSILMS Pag" 3 of 6 AS BUILT RLDLSIGft fE; SYSTEM IlCR f40. POS up D:
I40 . RDR fi0. F3 Fs F 3 _< 2 2 <l s<4 I
FWH-145 170 1 1.2 8.4 e 151 132 1 1.1 10.3
- 156 127 10 2.0 8.3 e 167 $7 10 0.61 5.4 e 166 98 -
2.9 9.5 e a > .1 169 141 10 1.40 11.8 e 17U 92 1C <1 9 29.7 .
MUH-59 149 11 0.6 48.0 o 556 114 10 3.6 11.6 e >3 1 557 78 - 3.3 12.43 e 1 3 558 77 -
2.n3 16.18 e >3 >3 585A 164 - 1.. 8.3 'e 593A 86 -
3.85 8.3 e >3 >3 612 142 10 2.1 8.4 e >3 >3 63;- 2 - 3.5 13.5 e >3 >3 634 151 12 2.5 10.7 e >3 >3 650 143 10 2.5 8.0 e >3 >3 712 7 -
3.7 51.0 . Zi:A A 822 10 -
1.2 9.9 .
845 146 / 2.5 32.3 e >3 >3 852 137 7 3.4 24.0 e <3 >3 940 156 - (1.0 10.7 .
941 104 7 <l.0 8.0 e 942 103 / <l.0 14.2 e 943 6 - 1.1 5.2 .
945 138 8 <2.0 28.6 .
946 152 12 0.0 10./ e 948 150 -
3.67 9.9 e >3 E RCH-35 129 1A 3.7 13.4 e' 3 >3 49A 145 -
3.32 8.0 e '3 33 55 60 1A 0.8 4.5 e 84 59 1A 1.1 8.1 e 239] 323 Baynard(BUL79-02)D75
9 EtiGINLI.RitiG SAll GUARD SY51Lf S nmie 4 of o SYSILM A5 BOILT RLOL5i"iN N!!N NO. ROR NO. NlR NO. I f, 1 3 32
?<l,<4 l' O '; l'i' Dil 3 , ,
SWH-lo J1 _
30^ 159 4 1.99 11.2 .
37A ?b - 2.9 6.3 . >3 >3 42A 96 -
2.55 12.3 ,, >3 >3 9 Rev 1 2.8 9.0 . 2BA >3 105 -
108 178 -
4.13 9.62 Ril 53 >3
. ,n ,, u , , si A L dl% , a a =
15GA 32 - 1.94 8.31 .
03 2.23 11.2 3 >3 15/ - .
161A 80 - 4.5 8.94 .
162 74 - 2.3 8.8 . >3 A 163A 28 IB 3.4 12.4 . >3 >3 165 24 - 2.3 8.3 .
166 61 - 3.6 10.3B . >3 >3 26 2.3 13.3 >3 >3 168 -
170 27 - 3.7 10.0 . 33 1
<4.0 8.31 >3 1liA 82 -
. 1 180 17 10 0./ H.3 .
16 2.5 13.4 . 2nA >3 182A 1 209A 66 - 4.18 8.04 .
223A 42 - 0.9 4.2 .
227A 21 - 3.9 8.0 . >3 >3 258 19 -
2.3 8.5 . >3 >3 312A 47 - 2.1 20.0 . >3 >J 402 65 - 2.29 8.2 . 2 >3 403 64 -
3.53 8.3 . >3 2 404A 93 - <2.0 10.6 .
405A 93 - <4.0 10.6 . JaA 2 93 <4.0 10.6 . 2 2BA 4')6 A -
93 <4.0 10.6 . 'A
. 2 407A -
93 <4.0 10.6 .. 2 >3 408A -
409A 93 - <4.0 If .6 . 1 >3 429A 93 - <2.0 10.o . -
431A 93 -
<2.0 10.6 . ,
432A 93 -
<2.0 10.6 . :
449A 93 -
C .0 10.6 .
93 <4.0 10.6 . s3 >3 450A -
451A 93 - <2.0 10.6 .
93 <4.0 10.6 . . , >3 >3 452A -
93 <4.0 10.6 . >3 >3 453A -
<4.0 10.6 .. >3 >3 454A 93 -
475A 166 - 2.96 8.4 . >3 3 Baynard(BUL79-02)D75 g.} ,-
ENGINELRING SAll LUARD SYSH.f's Nge 5 of 6 SYSTEM AS BUILT RLDESIGN Nita NO. RDR NO. NCR fiO. F 3
F s I.<2
. 2 <l s<4 PU's UP DN SWH-478A 93 - <?.0 10.6
<4.0 10.6 * ;!:A >3 480A 93 -
<4.0 10.6 3 >3
<4.0 10.6 * '3 >3 431A C3 -
0.71 5.1
530 18 -
2.0 15./
1.P 6.5o
2.4 H . .) * !;,A >J 24 8 -
3.4 8.3 >3 >3 12.0
- 26 97 10 1.05 31 107 4 3.4 61.0 * .3 >3 8.0
3.28 >3 >3 72 .3 1.2 .
2.4 100.0
- s3 92 5 - .4 Clili-13 </.0 22.0
21 12 -
<2.0 21.3
- 1. (>
99 2.0 15.3
3.5 24.0 * >3 >3 37 123 iD 39 179 -
4.64 57.2 Rii >3 >3 CllR-3 122 lu 0.0 154 MSit-Illi; 43 IB <?.0 3.4 192 1 2 2.4 10./ ..
>3 >3 245 113 IB 2.5 38.[I A >3 254 29 3 2.9 11.. -
>J' >3 1.0 13.0 *-
546 90 3 ,
239 325' Baynard(BUL79-02)D75
Tit!N-Ef;GINil RING SAf 1.GUAdD SY5 f t M5 N g. 6 o f 6 SYSTEM AS BUILT REDCSIGN NhN fiO. RDR f;0. NCP fiO. F F I s <2 2<f s<4 PUS P UU 3 s h.. _- . . _
LRH-2bA 84 IB 10.6 16.4 .
36 34 -
3.1 12.4 e 3 2 37 2.9 10.5 e 2 ?
38 -
40 39 -
2.9 6.9 e c 3 2.77 14.6 . 3 >3 43 54/62 -
LRR- '
1 1:44 15 <4.0 '. 2 . 3 e !M 9 3 -
3.48 9.4 e 3 >3 10 131 lE 1.9 32.1 e FDH-66 89 1C 3.8 15.0 e >3 L 83 161 IL <l.0 192.0 e SFH-523B 48 - 0.6 8.5 o 525 91 10 2.4 13.25 e >3 A 527 11 - 2.9 9.9 e >3 >3 533 23 10 ?.3 8.1 e >3 s3 570A 20 - 2.5 9.0 o >3 IBA 638 33 0 3.1 9.7 e >3 >3 691 46 - 2.0 8.8 e SFH-10 167 1: 2./ 25.4 e s3 >3 1E 2.6 9 . c. . 43 >3 32 J 's 3 57 40 0.6 8.0 o FDH-76 175 14 <2.0 208 o 80 176 14 <2.0 90.4 e 82 1/7 14 <?.0 4ho e . .
2393326' Baynard(BUL79-02)D75 e
I C. 4 t O
( .
.d N. .,
.i...B..~_ _ . - . , _ . . - . . . . . . . . . _ _ . . . . . . . ...
. l
..i s;
1 w,1
!c .
Is,._t.,-........-
Ti .-.. - -. .... - - - - - - - - - --- - - -- -- --- --*. .
t.
- c. i 1 We-O h' .
N .-
e eD GG
. . _ . . ... - .~
_Lg-ea
- l. -: .
%l C'
- r. .
oo _ . .
i
'..]s C C*
- N, 4 H 4 o?'
. I U
w IIg . ,
W i1
~ [.a s . . . . .
~: , . . _ , . . . . . .... . . - .
w w
>: ,j m t W. tf% D L. O p **
)W %
CO 'O
O N* ..
W *.
g ,
t/)
C1 e .4 C")
t.
l -...- .-. . . - - . . . . . -
p-
}
m Ne I
c.
1 N'h
..g . . . . . . ... .. . - - . .- e. - -- _. . - - -
lI e' e
'(e O
2393 327 '
~ ,, ,
o, -
"/. ,g b ' ,i d (O 0l en c.3 .
I 8
' C.'
c u u m tn - --
w.b ...M... ._..M.... . . . . . - . . . . . . . --
"I
i ~ .
(
.V .
. 4, 4.;
al
,s
n b-m.l o.
s.L'
<l L _t __
.l,
,~,
T V,
N
- 1
_I.-..-..... - . _ . . _ . - . - . . - . . . . -.
e.
E
%.I.
>'. c
,[ i N m._:
p q,.. . - _ _ . . _ _ . _ _ _ . . _ _ . . . _ _ . . _ . _ . . .
Mj t U, h!.
~;
O)e V
l %4 l- 4 [_.- . . . . . . - - . - _ . _ _ . . . . . . . . ..
O.
N,
- s. .' , ._. . . . ~ . . . . . . _ . . . . . . _ . ~ . - .
en
i I s,'
'.1 .
i -
,.1-.. .
i.
. l ...
Ce.
- o m , ,
., 2390 328 .
i, _m ,,.-. . . - - -- -
_l .
b D u r- o O i o c1 .
U l
3 C' '
cj ;.;
U b .e- .
. =
( g
=
=
g =
. =
I -
s i :,
s .
' E t
g
l '. N. .
.i. *. ' t . . . . -- .. . ... . . . .
F 0 .e ,
l L.'
s 1
L_: L _ _ . .. _.____.. _ ... _ -....._. __. . . . . _ _ . . ._ . _ . .. ._. - _ . .
i
,9 t-)
Nj
.~.
k_
1 e
%6 c'
e d
. . , ..j
_I .-l . -- . . . . . . .
El f .
Tl r-e;
-.i *
o.
i
.s ;
... g 7, ,
I. c' .e l N Cs 4
.f
~ . -- - . -. - . ~ . . ~ . - - . . . ~ .
( '..$.. . ... .... .. .. . . . . - . . - - - - . .~. .
I c;
N 3'4 e
.t 1 9-i.I .s .- -- - . - - - - -
...i._.....~. ..
,.,. l *
r'! .-e m
to al
. -4 tw N
-O r1 re 67 co O
r -.
-I r- M ,
Ol V. , O w e .-e e e a .4 ,,
,,.I._. -.
O. '.
e' 'f 6 ,J N c o w N
ei cT O O .-* es e4 in g a, l .+ ..e .4 .- e .. a . .e u) .e c.
r I, 8 8 8 I 1 8 8 g:8 ..
r, U *
, ; O -
6- . . . _ . . _ . . . . . . . . . . . . . . -
o k
( l
- .A
=..
%; g C
1 I I
I, c:
I,.1..,,.,.,...
.: .. ~. .-- - . . . ..
-- - - . - - - - ~ *----
l 6 1 _-
s m c .
P.
O
%. . _m l , ~- -- - - - - - - -
?..L_..---.-.-- . - - - . . - - . ---. - -. .-- --. - - - ---- - -
- j - . .. -- - - - -
?.
sI e.,
(. ,
~
.3
. c l. .
l s.l .
.=
. > . t :,. m.
4 .,3 _. .
'O l r?. g \.
~
= _
.(3 ._
.~. .
- 1 . .
a c,4
~~..
m _
- s. l. ,. _
_l....._-.-."_ - - - *--"-~^ '~
- ~ ~ - '
, . *. i
- i
=
239] 330^
l .
L1- =
a
..I
=
- - - - - - - - - - - - - - - ~ ~
l .
.n 4 er. c. a.1 4 t/1 to O CJ to to .f o t'1 O -- e .s 5
m c. ea o a o O ci r1 in o . .?
- D 3' . 4 o e a ** -4 .4 .* a .. C' O O O O -4 .-4 . -4 --
_ ' .l. O. . -. .-. .-
l o.
=
e r.4 ci .. cr. ,es
.9,. t-r i ..'
D9 o e .c . , - o o o 4 ci s r- 1 o ti ti -* p- .*
g Ol i, o o o in in te. .
I I I I
, 3, 3 3 5 8 8 I I I I a 8 C :
O.- . . .
- o. _ . . . . . .. . . . . - - . .
I
e f-l' .
's 4
.;I .
'l c
W g' a.
I
. . . . = . . . . . .. . . . . .. . . . . .
en en e
r-s O
o k-... . ... _ .. . _ . . . - _ _ _ _ - . . ~ . - - -- - ._ . . . .
.1 Y
s I'g
~. 4 I
C.
N c.'
L ~.
.e N. i l .. . . .
- v. ,. ); _- l . .. . . - . . . . - . .. ..
vs .
g D4 s I'l a:t i
! [I 1 t. l 4:i .... .__. .....
.._L -
O e
N, W
I a - -- - -~~ - -- --- -
r------------------
i N. 4 m
2393'331 s s'
- ._H, -.... . . ..... . . .. .. . . -. .. . -
n e
M co ~..
r a v4 sn g 'l s -
OI
. l.
.-,.I e c O
. ', l r-) eq
.- .n Pl . g -
(.!
.g-
.'i l $s 1 M . . .. . .. __.
( .
5
~ -
=
C,I -
i ,l I
i r-t 8
C t-l ', .. m . .. . . _ . - . . _ _
. ,l cy
~,
C~
L '.
w.
,- t
~
, c: 'i
- 9 t-y .i L: ::
t .1 1
- =; ,
en ,
A C t-g, w'
CI L '.
w
.9 i
G.
m_,
c\ .
ti 2393 332-eq m
.l l 9 O - - *. * * . . . - - -
6 . ~ . . . . . .
w s_.. ._.
I
~/. i i
O';l c- .,
- i m
--l O
o-La e C e
.._L:a.-.-.---...... .
4 e
e
( m .
~ ,. .
4 0I
~. 'I.
. _ . . . . . . -. . . . . . . . . . _ _ . _ . . _ . . . . . . _ - . . . . . . . .. . . . . . . . . . . . ~ - . - _
C L ',
~.
i r.
~.
q L-
~
.. . ,y _..__.. ... . _ _ _ _ . . _._ ___. .... . _ _ . . _ . _ _ _ _ _ . _ . . .
l
.a l o
si.
c .
. s. .
m
=
w..._i.._..._.:. ,
L ...
~s :
- m. .
- s. n.;
T_
i i
O.
N O,
.t - 1.i
...g . . . .. . . _ . - . . ,_._o..__..
A.
t m .
b .
i 239) .
333-
~
l .I . - . . . . . ,.
p.s._.~. . . . . .
I.
I
.I ci ss
,.i.,m o. ..
C' CJ f;. $ (. b.
j o
.I
.b. .
c n e .1 la q) st m
-4 .-g e C., l c .- : : ,
c '
G -
,.P.'.b._.........._.
a el ,
f I .
~.
.. (.
.. 4
.l
) 1 C-l te s' .
, .j . . . ...-... . .. . . . .. . . . - - . - . . . . . . . . . . . . - - . - - . -
i t-5 c-L.1 l
. - - . . - - ~ ~ ---
Si - - . - . - - - . . . - ~ ~ . - - . . .- . . . - . - . . . -
. .l a..
'l E
.L f
.1 u.-
.lp-..-.. - . ~ . . . - - - - - . . . . - . - . - - ..-- . . -- -- --
t sif l t4' I
i c. '
l g.
'Nl en,t
- f. ::, . . - . .
mg 1
. e til t'l P *
.'t C'" e.
9
- g. -
E N.. g
,L --.--..em_ .
So
. =
O =
N ".
C .
5.
t =
t.: =
s .
%.1 f _.
m .
N =
~ T r, n 2-cc - J J; k
~
~ $ J / J 1 .,, .
l p_i. ..a., s.. . . - _ . . . . - - - - - - -....- .-.. . ....--..... - - . - - - . - - - . - - - - - - - - - . .
1 s
01
(A cc ~2 N ~! nn ~1 m 69 C CO CO CO .f
') l
(-
.D. .
0 03 m vs r3 en k4 U l n I 8
.J I
(4 B
CT B 3 C:8 L c' g) c: ' p
~;l. . . 3'- . . - . _ . - . ~ . . - . . d..- - - . - . - . - . - .
f.'
~. ,
( .I.' .
. . i.
'1 C
I N
i~,I I... . I - * - - ~ ~
\ ..I _ . . . . . - - - - ..- . . . -
l Q
m ..
=
~.
1-
. _I ....._ 3 ._ ._. ... ... -
... . .. . . ~ . . -- --. . . - ..
t i, s -
c
.. l,
- n. t. : - . -. .
m.. , i_ .-. .- - .- ...-... . .- - - - -..-
in l t g,i
.+
r 'i .I sCs' L. '
...a .e..ee. ..-.s.==*e. . . - . . > . . * - - - = - = = .. . - * .
i,w .
C1 N,
en i
i t....,
- ~.- " - -
e-,
J m,1 239') 335 1 ..e -
L c.:..
... ~
I, t
.I O l
/
4 D.- e C. n b $. $.O
(' 8 et el o a ~
.I
.r, i s.'
kJ S* C' II) *I ty . . m o e
i E 8 C '. d .-
- - ~ - '
. . . ~.
\
f .
4.
-t ,' .
l o., . .
c .~.
.e
.I .f 3 .
t_..
. . ~ . . . . . . . . . . . . . . _ . . . _ _ . . . . . . . _ . ...
~
C =.
_t. .
,i- _t _ _ . . _ . .- . _ _ _ _ . . - . . . _ . _ . . . .- . .. . . . . . . . . -
r L' .
s.
- c. .
~
( 0. . .
. v ,.
=
. -J, .
m i
i r .l,
~,.
(*4 11 N.
i _. - .. . . . - . - . . . . . . - . . . . - _ . . .
C*
N.
C'I
.m
- .: - . _ . . . . ..,. _. ....-.. _- ....... . _ . ~.
E 239J 3.56' t.1 -
. ~ ' ' '
. - . . ~ . . .
.C . -
9 (4 (N h lN b () %f @ (I r *4 ,g 6 1 L) C' ri r1 4 4 ee .- ti sai C.Ij '
o t_s O 4 . e4 c. .4 .. . . . . ..
gp* . ... . .e 9
O
' e', g' ea
< o e in 1 a r3 ei (9 c 9 t#1 ** m ern es nr% s.) ,1 ~ e. ,
(8, C l- t/ l m O Cl et) o, g'i o 8 8 8 8 8 I 8 8 5 h)9 .f.
rj (i
- t. *=.
Le. .*
=.we.. e .i... . a. . . ..
4
c _
~ .
n.
,.w . - .. ... .
=. . . ... . ._ . . . . .
J.
s.
C I
u.,
C,,i l
.t. ,
'~ - * *-"
g ___ .- .. . ... . . - . - - ~ - - ~
.. i.
)
Ni.
m I
t )
N. .q (A.
s e
/.
t_J 1. '
[ 0, %j v.i , _ . . _ . . . . . . -
M;g i O'
n r.
N.
m L'
..J
. .. . . - . . . . . . . . . . . ~ . - -.
0 t i,
~. o. '
.. - . - - . . . . ~ . . - . - = - - . .
- 23M 337 I
u-
.e .. . - -. - - - - ~ ~ - -
. l . . ..- .- . . . . . . . . . - . . . - - . ... ..
t
.I o .
/.
CI (4
c.
pg nn #
4 C '* ee e< . - -
0
(
..t O
$ . **e
(; ) ci kt' c' ri -j tl g g
<J u w
, . .Y . . .. . - .... . . . . -- .
t e'
%. l 0
L e
I .
,. .s i, --
l , =. . . - - - - . . - . - . - . . . . . . .
a
- I N
c l t
.l .J' . . .-- - - - . . . - - . . - - - -
1 . I .. . . . .. . . . . . .
t-i 0-ti s.
- - - -* ** * * * ~ ~
.-... -. . . . - - - - + - . . - -
. ...i _ . ...
t w,
7 g..
e ' ^***
. . -. - . *~~ ~ ' ' " * * * -
_ _ . .w.. . . . . . . ~ - - . . .
s t C4
-J c
b4O
- 'I ( l' l! *%
~. ~ - - - * ' - -- * ~ ' -
. . . - - . - . - - - - . a. . ~ --
f0* _ & _ . . _ ... -- :
me e.
h, b =.
e O e a
c". e.
a.
5 t1 e.
s
.% 9 m 4 ee e.
e e
=
Ci =
e4 gg N e CC e o
a
=
11 "
N [
- i e ~. .. . . .- .--. . . . . . - . ~ . - - - - - ==-.
' _,se..,. . . . .. . .
E f1
n s . 4 O 'ani CC
~.
J/J f..
t;I N..
e
_ _ _ - . . .-. ...---..-....-...,-----.-~~ - --
l :
O
-e O rq m a eq h f,; ~ es en en o. c c
_' C O O O O . . . O. +
n
- - -- ~.- --*---
O
- ". .c en P. O f7 c) b'1 C'4 h M 'T) (4 04 C7 O to O t1 ($ M 07 s1 C- I 8 5 I I 4 8
Le e k w..-
C.* -'A.-.. . . . . . .
. (n.
l-( .
i
,C I e
a .
- =
A a
8: ..
~.
_. i ._ _ _ . _ . ..__ _..__. _ .
g i "_
,c ci .
.e . , .
, . . - . _ . ..~___
i
- a s c>
Erl I N [
- m. c m,
<g.- :
I .
. ... .- .ep.. .. .. . . .
,,L,........... .
.i r,
.m .
=
., s n -
0 f.a i: _
q .
.q
. . . ,_.. .=
e :
.4 P
~,
u =
_c., . .
, m :
~ .
m :
~ _
1~.
.i
' 239) 339 01 M c- c. .. 4 ir , o r- ro en e o c' o en c '. r> i.! j, ' ', ' ' I i
- t. ci o
..e.fhf pu
'" esh er
" l e
T b t
3-
/. '
" nh
.l l x e
ot
" i s in 8- " t
/ 8 i
l e a ,n. th
?, " u mpi
' i.<ti t g
,i,"'I- !!. ,ii j;' , . ;i Il f
.! !t!
i "
t an t
c r 4 " t e - er h np odi i
2 2 ot
/. "
". . 8 t c, r G- " naf no A " o o - t r c P.. g "
i d t e- ua
.,l,iil
' " f ' ,I,i ;!1i .i!ji :': ,i' i 8 a
r r i pt d,f j.,. s e o1 e M_ - . pf il t T 7- orbb e S :. eiif
/ g ps s a
'i P I n s s t S_ " i e e e
'4__ t " rh c ce u c ct j ' d1 aaa
'S '.- _ 1 i lji . ;;!- I!iili. tit lil !i .t ' *" l *'
l wh op b t no r
is -ee ep 0 svnr p 1
eri aa
/
8 c um 8 csrheciei
" a nt it
" " o o .h
/ . '" .'b,i id j .wo g {i '!
'?.-,fa .llij 3'sl ritj .;: , ;t- I . . . , - l* I t o s .
o a. t r < o n! -
. o'
. d - l 3 r r -i t
/ a e a r u 8 MA wh g O
/
!n;.il;!i :: ; ' - 4 : ' .I .' ! ' f .t)iII l ; , i!.i lil!
a) >
.m b "g C-us o
N 2 3 3 3 3 3 7 3 3 8 3 ,w 3 7 0 2 9 9 9 9 9 0 ? 9 7 0 n- 1 7 0 5 0 0 0 0 0 0 0 0 0 1 0 nw 0 9 1 1 R ' .
~ . :
lI' i' o -
N A A 'A A A A A A A 3 9 0 1 4 2 7 9 3 r 0 c 4 7
4 8
4 8
2 5
4 3
1 0
4 0
4 0
1 2
9
,O ow 5
1 g3 1 6 s
m
- r. P
- t. 2 7
H S i.!, i!ill'} , ,: ,> t S; i .'!-i *
. I :!l
RESI'ONSE TO I NF01 " At. NRC Qllu;I loMS Question 1 Provide a detalled listing of hangers with a safety factor less than 4 and their proximity to other hangers in the system.
Response 1 .
This information is provided in Table II of this submittal.
Question 2 Indicate wh ich ha ng" rs with a safety factor less than 2 are on 1:n ,i nee red Safety Feature Systems (ESF).
ES_s_pon s e ,2 This information is provided in Table 11 of this submittal.
Question 3 Provide description on the testing of redhead anchors at CR #3 and insure they are compared to a 5 to 1 safety factor.
Response 3 .
Shell type (redhead) anchors were tested by insuring bolts were not bottomed ou either threads or plugs and that the re was at least 1/8" between the shell and plate or backing unit, then applying a tension load on the bolt by torquing to specified valves. The shell to plug distance and shell recession were also raeasured. Shells were accepted Lf the shell to plug distance indicated the shell was teated according to manufactor.ar's data. A pre-load was applied to all shell type (redhead) anchors included in this test sample equivalent to five times the analyzed design load or great e r.
Question 4 Provide detailed information or the method of analysit used to est ablish the present safety factor and the new safety factor.
Response 4 All seismic 1 (SI) supports or seismic III supports ad jach t to SI systems (SIII/1) on large bore (2-1/2" or larger) piping that have concrete expansion anchor bolts were analytically reviewe,'. The analysis considered s t ruct ural adequacy for all membe rs, welds, and 3 y expansion-type ho'ts.
In gene ra t ing the load rating, the most conservative geonote ry conbi na t ion of the maxinun distance from the pi pe to the sttoeture was used fu connection with the smallest allowed spacing between anchor bolts which resulted in the wo rs t load case.
WPSemhF01 ,
D43
. Responne 4 (Con t '.I)
Mos t supiu rt s were .u 11yzed wi th r i;; I plate analyslu at the ons l . :iow 43 supports were reviewed ut ilizing the flexible plate analy,i, at the o n'.e t . For those . supports that were checked using th: flexible ,' late analysis (FPA) and yielded saf ety f actors greater than 4, no a.blitional cons iderat ion was c,1 ven provided a non co n f o rma n c e report (NCR) eu not issued. .
For those supports t h:it ut ilized the rigid plate analysis (RPA) t echo lque and yielded safety factors greater than 8, no PPA war, considered.
Justification for this approach is based on supports for which RFA and fl%
techniques were utilized and determined that the FFA technique did not reduce the safety factor by more than a factor of 2.
Supports that were checked using the RPA techulques that yleided safety f ac tors of between '. and 8 were then analyzed with the FPA techalque.
Safety factors of 4 or more based on FPA were conaldered satisfactory, provided an NCR did not exist.
Supports that were checked using either the RPA technique or the FPA technique with cafety f ac tors less than 4 were re des i p,.icit to yi. id final saf et-f factors that are consistent with the approach de cribed asuve.
In all of the above cases, NCRs were considered. As of this dat e , field verification of alI supports has been completed. When they were reported, analytical determination w s made that the as-built co n fo ras to the m
approach described above. ,
All supports associated with NCRs or RL)Rs (redesign request ) have bee n design ve ri fied to assure compliance with lli 79-02.
Question 5 Provide a more detailed schedule of the hangers to be upgraded an.1 also thei r acces ;ibility durlug operat ion.
Response 5 A det lied schedule for modif icat ion to each hanger, including accessibility during operation, is included in Table ill of this submittal.
Question 6 l>e sc r i be the difterence he t ween the original design a n.1 t . .da v 's ilo lgo thar is causing so many redesinns. -[
Response 6 The need for redesign of hanger at CR /83 can be summarir ql,into 3 main categories or reasons-
- 1. Inadequate installation resulted i n 63 Redes ign Request s (RDR).
WPSemhF01 -
D43 h} jf
1:es p.in..e t. (i:o I ' .t )
- 2. I;ighty five'(85) RDRs were result ot underdesign for the calculated loads.
- 3. A change in the prying criteria (11exible vs igid pl.it -)
resulted in 20 RDRs.
Th e : ,.
- redesigns were a direct ren u i t oi 1- 4'C 's iles i gn , e s i t I c.it ion n1 approximately 1670 hangers and the new flexible plate criteria.
2395343
/
WPSemhE01 -
D43 N