Letter Sequence Other |
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Results
Other: 3F0198-34, Forwards Summary of Evaluation of Dynamic Effects of Pressurizer Surge Line LOCA Other Systems & Components,In Response to NRC 971222 Rai.Commitments Made by Util,Encl, 3F0298-17, Forwards List of Commitments,Conclusions Presented in 980130 Telcon,Description of long-term CAs Required to Resolve Conflicts within FSAR & Summary of Previously Docketed Correspondence Re Protection Against Effects of LOCA, 3F0697-13, Responds to to Update NRC on Ifi 95-15-02 Re Protection Against Dynamic Effects of Loca.Insp Completed & Summary of Field Insp Results, 3F0997-01, Submits Suppl to NRC Ltr Re Protection Against Dynamic Effects of Loca.In Addition,Issue Being Tracked by NRC as Inspector Followup Item 50-302/95-15-02.W/one Oversize Drawing, 3F1197-29, Responds to NRC Expressing Concerns Re Basis for & Conclusion of USQ Determination for Resolution of Jet Impingement Issue Provided on 970929.10CFR50.59 Program for CR-3 Sound & Effective, 3F1297-05, Forwards Rev 0 to Calculation M97-0121,IAW Commitment to re-evaluate Conclusion Re LOCA Effects of Jet Impingement, ML20147J251, ML20198H970, ML20211P928
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MONTHYEARML20147J2511997-04-10010 April 1997 Discusses Plant Unit 3 Re Licensing Basis for Dynamic LOCA Effects.Requests Info for Resolving Ifi 95-15-02 Project stage: Other 3F0697-13, Responds to to Update NRC on Ifi 95-15-02 Re Protection Against Dynamic Effects of Loca.Insp Completed & Summary of Field Insp Results1997-06-0505 June 1997 Responds to to Update NRC on Ifi 95-15-02 Re Protection Against Dynamic Effects of Loca.Insp Completed & Summary of Field Insp Results Project stage: Other 3F0997-01, Submits Suppl to NRC Ltr Re Protection Against Dynamic Effects of Loca.In Addition,Issue Being Tracked by NRC as Inspector Followup Item 50-302/95-15-02.W/one Oversize Drawing1997-09-29029 September 1997 Submits Suppl to NRC Ltr Re Protection Against Dynamic Effects of Loca.In Addition,Issue Being Tracked by NRC as Inspector Followup Item 50-302/95-15-02.W/one Oversize Drawing Project stage: Other ML20211P9281997-10-0909 October 1997 Discusses Submitting Results of Analysis of Potential Dynamic Effects of Pressurizer Surge Line Following loss-of-coolant-accident on Svc Water Sys Piping Project stage: Other 3F1197-29, Responds to NRC Expressing Concerns Re Basis for & Conclusion of USQ Determination for Resolution of Jet Impingement Issue Provided on 970929.10CFR50.59 Program for CR-3 Sound & Effective1997-11-0707 November 1997 Responds to NRC Expressing Concerns Re Basis for & Conclusion of USQ Determination for Resolution of Jet Impingement Issue Provided on 970929.10CFR50.59 Program for CR-3 Sound & Effective Project stage: Other 3F1297-05, Forwards Rev 0 to Calculation M97-0121,IAW Commitment to re-evaluate Conclusion Re LOCA Effects of Jet Impingement1997-12-13013 December 1997 Forwards Rev 0 to Calculation M97-0121,IAW Commitment to re-evaluate Conclusion Re LOCA Effects of Jet Impingement Project stage: Other ML20198H9701997-12-22022 December 1997 Discusses Plant Protection Against Dynamic Effects of Loca. Based on Evaluation,Nrc Find Util SW Piping Operability Determination to Be Acceptable Project stage: Other ML20197H3151997-12-22022 December 1997 Rev 19 to AR-401, PSA F Annunciator Response Project stage: Request 3F0198-34, Forwards Summary of Evaluation of Dynamic Effects of Pressurizer Surge Line LOCA Other Systems & Components,In Response to NRC 971222 Rai.Commitments Made by Util,Encl1998-01-23023 January 1998 Forwards Summary of Evaluation of Dynamic Effects of Pressurizer Surge Line LOCA Other Systems & Components,In Response to NRC 971222 Rai.Commitments Made by Util,Encl Project stage: Other 3F0298-17, Forwards List of Commitments,Conclusions Presented in 980130 Telcon,Description of long-term CAs Required to Resolve Conflicts within FSAR & Summary of Previously Docketed Correspondence Re Protection Against Effects of LOCA1998-02-18018 February 1998 Forwards List of Commitments,Conclusions Presented in 980130 Telcon,Description of long-term CAs Required to Resolve Conflicts within FSAR & Summary of Previously Docketed Correspondence Re Protection Against Effects of LOCA Project stage: Other 1997-04-10
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F9941999-10-15015 October 1999 Discusses FPC 970819 Request for Temporary Relief from ASME Code Section XI Requirements to Repair ASME Class 3 Nuclear Service & Decay Heat Sea Water System Piping.Forwards SE Containing Results of Staff Review ML20217J5171999-10-13013 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Plant,Unit 3 & Did Not Identify Any New Areas That Warranted More than Core Insp Program.Previously Planned Regional Initiative Insp of safety-related Mod Will Be Performed 3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999 Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed 3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999 Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made ML20212L0771999-10-0404 October 1999 Forwards SER Accepting Licensee Relief Requests 98-012 Through 98-018 Involving Containment Insps at Crystal River Unit 3 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(a)(3)(ii) ML20217D6551999-10-0101 October 1999 Requests That Natl Communication Sys Arrange for Licensee Participation in Government Emergency Telecommunications Service,Per NRC Info Notice 99-025 ML20212J8481999-10-0101 October 1999 Forwards Safety Evaluation Re Second 10 Yr Interval ISI Program Requests for Relief 98-009-II.Reliefs Granted for 98-009-II,Parts B & C & 98-010-II & 98-011-II 3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999 Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment 3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999 Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331 ML20212F7251999-09-23023 September 1999 Discusses Staff Review of Util 980330 Response,As Suppl on 990514,to GL 97-06, Degradation of SG Internals. Staff Concludes That Licensee Responses to GL Provide Reasonable Assurance That Condition of SG Internals Acceptable ML20212F7331999-09-23023 September 1999 Discusses Util Licensing Action for GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants. NRC Ack Efforts Util Completed to Date in Preparing Crystal River,Unit 3 for Y2K Transition 3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999 Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46 ML20212E6741999-09-21021 September 1999 Forwards Safety Evaluation Accepting Proposed EAL Changes Submitted by ,As Supplemented by 981120,990713 & 0831 Ltrs,Incorporating Guidance in NUMARC/NESP-007,Rev 2, Methodology for Development of Eals 3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999 Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv) 3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999 Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief ML20212F3141999-09-13013 September 1999 Forwards Insp Rept 50-302/99-05 on 990704-0814.Violations Noted,But Being Treated as non-cited Violations ML20211L9081999-09-0303 September 1999 Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Crystal River Unit 3 ML20211Q7581999-09-0101 September 1999 Forwards Summary of 990812-13 Training Managers Conference in Atlanta,Georgia Re Recent Changes to Operator Licensing Program.List Conference Attendees,Copy of Presentation Slides & List of Participant Questions Encl 3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999 Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals ML20211G7111999-08-30030 August 1999 Modifies Approval of 980521 Request for Exception to 10CFR50.4(b)(6) & Grants Util Approval to Submit Copies of Future Updates to FSAR as Listed ML20211G7031999-08-30030 August 1999 Informs of Approval of Util 980521 Request for Exception to 10CFR50.4(b)(6),allowing Util to Submit Updates to Plant Ufsar.Ltr Modifies That Approval & Grants Util Approval 3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999 Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002 ML20212C1351999-08-27027 August 1999 Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input 3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999 Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71 3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999 Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3 3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999 Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05 3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999 Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal 3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999 Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2 3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value 05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999 Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented ML20210Q4511999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 ML20210P0741999-08-0505 August 1999 Forwards SE Accepting Licensee 980416 & 1130 Ltrs Re Third 10-year Interval ISI Program Plan & Associated Requests for Relief for Plant,Unit 3 3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999 Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603 ML20210G8551999-07-27027 July 1999 Forwards Insp Rept 50-302/99-04 on 990523-0703.One Violation Identified & Being Treated as Noncited Violation 3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999 Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments ML20209H5211999-07-16016 July 1999 Forwards Request for Addl Info Re Licensee Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in CR-3 once-through Steam Generators in Order to Complete Review ML20209G3231999-07-15015 July 1999 Forwards Biological Opinion Issued by Natl Marine Fisheries (NMFS) of Dept of Commerce.Nmfs Concluded That Operation of Cw Intake Sys of Crystal River Not Likely to Jeopardize Existence of Species Listed in Biological Opinion ML20209G3481999-07-15015 July 1999 Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon 3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999 Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl 3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999 Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl 3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999 Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl 3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999 Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held 3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21 3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21 ML20196L1261999-07-0707 July 1999 Discusses Closeout of TAC MA0538 Re License Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Unit 3 3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999 Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3 ML20196J4991999-07-0101 July 1999 Advises That Info Contained in ,Which Included TR BAW-2346P,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20209C0811999-06-25025 June 1999 Forwards Overdue Controlled Document Transmittals for Listed Documents 3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999 Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl 1999-09-03
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999 Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed 3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999 Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made 3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999 Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment 3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999 Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331 3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999 Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46 3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999 Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv) 3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999 Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief 3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999 Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals ML20212C1351999-08-27027 August 1999 Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input 3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999 Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002 3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999 Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71 3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999 Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3 3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999 Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal 3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999 Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05 3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999 Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2 05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999 Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented 3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value 3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999 Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603 3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999 Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments ML20209G3481999-07-15015 July 1999 Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon 3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999 Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl 3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999 Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl 3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999 Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl 3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999 Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held 3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21 3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21 3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999 Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3 ML20209C0811999-06-25025 June 1999 Forwards Overdue Controlled Document Transmittals for Listed Documents 3F0699-12, Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested1999-06-23023 June 1999 Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested 3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999 Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl 3F0699-08, Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments1999-06-21021 June 1999 Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments 3F0699-09, Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl1999-06-0404 June 1999 Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl 3F0599-21, Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads1999-05-28028 May 1999 Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads 3F0599-10, Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl1999-05-26026 May 1999 Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl ML20207E4341999-05-25025 May 1999 Submits 30-day Written Rept on Significant PCT Changes in ECCS Analysis for ANO-1.CRAFT2 Limiting PCT for ANO-1 Was Bounded by 1859 F PCT Calculated at 2568 Mwt for Crystal River 3 Cold Leg Pump Discharge Break Size of 0.125 Ft 3F0599-22, Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs1999-05-21021 May 1999 Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs 3F0599-18, Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM1999-05-14014 May 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM 3F0599-17, Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments1999-05-14014 May 1999 Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments 3F0599-07, Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 19781999-05-14014 May 1999 Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 1978 3F0599-03, Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR1999-05-12012 May 1999 Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR 3F0599-05, Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl1999-05-12012 May 1999 Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl 3F0599-08, Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments1999-05-0303 May 1999 Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments 3F0599-09, Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 19981999-05-0101 May 1999 Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 1998 3F0499-24, Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent1999-04-30030 April 1999 Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent 3F0499-09, Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 9907301999-04-30030 April 1999 Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 990730 3F0499-23, Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements1999-04-23023 April 1999 Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements 3F0499-18, Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl1999-04-20020 April 1999 Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl 3F0499-05, Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin1999-04-16016 April 1999 Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin 3F0499-08, Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 19981999-04-16016 April 1999 Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 1998 1999-09-27
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we Florida fgggpr
- .0: Je September 29, 1997 3F0997-01 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001
Subject:
Protection Against Dynamic Effects of LOCA, IFI 95-15-02, Supplemental Letter (TAC No. M96604)
References:
- 1. FPC to NRC letter, 3F0697-13, dated June 5, 1997 l 9. NRC to FPC letter, 3N0497-12, dated April 10, 1997
)
Dear Sir:
l Florida Power Corporation (FPC) is hereby submitting this letter as a supplement to Reference 1. In that letter, FPC committed to provide additional information to address the effects of jet impingement between the Crystal River Unit 3 (CR-3)
Pressurizer Surge Line and the Nuclear Services Closed Cycle Cooling (SW) System lines serving the Reactor Coolant Pumps (RCP) by September 29, 1997. In addition, this issue is being tracked by the NRC as Inspector Followup Item (IFI) 50-302/95-15-02.
As FPC stated in Reference 1, two items remained open for FPC to complete so IFI '
95-15-02 could be resolved. FPC indicated that further evaluation of jet impingements was necessary to confirm whether these possible interactions created adverse effects between the surge line and the SW System piping. In paragraphs d and e of Reference 1, FPC stated the following:
- d. Circumferential pipe ruptures do have the potential for jet impingement on SW piping associated with RCP-1A because of the free stream expansion jet produced by a circumferential pipe rupture and there are no jet
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impingement barriers between the surge line and the SW >
piping.
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. . U. S. Nuclear Regulatory Commission 3F0997 01
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- e. Longitudinal pipe ruptures also have the potential to result in jet impingement on SW piping associated with RCP-1A and RCP-1B because of the free stream expansion jet produced by a longitudinal pipe rupture and no jet impingement barriers between the surge line and the SW piping.
FPC has completed that evaluation of the potential impact of the jet impingement due to a circumferential or a longitudinal pipe rupture. FPC has concluded that neither a circumferential nor a longitudinal pipe rupture will adversely affect the SW System piping serving the RCPs. The results of the evaluation are presented in Attachment A.
Based on this evaluation, FPC determined that Final Safety Analysis Report (FSAR) changes will be required to clarify the licensing basis for ruptures on the pressurizer surge line. First, FSAR Section 4.2.6.6 will be revised to state that longitudinal ruptures were eliminated by following the guidelines of Generic Letter 87-11 " Relaxation in Arbitrary Intermediate Pipe Rupture Requirements."
Second, FSAR Section 14.2.2.5.11 will be revised to state that the fluid jet created by a circumferential rupture is limited to a 20' included angle consistent with Standard Review Plan 3.6.2, " Determination of Rupture Locations and Dynamic Effects Associated With the Postulated Rupture of Piping," and ANSI /ANS 58.2-1980, " Design Basis Protection of Light Water Nuclear Power l Pl ant s . "
l FPC has completed a Safety Assessment /Unreviewed Safety Question Determination (SA/USQD) on these changes to the CR-3 licensing basis. There are no Unreviewed Safety Questions as defined by 10 CFR 50.59. A copy of the proposed FSAR changes is provided, for information only, in Attachment B. The final form of the FSAR change will be submitted to the NRC in FSAR Revision 24 on or before December 8,
.997.
There are no adverse interactions between SW System piping serving the RCPs and the Reactor Coolant System Piping including the pressurizer surge line. The results presented in this letter and Reference 1 will allow FPC to close Restart Issue D-58, " Design Requirements for Dynamic LOCA Effects." The D-58 closure package will contain copies of the FPC letters discussing the issue, internal FPC correspondence related to this issue, and those FPC calculations used to resolve the issue. This material is available for NRC inspection.
The commitments in this letter are contained in Attachment C.
If you have any further questions, please contact Mr. David Kunsemiller, Manager, Nuclear Licensing at 352-563-4566.
Sincerel jfWhy.eudnL M. W. Rencheck, Director Nuclear Engineering and Projects MWR/jwt Attachments xc: Regional Administrator, Region II Senior Resident Inspector NRR Project Manager
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72 3F0997-01 ATTACHMENT A EVALUATION OF JET IMPINGEMENT EFFECTS ON CR-3 PRESSURI7sER SURGE LINE i
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U. S. Nuclear Regulatory Commission Attachment A 3F0997-01 Page 1 of 8 Introduction In Reference 2, noted in the cover letter, NRC requested FPC to document the results and resolution of any dynamic loss-of-coolant-accident (LOCA) effects on the Nuclear Services Closed Cycle Cooling (SW) System. Reference 1 provided the results and resolution for the dynamic LOCA effects due to pipe whip. Dynamic i LOCA effects due to jet impingements were the only remaining issues to be resolved. This attachment describes the results of FPC's evaluation of jet impingement effects on the SW System lines serving the Reactor Coolant Pumps l (RCP).
Current licensina Basis The licensing bases for potential impact of the jet impingement due to a circumferential or a longitudinal pipe rupture is defined in Final Safety Analysis Report (FSAR) Section 4.2.6.6, "LOCA Restraints," and FSAR Section 14.2.2.5.11, " Reactor Building Subcompartments Pressure Response." The bases are:
a Postulated circumferential and longitudinal pipe ruptures are possible anywhere within the Reactor Coolant System pressure boundary, a The break is assumed circular, with an area equal to the cross-sectional area of the pipe, a The fluid jet is assumed to be conical with an included angle of 30'.
I e Initial thrust is given by the initial pipe pressure multiplied by the cross-sectional area of the pipe. The pressure at any impingement plane is assumed to be indirectly proportional to the j i
cross-sectional area of the conical expansion being generated, i s
l' These licensing bases apply to the hot leg and cold leg Reactor Coolant System (RCS) piping. These are large bore pipes which involve the Leak-Before-Break (LBB) criteria and General Design Criteria (GDC) 4 exemption previously approved by the NRC for use at CR-3. As the NRC indicated in Reference 2, the RCS branch lines, such as the pressurizer surge line, do not fall within the scope of the LBB criteria and GDC-4 exemption. The present RCS piping design documentation for the CR-3 pressurizer surge line is not of sufficient detail to judge the extent of the application of two of the current licensing bases to the surge line dynamic interactions -- longitudinal breaks and jet fluid angle. FPC has reviewed the NRC and_ industry guidance on the application of methods to ensure that jet impingements from high energy lines do not interact adversely. NRC guidance which was developed after most of the CR-3 RCS piping design and analyses were performed do provide more definitive criteria for considering dynamic LOCA' effects.
~-. .
U. S. Nuclear Regulatory Commission Attachment A
- 3F0997-01 Page 2 of 8 The use of these later NRC guidelines will require FSAR revisions. These revisions are- necessary- to clarify the licensing bases for ruptures of the pressurizer surge line to be consistent with current NRC guidelines and industry analytical methods. Thai bases being revised deal with postulated longitudinal pipe rupture and fluid jet angle. The basis for each of these changes is
, described in the following paragraphs. As pa.t of this research, the CR-3 Operating License Safety Evaluation Report (SER) and its four supplementt (References 1 through 5 located at the end of this attachment) were reviewed to confirm that the NRC had not imposed additional requirements beyond those described in the FSAR. Revisions to these bases do not involve an unreviewed safety question because these changes implement analytical techniques that are consistent with NRC guidelines and do not conflict with methodologies already reviewed and approved by the NRC for CR-3.
Lonoitudinal Pine Ruotures A postulated longitudinal pipe rupture has the potential to result in jet impingement on SW piping associated with RCP-1A and RCP-18. This impingement could occur because of the free stream expansion jet produced by a rupture.
There are no jet impingement barriers between the surge line and the SW piping.
The guidance in Generic Letter 87-11. " Relaxation in Arbitrary Intermediate Pi)e Rupture Requirements," would allow longitudinal breaks on the surge line to )e eliminated if specific criteria were satisfied. Generic Letter 87-11, Section B.3.b(1) states
- Longitudinal breaks in fluid systems and branch runs should be postulated in nominal pipe sizes 4-inch and larger, except where the maximum stress range exceeds the 1imits speciffed in 8.1.c.(1) and B.1.c.(2) but the axial stress range is at least 1.5 times the circumferential stress range.* If CR-3 surge line stresses could be shown to meet this criteria, longitudinal breaks could be eliminated from consideration.
FPC performed analyses on the surge line to determine if stresses were in excess of the Generic Letter 87-11 limitations. To preserve conservatisms in evaluating possible surge line break locations, FPC used the CR-3 surge line stress analyses that were generated in response to-implementing the requirements of NRC Bulletin 88-11, " Pressurizer Surge Line Thermal Stratification." .The pipe rupture stress analyses show that all postulated breaks in the straight pipe sections and the elbows of the surge line are circumferential breaks. Possible longitudinal break locations on the CR-3 pressuriter surge line do not meet the Generic Letter 87_-
11, Section B.3.L(1) guidance for consideration as breaks.
Therefore, FPC will-revise the licensing basis for pipe ruptures in FSAR Section 4.2.6.6, "LOCA Restraints," to state that FPC analyses have eliminated longitudinal ruptures from consideration for the pressurizer surge line based on the application of Generic Letter 87-11. As stated in Generic Letter 87-11, licensees are permitted to implement the requirements of this generic letter unless such changes conflict with the license or technical specifications. FPC's review of the CR-3 Operating License and the Improved Technical Specifications indicates that they do not contain any requirements that conflict with these licensing basis changes. The proposed FSAR change to Section 4.2.6.6 is included in Attachment B.
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U. S. Nuclear. Regulatory Commission Attachment A 3F0997-01 Page 3 of 8 fluid Jet Anale A postulated circumferential pipe rupture does have the potential for jet impingement on SW piping essociated with RCP-1A. This impingement could occur because of the free stream expansion jet produced by a rupture. There are no jet impingement barriers between the surge line and the SW piping. This conclusion of a potential for jet impingement on SW piping was based on the requirement for a conical fluid jet with an included angle of 30'. Figure 1 in this attachment is a simple isometric drawing that shows the surge line circumferential break locations of interest for this discussion. Break location #4 is the most limiting break for impact on RCP-1A. This break is at the maximum distance from the target pipes where the expansion of the jet cone is the greatest. Figurc 2 (FPC Drawing 112826D) in this attachment is an isometric representation of the RCS showing the relative location of components.
FSAR Section 14.2.2.5.11 (page 14-69) discusses the jet impingement forces for large pipe break sizes (8.0 ft" and 14.1 ft*). It states "The forces on targets in the path of escaping fluids are dependent upon the size and shape of the l
target and its distance from the rupture area. Since the actual shape of the rupture dictates the flow field shape eing generated, it is assumed that a typical rupture is circular and the free stream expansion of the jet conical with an included angle of 30"." Cutoff distances (i.e., the distance from the break plane beyond which impingement effects naed not-be considered) and target shape ,
factors would have been used to determine the population of impingement targets i and effective applied impingement pressure. However, without specific details '
from the original CR-3 design documentation to define these parameters, FPC can not document the impact of a potential break location's fluid jet effects. FPC has chosen to upgrade the CR-3 analytical methods to follow NRC and industry accepted methodologies for establishing the jet angle. These methodologies describe the criteria that must be considered for evaluating fluid jets.
Much of the development of the methodolgy for analysis of dynamic effects of HELBs was a result of the Atomic Energy Commission (AEC) letter written by Mr.
A. Giambusso on December 22, 1972, that contained design guidance for HELBs outside containment and the May 1973 version of Regulatory Guide (RG) 1.46,
" Protection Against Pipe Whip Inside Containment." The techniques used to develop jet geometry prior to issuance of Giambusso's letter were based en experiments that did not consider the jet as a steam / water mixture (fluid jet geometry for impingement is not defined in either Giambusso's letter or R.G.
-1.46). 1he resulting jet shape was conservatively based on subcooled water or steam conditions (rather than a mixture of water / steam) and was conical with an included angle of 30', This is consistent with the jet geometry for RCS breaks referenced in FSAR Section 14.2.2.5.11.
Refinement of the CR-3 impingement jet geometry from 30' to 20' reflects developments in industry methods since the original CR-3 design. The standard jet geometry used for the evaluation of impingement e"ects at nuclear power plants, as defined in the Standard Review Plan 3.6.2, " Determination of Rupture Locations and Dynamic Effects Associated With the Postulated Rupture of Piping,"
~ -
e U. S. Nuclear Regulatory Commission Attc:hment A
. 3F0997-01 Page 4 of 8 {
and ANSI /ANS 58.2-1980, " Design Basis Protection of Light Water Nuclear Power Plants," is conical with an included angle of 20' (both Revision 0 in November 1975 based (NUREG-75/087) and Revision 1 of SRP 3.6.2 in July 1981). This shape is on analytical and empirical data and recognizes that the jet is a steam / water mixture. In addition, for piping breaks outside the Reactor Building, CR-3 follows the methodology in FPC's " Pipe Rupture Analysis Criteric Outside the Reactor Building," that has been reviewed and approved by the NRC (NRC to FPC letter, 3N0490-10, dated April 11,1990). It also uses a 20' cone angle. The development of NRC and industry guidance since the early 1970s for fluid jet angles leads to the conclusion that the difference between the jet angles in the FSAR and those recommended today for inside and outside containment analyses results from the vintage of the CR-3 RCS piping jet impingement analyses.
The current NRC guidance in SRP 3.6.2, the CR 3 HELB Criteria, and ANSI /ANS 58.2-980 can serve as a foundation upon which t jet shape half angle of 10' (20' total) can become the basis for a CR-3 pressurizer surge line rupture. FPC has analyzed circumferential breaks on the surge line and applied a jet shape half l angle of 10' according to the current NRC guidance and FPC's HELB Criteria. The l half angle methodology is defined by ANSI /ANS 58.2-1980.
Figure 3 in this attachment is based on ANSI /ANS 58.2-1980 and should aid in the following discussion. The methodology assumes that for a circumferential break with full separation of the process piping, the jet shape is a linear increase in radius from the initial break plane to the asymptotic plane at a distance of
, L,. The jet area remains constant at the asymptotic plane until intersecting with the 10' half angle. From this point on, the jet area continues expanding along the path of the 10' expansion half angle.
For CR-3, the asymptotic plane, L., is no more than 88 inches from the postulated break location #4 on Figure 1. The minimum distance from the break location to the SW System lines on RCP-1A that are of interest is 159 inches. The jet shape expanding along the path of the 10' expansion half angle will miss the SW System lines by at least 8 inches for the maximum pressure conditions defined in FSAR Section 14.2.2.5.11.
Therefore, a circumferential rupture in the CR-3 pressurizer surge line will not impact the SW System lines serving RCP-1A. FPC will revise FSAR 14.2.2.5.11,
" Reactor Building Subcompartments Pressure Response," to state that for the pressurizer surge line the jet is conical with an included angle of 20'. The proposed FSAR change to Section 14.2.2.5.11 is included in Attachment B.
Conclusions Longitudinal pipe ruptures on the CR-3 pressurizer surge line can be eliminated from consideration as part of the licensing and design bases in accordance with the guidance in SRP 3.6.2 and Generic Letter 87-11, therefore, jet impingements from this type of rupture will not occur. A license amendment is not required because this change does not conflict with the CR-3 Operating License or the Improved Technical Specifications.
U. S. Nuclear Regulatory Commission 3f0997-01 Attachment A Page !: of 8 Circumferential pipe ruptures on the CR-3 pressurizer surge line will not produce fluid jets that impact any SW System piping serving the RCPs. The fluid jet released by the pipe rupture does not impinge on RCP-1A using the assumptions from SRP 3.6.2 and ANSI /ANS 50.2-1980.
FPC has completed a Safety Assessment /Unreviewed Safety Question Determination (SA/USQD) in accordance with FPC's 10 CFR S0.59 program on these changes to the CR-3 licensing basis in the FSAR. There are no Unreviewed Safety Questions created by these changes.
References
- 1. CR-; Operating License Safety Eva'.Lation Report (SER), July 5, 1974, l 3N0774 01
- 2. CR-3 Operating License Safety Evaluation Report (SER), Supplement #1, 1 January 17, 1975, 3N0175-01
- 3. CR-3 Operating License Sr.fety Evaluation Report (SER), Supplement #2, December 3, 1976, 3N1276-09
- 4. CR-3 Operating License Safety Evaluation Report (SER), Supplement #3, December 30, 1976, 3N1276-10 j 5.
CR-3 Operating License Safety Evaluation Report (SER), Supplement #4, January 27, 1977, 3N0177-09 o
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. U. S.' Nucl ar Regulatory Commission Atthchm.nt A 3F0997 Page 6 of 8 PREESURIZER NORTH CONNECTION
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72 3F0997-01 ATTACHMENT B PROPOSED FSAR REVISIONS i
Strikeout / Shadow Changes l
l Text being deleted 4edicated by strikccat Text being added Indicif6dtby'ihidowing i
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The cases of maximum impinging velocity and constant force for side split and guillotine ruptures are investigated to determine the capability of the supporting structure to absorb the energy imparted to it. The allowable limit strain in the beams is incipient strain hardening of the compression-tension, stress-strain curve, this being the general limit of unsuported beam flanges as shown in Figure 14 of Transactions, ASCE Vol. 124, 1959. This results in an allowable ductility factor of 12 for ASTM A36 steel. Therefore, a design utilizing plastic mechanisms to resist the rupture thrust force will give satisfactory results for the structural system.
When a shear mode of response governs the situation, Hall and Newmark nave shown that the ductility factor for compact rugged structural shapes by far exceeds 12, 4.2.6.5 Pumo and Motor The RCP casing, internals, and motor weight are supported by the 28 inch coolant lines and constant load hangers attached to the motor. In the cold condition, the RCS piping will support the RCP and motor without the hangers. The structural portions of the constant load hangers for the RCPs are constructed in accordance with USAS B31.7 Nuclear Piping Code and/or MSS-SP-58, as applicable.
4.2.6.6 LOCA Restraints Each steam generator has restraints located at the elevation of the upper tube
- ,heet which transfer forces from the generator into the shield walls in the event of a circumferential rupture of the 36 inch line. Each 36 inch reactor coolant outlet line has a restraint located outside of and bolted to the primary shield to limit pipe motion in the event of a circumferential rupture of the piping inside the primary shield.
The design criteria which were used to examine the effects of pipe rupture did consider that postulated pipe breaks could occur at any location within the reactor coolant pressure boundary. Both longitudinal and circumferential type ruptures were evaluated. F6 rt hir iinilfs i siTd ocuins6tsdt i n* F PC TC al dul a t i onT 97 0090 T fel imi hitid %1 bng liisdi nalMty[e%ru p t u re s Q f roe M on s i dera t 16n S for$t hs Pres suri ze ri Surge Ri ne d by X fol l owi ng sthe i gui del i nesiof4 Generi cWetter > 87;lli "Relaxatioisin!Arbitrar Ihe~dssfgiiappF6ach~wa's/"to" design"each'c6lhionent~5hd cbmp'onhnt" sup worst break type and location.
The constant forcing function which was used in the design of pipe restraints utilized a force equal to one times the operating pressure times the cross-sectional area of the break. In addition, the restraints for the 36 inch lines were analyzed by the energy balance technique where the gap was taken into account using the constant forcing function. The RCPs were designed using a static analysis technique with a dynamic load factor of 1.7 times the constant forcing function. All pipes whose ruptures could cause deleterious effects on the other components or piping have been adequately restrained.
4.2.7 MISSILE PROTECTION The major components including reactor vessel, RCS piping, RCPs, steam generators, and the pressurizer are located within three shielded cubicles. Each of two cubicles contain one steam generator, two RCPs, and associated RCS piping.
One of the cubicles also contains the pressurizer. The reactor vessel is located within the third cubicle or primary shield. The reactor vessel head and control rod drives extend into the fuel transfer canal.
4-38 (REMXX).
, 14.2.2.5.11 Reactor Building Subcompartments Pressure Response (continued)
To simulate the physical model and to take advantage of the computer code, the entire system was conveniently divided into several lumped nodes. Each volume was given an average height depending on its lowest and top-most elevations in the actual system. An average cross-sectional area of each node was calculated from existing layouts and/or structures.
The control volumes were connected by two principal types of paths, i.e., surge line (pipe and critical flow check) and a leak path (flow versus area). The flow direction of each path was specified according to the physical understanding of the system behavior. When flow direction is uncertain, the program has bi-directional capability. Details of the mock-up of the whole system by control volumes (nodes) and the paths connecting each is shown in Figures 14-55 through 14-58. The control volumes (nodes) shown on these figures were selected because they represent the actual physical configuration w; thin the containment building.
The break locations in the control volumes do not affect C pressure response, and hence were chosen to be in the mid-plane of the pipe run.
To complement the above program application, several assumptions had to be considered in this analysis:
- a. Although the Flash-2 code handles two phase mixtures (where in fact there is steam-air-water), a modification was made to the code to simulate the initial conditions as a three component atmosphere.
Subsequently, during the transient a two phase mixture is considered.
- b. No heat transfer to the containment walls, floors, or equipment was assumed.
- c. Other assumptions remain intact as described in the Flash-2 report.
The highest calculated steam generator compartment pressures occur for a rupture of the hot leg pipe with an area equivalent to a double-ended break. This pipe is the largest in the RCS, and its rupture results in the highest mass and energy release rates. The blowdown rates were calculated using Moody correlation, with a Co - 1.0, as explained in BAW-10030, " Craft Descript'on of Model for Equilibrium LOCA Analysis Program," October 1971.
Jet Imoinaement Forces:
The forces on targets in the path of escaping fluids are dependent upon the size and shape of the target and its distance from the rupture area. Since the actual shape of the rupture dictates the flow field shape being generated, it is assumed that a typical rupture is circular and the free _ stream. expans. ion o.f _the _ jet conical with an included angle of 30*. An:excepti.onftolthistis:the. Pressurizer SUiis{l~iWE f6EwhithTthe ?jst?[i siconi c alNi tManEincl uded tangi s ;on 20 $as docume.nt ed ; i nj F PCi C al,cul _at i o n; M_97 - 00.91, Calculations of the force on an object is determined by assuming that the dynamic pressure (di - %C (V - V,)') developed at the rupture exit is for the maximum 3
mass flow and pressure conditions. Also, it is assumed that the pressure is inversely oroportional to the cross-sectional area of the conical expansion being generated. The dynamic pressure used for these calculations was determined assuming V, - 0.0 to provide the maximum dynamic affects since this velocity is dependent on the break conditions. . . ..
14-69 {Re_vp_XX).
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FLORIDA POWER CORPORATION !
l CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72 3F0997-01 i
ATTACHMENT C l List of Regulatory Commitments l
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U. S. Nuclear Regulatory Comission
. Attachment C 3F0997-01 Page 1 of 1 The following table identifies those actions comitted to by Florida- Power
- Corporation in this' document. Any other actions discussed in the submittal represents intended or planned actions by Florida Power Corporation. They are described to the NRC for the NRC's information and are not regulatory comitments. Please notify the Manager, Nuclear Licensing of any questions regarding this document or any associated regulatory comitments.
ID NUMBER- COMMITMENT IMPLEMENTATION 3F0997-01-1 FPC will revise FSAR Section 4.2.6.6, FSAR Revision 24 "LOCA Restraints," to state that December 8, 1997 longitudinal ruptures were eliminated by following the guidelines of Generic Letter 87-11.
3F0997-01-2 FPC will revise FSAR 14.2.2.5.11, FSAR Revision 24
" Reactor Building Subcompartments December 8, 1997
. Pressure Response," to state that the fluid jet created by a circumferential 1
rupture is limited to a 20' included angle rather than 30' as currently described in the FSAR.
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