Letter Sequence RAI |
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Results
Other: 3F0198-29, Informs That Util in Conjunction W/Framatome Technologies Inc,Completed Confirmation Which Includes Consideration of SG Tube Plugging Levels Specific for CR-3.Util Verified That LOCA Analyses of Record Does Not Require Manual Actuation, 3F0198-35, Forwards Complete Updated TS & Bases Pages to TS Change Request Notice 210 Submitted on 970614.Updated Pages Reflect Changes Identified in Licensee ,Correction of Typo & Addition of Footnotes, 3F0298-02, Forwards Status of Requirements Stated in SE Submitted W/ License Amend 163.Status of SE Requirements Do Not Invalidate or Alter Any Conclusions,Or Basis of Any Conclusion,Supporting TS Issued in License Amend 163, 3F1197-45, Submits Rev 1 to TS Change Request Notice 210,which Proposes Amends to OL DPR-72.Rev Addresses Changes Resulting from NRC Review of TS Change Request Notice 210.Rev Involves Additional Restrictions,Editorial Clarifications & Typos, 3F1197-54, Forwards Copy of Proposed Rev 5 to EOP-8, LOCA Cooldown, as Committed in, 3F1297-27, Forwards Response to 971126 RAI Re TS Change Request 210, Which Addresses Design & Licensing Basis Changes Primarily Involving Plant Systems Used to Mitigate Consequences of Certain Small Break LOCA, 3F1297-32, Provides NRC Requested Clarification Re Use of HPI Flow Throttling TS Change Request Notice 210.No New Commitments Made in Submittal, 3F1297-38, Forwards Addl Info on Validations of Proposed Emergency Operating Procedures Containing Operator Actions Related to TS Change Request 210,per 971203 Telcon, 3F1297-47, Forwards Response to 971219 RAI Re TS Change Request Notice 210,addressing Design & Licensing Basis Changes Involving Plant Systems Used to Mitigate Consequences of Certain Sbloca.Commitments Made by Util Also Encl, ML20199B738, ML20203C390
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MONTHYEARIR 05000302/19970071997-07-0707 July 1997 Insp Rept 50-302/97-07 on 970504-0607.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support Re self-assessment Rept on Health Physics & Radiation Control Areas Access Control Program Project stage: Request ML20216J9101997-09-10010 September 1997 Forwards Request for Addl Info Re Submitting Emergency Operating Procedures W/Proposed Changes to Reflect TS Change Request Number 210 Relating to Mitigation of Small Break Loss of Coolant Accidents & Design Basis Changes Project stage: RAI ML20199B4421997-11-0505 November 1997 Forwards Request for Addl Info Re License Amend Submittal & 970925 Re FPC Approach for Addressing Certain SBLOCA Scenarios Project stage: RAI ML20199B7381997-11-15015 November 1997 Provides Response to 971105 RAI Re TS Change Request Notice 210,proposing Amends to License DPR-72.List of Commitments Made in Submittal Encl Project stage: Other ML20199E3951997-11-19019 November 1997 Forwards Request for Addl Info Re Emergency Operating Procedures Tech Specs Change Request Notice 210.Questions Pertain to Operator Actions Described in Eops,Involving Mitigation of Certain Small Break LOCA Scenarios Project stage: Request 3F1197-54, Forwards Copy of Proposed Rev 5 to EOP-8, LOCA Cooldown, as Committed in1997-11-21021 November 1997 Forwards Copy of Proposed Rev 5 to EOP-8, LOCA Cooldown, as Committed in Project stage: Other 3F1197-45, Submits Rev 1 to TS Change Request Notice 210,which Proposes Amends to OL DPR-72.Rev Addresses Changes Resulting from NRC Review of TS Change Request Notice 210.Rev Involves Additional Restrictions,Editorial Clarifications & Typos1997-11-21021 November 1997 Submits Rev 1 to TS Change Request Notice 210,which Proposes Amends to OL DPR-72.Rev Addresses Changes Resulting from NRC Review of TS Change Request Notice 210.Rev Involves Additional Restrictions,Editorial Clarifications & Typos Project stage: Other ML20202E5671997-11-26026 November 1997 Forwards Request for Addl Info Re Amend Submittal ,supplemented by Submitting Approach for Addressing Certain SBLOCA Scenarios Project stage: RAI ML20202D4161997-11-26026 November 1997 Mod Outage Integrated Verification Team Rept Project stage: Request 05000302/LER-1997-039, Corrected Page 1 to LER 97-039-00,adding Rept Date in Block 7.On 971108,unqualified Matl Discovered Left in Reactor Bldg During Const.Caused by Personnel Error.Polystyrene Permanently Installed1997-12-0303 December 1997 Corrected Page 1 to LER 97-039-00,adding Rept Date in Block 7.On 971108,unqualified Matl Discovered Left in Reactor Bldg During Const.Caused by Personnel Error.Polystyrene Permanently Installed Project stage: Request 3F1297-27, Forwards Response to 971126 RAI Re TS Change Request 210, Which Addresses Design & Licensing Basis Changes Primarily Involving Plant Systems Used to Mitigate Consequences of Certain Small Break LOCA1997-12-0303 December 1997 Forwards Response to 971126 RAI Re TS Change Request 210, Which Addresses Design & Licensing Basis Changes Primarily Involving Plant Systems Used to Mitigate Consequences of Certain Small Break LOCA Project stage: Other ML20203C3901997-12-0505 December 1997 Requests Addl Info Re 970614 License Amend,Suplemented on 970925,1119,1121 & 1203,re FPC Approach for Addressing Certain SBLOCA Scenarios Project stage: Other 3F1297-32, Provides NRC Requested Clarification Re Use of HPI Flow Throttling TS Change Request Notice 210.No New Commitments Made in Submittal1997-12-0505 December 1997 Provides NRC Requested Clarification Re Use of HPI Flow Throttling TS Change Request Notice 210.No New Commitments Made in Submittal Project stage: Other 3F1297-38, Forwards Addl Info on Validations of Proposed Emergency Operating Procedures Containing Operator Actions Related to TS Change Request 210,per 971203 Telcon1997-12-11011 December 1997 Forwards Addl Info on Validations of Proposed Emergency Operating Procedures Containing Operator Actions Related to TS Change Request 210,per 971203 Telcon Project stage: Other 3F1297-47, Forwards Response to 971219 RAI Re TS Change Request Notice 210,addressing Design & Licensing Basis Changes Involving Plant Systems Used to Mitigate Consequences of Certain Sbloca.Commitments Made by Util Also Encl1997-12-24024 December 1997 Forwards Response to 971219 RAI Re TS Change Request Notice 210,addressing Design & Licensing Basis Changes Involving Plant Systems Used to Mitigate Consequences of Certain Sbloca.Commitments Made by Util Also Encl Project stage: Other 3F0198-29, Informs That Util in Conjunction W/Framatome Technologies Inc,Completed Confirmation Which Includes Consideration of SG Tube Plugging Levels Specific for CR-3.Util Verified That LOCA Analyses of Record Does Not Require Manual Actuation1998-01-15015 January 1998 Informs That Util in Conjunction W/Framatome Technologies Inc,Completed Confirmation Which Includes Consideration of SG Tube Plugging Levels Specific for CR-3.Util Verified That LOCA Analyses of Record Does Not Require Manual Actuation Project stage: Other 3F0198-35, Forwards Complete Updated TS & Bases Pages to TS Change Request Notice 210 Submitted on 970614.Updated Pages Reflect Changes Identified in Licensee ,Correction of Typo & Addition of Footnotes1998-01-22022 January 1998 Forwards Complete Updated TS & Bases Pages to TS Change Request Notice 210 Submitted on 970614.Updated Pages Reflect Changes Identified in Licensee ,Correction of Typo & Addition of Footnotes Project stage: Other 3F0298-02, Forwards Status of Requirements Stated in SE Submitted W/ License Amend 163.Status of SE Requirements Do Not Invalidate or Alter Any Conclusions,Or Basis of Any Conclusion,Supporting TS Issued in License Amend 1631998-02-20020 February 1998 Forwards Status of Requirements Stated in SE Submitted W/ License Amend 163.Status of SE Requirements Do Not Invalidate or Alter Any Conclusions,Or Basis of Any Conclusion,Supporting TS Issued in License Amend 163 Project stage: Other 1997-12-24
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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:OUTGOING CORRESPONDENCE
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 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) 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 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 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 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 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 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 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 ML20210G8551999-07-27027 July 1999 Forwards Insp Rept 50-302/99-04 on 990523-0703.One Violation Identified & Being Treated as Noncited Violation 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 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 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) ML20207G3081999-06-0808 June 1999 Discusses Providing NRC Biological Assessment of Impact to Sea Turtles at Plant.Forwards Comments on Draft Biological Opinion Re Impact to Sea Turtles at Plant ML20195F3071999-06-0404 June 1999 Forwards Insp Rept 50-302/99-02 on 990411-0522.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206N5511999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Sr Peterson Will Be Section Chief for Crystal River Npp.Organization Chart Encl ML20206P5411999-05-0606 May 1999 Forwards Insp Rept 50-302/99-02 on 990228-0410.No Violations Noted.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20206G1971999-05-0404 May 1999 Forwards Summary of 990412 & 14 Telcon with FPC Representatives Re NRC Questions Concerning Util 980729 & 1120 Ltrs Requesting Approval to Adopt NEI 97-03 Draft Final Rev 3, Methodology for Development of Eal ML20206K4461999-04-27027 April 1999 Forwards Notice of Withdrawal in Response to Util 990412 Request for Withdrawal of Application & Suppl by for Amend Re Normal Standby Position of Dh Removal Sys Valves DHV-34 & DHV-35 ML20206B9141999-04-20020 April 1999 Refers to Open Mgt Meeting Conducted at Licensee Request in Atlanta,Ga on 990414 Re Recent Crystal River 3 Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20205S4741999-04-20020 April 1999 Informs That NRC Determined FTI Topical Rept BAW-2342P,Rev 0,entitled OTSG Repair Roll Qualification Rept,Addendum a, Marked as Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) ML20205T3241999-04-0909 April 1999 Informs That on 990402,K Mccall & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Plant for Y2K Initial Exam Dates Are Wks of 000828 & 0911 for Approx Nine Candidates ML20205K6001999-04-0808 April 1999 Forwards Draft Biological Opinion from National Marine Fisheries Service Re Impact on Endangered Sea Turtles of Operation of Crystal River Energy Complex for Review & Comment ML20205K6111999-04-0202 April 1999 Forwards Request for Addl Info Re Util 980416 & Revised 981130 Submittals of Third 10-year Inservice Insp Program for Crystal River Unit 3 ML20205Q4871999-03-29029 March 1999 Forwards Insp Rept 50-302/99-01 on 990117-0227.No Violations Noted ML20205D5101999-03-26026 March 1999 Discusses FPC 961008 & 970228 Responses to NRC RAI Re Postulated Failure of RCP Seal Area Heat Exchanger Which Could Cause Overpressurization of Nuclear Svcs Closed Cycle Cooling Sys.Determined That in-depth Study Not Needed ML20205D3391999-03-22022 March 1999 Advises of NRC Planned Insp Effort Resulting from Plant PPR Completed on 990203,to Develop Integrated Understanding of Safety Performance.Historical Listing of Plant Issues & Details of Insp Plan for Next Eight Months Encl ML20204J5601999-03-22022 March 1999 Confirms 990309 Telcon Between R Mclaughlin of Licensee Staff & Ninh of NRC Re Mgt Meeting to Be Held at Licensee Request & Scheduled for 990313 in Atlanta,Ga to Discuss Recent Crystal River 3 Performance ML20207L3501999-03-0404 March 1999 Forwards Request for Addl Info Re 980730 License Amend Request 222 on Control Room Emergency Ventilation Sys IR 05000302/19982011999-02-16016 February 1999 Forwards Operational Safeguards Insp Rept 50-302/98-201 on 980504-06.No Violations Noted.Briefings,Observations,Drills & Exercises Indicated That Modified Protection Strategy Generally Sound.Without Encl ML20203G4891999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20203A4301999-02-0303 February 1999 Forwards SE Re 3 EAL Changes.Nrc Has Concluded That Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 & Therefore Acceptable ML20206S4191999-01-26026 January 1999 Forwards FEMA Final Exercise Rept for 981014,emergency Response Exercise.No Deficiencies or Areas Requiring Corrective Action Were Identified During Exercise ML20199J8701999-01-14014 January 1999 Informs That on 990117,Region II Will Implement Staff Reorganization as Part of agency-wide Streamlining Effort. Copy of Organization Charts Encl for Info ML20199F4971999-01-11011 January 1999 Confirms FPC Informing That Request for USNRC Review of Topical Rept Boron Dilution by RCS Hot Leg Injection Submitted on 970227 Was Being Withdrawn.Informs That All Remaining Review Effort for Request,Canceled ML20199E3441999-01-11011 January 1999 Confirms Licensee Informing NRC That Request for Exemption from Requirements of 10CFR70.24(a) for Crystal River Unit 3,submitted by Util by Ltr Being Withdrawn ML20199D6071999-01-0404 January 1999 Forwards Insp Rept 50-302/98-10 on 981025-1205 & Notice of Violation.Nrc Concluded That Info Re Reason for Violation, C/A Taken & Plan to Correct Violation & Prevent Recurrence Already Adequately Addressed ML20199E3991998-12-23023 December 1998 Discusses Training Managers Conference Conducted at RB Russell Bldg on 981105.Agenda Used for Conference,List of Attendees,Slide Presentation & Preliminary Schedule for FY99 & FY00 Encl ML20198N9051998-12-16016 December 1998 Forwards Insp Rept 50-302/98-13 on 981116-20.No Violations Noted.Insp Consisted of Selective Exams of Procedures & Representative Records,Interviews with Personnel & Observations of Activities in Progress ML20196H2511998-12-0101 December 1998 Forwards Insp Rept 50-302/98-12 on 981013-16.No Violations Noted.Insp Team Observed Selected Portions of Emergency Organizations Response in Key Facilities During EP Plume Exposure Exercise ML20196C2931998-11-24024 November 1998 Forwards Notice of Withdrawal of 971031 Application for Amend to License ML20196A5321998-11-23023 November 1998 Ack Receipt of That Informed of Clarifications Needed Re Time Necessary to Start Control Complex Chillers at Plant,After Loss of Offsite Power.Changes to Start Times Do Not Alter Conclusion in SE Supporting Amend 163 to TSs ML20196C6291998-11-20020 November 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting Held on 981102.Insp Plan for Next 4 Months & Historical Listing of Plant Issues,Called Plant Issues Matrix, Encl ML20195G4461998-11-17017 November 1998 Discusses FPC 980518 Submittal of Operational Assessment of Once Through SG Tube Degradation at CR-3 in Accordance with License Commitment Submitted on 971207 1999-09-03
[Table view] |
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.- . . . - . - - - .- - - - -
I September 10, 1997 e Mr. Roy A.= Anderson Senior Vice President. Nuclear Operations-Florida Power Corporation <
-ATTN Manager.-Nuclear Licensing Crystal River Energy Complex (SA2A) 15760 W Power Line Street Crystal River. Florida 34428 6708
SUBJECT:
- CRYSTAL RIVER UNIT 3 - RE0 VEST FOR ADDITIONAL INFORMATION RELATED TO EMERGENCY OPERATING PROCEDURES TECHNICAL SPECIFICATIONS CHANGE RE0lJEST NUMBER 210 (TAC N0. M98991)
Dear Mr. Anderson:
By-letter dated August 4. 1997. you submitted emergency operating procedures (EOPs) with proposed changes to reflect your technical specifications change request number 210 relating to mitigation of small break loss of coolant accidents and associated design basis changes. The purpose of this letter is to request additional information (RAI) relating to the proposed E0Ps.
Enclosed are the details of the RAI.
-We discussed the technical details in a telephone conversation with your staff on September 9, 1997. At your staff's request, we have tentatively scheduled a meeting with your staff at the Nuclear Regulatory Commission headquarters
. offices on Septcmber 18, 1997, to further discuss these issues. We will confirm the meeting date and agerida by a separate meeting notice. We request you to provide a written response.to our RAI before the meeting date.
If you have any questions, please write or call me at (301) 415-1471.
Sincerely.
Original signed by L. Raghavan Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-302 cc: See next page DistribJt'on e Docket Ei g '
'J.Zwolinski PUBLIC-OGC CR-3 r/f ACRS B. Boger J. Lyons IQ.[) / - j J. Bongarra Cecil Thomas J. Jaudon. Region II DOCUMENT-NAME: G:\ CRYSTAL \u m.a.u . .
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.* k UNITED STATES e- 'O NUCLEAR REGULATORY COMMISSION -
o WASHINGTON, D.C. 30006-4001
%, September 10, 1997 Mr. Roy A. Anderson Senior Vice President. Nuclear Operations Florida Power Corporation ATTN: Manager. Nuclear Licensing CrgstalRiverEnergyComplex(SA2A) 15,60 W Power Line Street Crystal R M r. F1orida 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 - RE0 VEST FOR ADDITIONAL INFORMATION RELATED TO EMERGENCY OPERATING PROCEDURES - TECHNICAL SPECIFICATIONS CHANGE RE0 VEST NUMBER 210 (TAC N0. M98991)
Dear Mr. Anderson:
By letter dated August 4, 1997. you submitted emergency operating procedures (E0Ps) with proposed changes to reflect your technical specifications change request number 210 relating to mitigatica of small break loss of coolant accidents and associated design basis changes. The purpose of this letter is to request additional informatioq (RAI) relating to the proposed E0Ps.
Enclosed are the details of the RAI.
We discussed the technical details in a telephone conversation with your staff on September 9. 1997. At your staff's request, we have tentatively scheduled a meeting with your staff at the Nuclear Regulatory Commission headquarters offices on September 18, 1997, to further discuss these issues. We will confirm the meeting date and agenda by a separate meeting notice. We request you to provide a written response to our RAI before the meeting date.
If you have any questions, please write or call me at (301) 415-1471.
Sincerely, a f -
L. Raghavan Project Manager Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50 302 cc: See next page
\
Mr. Roy A. Anderson Florida Power Corporaticc, CR(STAL RIVER UNIT N0. 3 Cc:
Mr. R. Alexander Glenn Corporate Counsel Senior Resident Inspector Florida Power Corporation Crystal River Unit 3 MAC-ASA U.S. Nuclear Regulatory Commission P.O. Box 14042- 6745 N. Tallahassee Road St. Petersburg, Florida 33733-4042 Crystal River, Florida 34428 Mr. Bruce J. Hickle, Director Mr. John P. Cowan Nuclear Plant Operations (NA20) Vice President, Nuclear Production Florida Power Corporation (NA2E)
Crystal River Energy Complex Florida Power Corporation 15760 W. Power Line Street Crystal River Energy Complex Crystal River, Florida 34428-6708 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Pobert B. Borsum B&W Uuclear Technologies Mr. James S. Baumstark
'1700 Rockville Pike, Suite 525 Director, Quality Programs (SA20)
Rockville, Maryland 20852 Florida Power Corporation Crystal River Energy Complex Mr. Bill Passetti 15760 W. Power Line Street Office of Radiation Control Crystal River, Florida 34428-6708 Department of Health and Rehabilitative Services Regional Administrator, Region 11 1317 Winewood Blvd. U.S. Nuclear Regulatory Commission Tallahassee, Florida 32399-0700 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303-3415 Attorney General Department of Legal Affairs Mr. Kerry Landis The Capitol U.S. Nuclear Regulatory Commission Tallahassee, Florida 32304 61 Forsyth Street, SW., Suite 23T85 Atlar.ta, GA 30303-3415 Mr. Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32309-2100 Chairman Board of County Commissioners Citrus County 110 North Apopka Avenue Iverness, Florida 34450-4245 Mr.- Robert E. Grazio, Director Nuclear Regulatory Affairs (SA2A)
Florida Power Corporation Crystal River Energy Complex 15760 W. Power Line Street Crystal River, Florida 34428-6708
\
O REQUEST FOR ADDIT ONAL INFORMATION -
EM!RGENCY OPERA"ING PROC EDURES
- 1. Attachment F- Supporting Information, Crystal River 3 Safety Assessment.
Revision 2, 6/14/97 Please match the operator actions listed in Tables 3A and 3B with the corresponding steps that appear in Crystal River's emergency operating procedures (E0Ps)
- 2. How much total time (from initiation of each of the three small break-loss-of coolant accident (SBLOCA) events (i.e., loss of battery A (LOBA): loss of battery "B" (LOBB) and the emergency feedwater pump) is available to allow the operator, and the equipment, to complete actions needed before any design basis requirement / limit is exceeded? How were the total times determined (i.e., what were the criteria used to establish the times available to the operator to take the necessary steps)?
- 3. TSCRN 210. Table 3A Operator Actions Less Than 20 Minutes.
Operator Action 1 - Reference indicates that operator action to trip reactor coolant minutes of what? pumps (RCPs) is accident?
taken "withinInitiation 2 minutes":
within 2 Initiation of the of an alarm?
Please clarify.
- 4. E0P-3, Inadequate Subcooling Margin (ISM),
a, Entry Conditions How does an operator know that an ISM condition exists i.e., what is meant by "subcooling margin' monitor? What type of instrument is it (analog display, CRT screen, etc.)? Is an ISM easily read or is interpolation needed by the operator? How is the instrumentation qualified (i.e. , per RG 1.97)?
- b. Imediate Actions Step 2.1--- How does the operator know whether 2 minutes have elapsed since losing SCM (knowledge of s3ecific time elapsed seems necessary to determine whether to trip all RC)s or have one RCP running in each loop)?
[ Rule 1. Loss of SCM]--- What does this refer to? If this information is important to understanding what the operator does in completing E0P steps, please provide a copy of the rule (as well as copies of all other
" rules' cited in the associated E0Ps).
Enclosure
,i
. 5. During the LOBA condition, how does the operator manually load the "B" Control Complex Chiller on EDG-1B, i.e., is the action carried out from the control room or is it done locally? In either case, what ste)s does the operator takrto accomplish this task and how long does it tate?
The operator has I hour to complete this task, How was this time determined? ' Will the performance of this step be verified / validated as part of the verification / validation (V/V) effort?
6, Under the LOBB condition, please describe the validation that was/will be done to demonstrate that the EFW can be cross-connected before an operational limit is reached.
- 7. TSCRN 210 Attachment 8, Page 8 14 Describe the process used to conduct the table-top evaluation and simulator V/V. Has the V/V been completed? Have all the crews been trained and tested (i.e., evaluation of the success / failure of the crews
- performance) on the use of the new procedures? What were the results (i.e., successes vs. failures) of the V/V7 Were the operator acticns required performed with minimum shift staffing as well as normal crew staffing level? If there are any local manual actions required, how were they simulated / considered in the V/V process?
- 8. In general, when evaluating temporary or permanent changes to a facility that credit operator actions for system or component actuations that were previously automated, the staff has relied on guidance in Generic letter 91-18 and ANSI /ANS 58.8, " Time Response Criteria for Safety-Related Operator Actions." While ANSI-58.8 supplies guidance for determining minimum response times for operator actions, the standard does allow licensees to use time intervals derived from independent sources, provided that they are based on task arialyses to include, among other things, (a) specific operator actions required (b) potentially harsh or inhospitable environmental conditions ex)ected. (c) a general discussion of the ingress / egress paths taken by t1e operators to accomplish functions, (d) procedural guidance for the required actions.
(e) specific operator training necessary to carry out actions including any special qualifications required to perform the actions (f) description of information required by the control room staff to determine such operator actions are required, including uaiified instrumentation used to diagnose the situation and verif that the required action has been successfully taken, and (g) abi ity to recover from credible errors in performance of manual actions and the expected time required to make such a recovery.
Characterization of these items, through detailed analysis including the use of the )lant-specific simulator, 3rovides a means for the licensee to assess tie likelihood of accomplis 11ng the required actions and the consequences of delayed or missed opportunities to complete such actions.
Please discuss your application of the ANSI 58.8 standard for establishing or verifying operator action times. Also, please identify and reference applicable. procedures, and confirm your plan for completing operator training prior to implementing the E0P changes.