Letter Sequence Draft Other |
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MONTHYEARML20205K6001999-04-0808 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
Project stage: Draft Other
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
Project stage: Draft Other
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
Project stage: Draft Other
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
Project stage: Other
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
Project stage: Other
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
Project stage: Draft Other
3F1099-01, LAR 253,rev 0 to License DPR-72,incorprating Requirements from Biological Opinion Issued by Natl Marine Fisheries Svc1999-10-12012 October 1999
LAR 253,rev 0 to License DPR-72,incorprating Requirements from Biological Opinion Issued by Natl Marine Fisheries Svc
Project stage: Other
1999-06-08
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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] |
Text
'~
Mr. John Paul Cowan
~ Vice President, Nuclear Operations N'T 4> 1999 Florido Power Corporation ATTN: Manager, Nuclear Licensing (NA2C)
Crystal River Energy Complex 15760 WiPower Line Street
. Crystal River, Florida 34428 6708
SUBJECT:
SUMMARY
OF CONFERENCE CALL CONCERNING ADOPTION OF NEW EMERGENCY ACTION LEVEL METHODOLOGY (TAC NO. MA1706)
Dear Mr. Cowan:
By letter dated July 29,1998, and revised by letter dated November 20,1998, Florida Power Corporation (FPC) requested approval to adopt Nuclear Energy Institute 97-03 Draft Final Revision 3, " Methodology for Development of Emergency Action Levels," for Crystal River Unit
- 3. On April 12 and 14,1999, representativss of the U.S. Nuclear Regulatory Commission (NRC) staff held a teleconference with FPC representatives to discuss NRC staff questions concoming this request. The enclosure summarizes and documents this teleconference, including our understanding of actions FPC will take to resolve NRC concems. If the understanding of your staff concoming the agreed-to actions differ from ours, please have your staff contact me as soon as possible. The schedule for respond!ng to the action items included in this summary were discussed with John Stephenson of your staff, and it was agreed that a response would be provided within 60 days of receipt of this letter.
Please contact me at (301) 415-1495 if you have any questions regarding this matter.
Sincerely, . ;
~
Original signed by:
Leonard A. Wiens, Senior Project Manager, Section 2 Project Directorate il LDivision of Licensing Project Management Office of Nuclear Reactor Regulation
~
Docket No. 50-302
Enclosure:
As stated cc w/ encl: See next page bW DISTRIBUTION:
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UNITED STATES NUCLEAR REGULATORY COMMISSION g g2 WASHINGTON, D. C. 20555 May 4, 1999 k.....
Mr. John Paul Cowan Vice President, Nuclear Operations Florida Power Corporation ATTN: Manager, Nuclear Ucensing (NA2C)
Crystal River Energy Complex 15760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
SUMMARY
OF CONFERENCE CALL CONCERNING ADOPTION OF NEW EMERGENCY ACTION LEVEL METHODOLOGY (TAC NO. MA1706
Dear Mr. Cowan:
By letter dated July 29,1998, and revised by letter dated November 20,1998, Florida Power Corporation (FPC) requested approval to adopt Nuclear Energy Institute 97-03 Draft Final Revision 3," Methodology for Development of Emergency Action Levels," for Crystal River Unit 3. On April 12 and 14,1999, representatives of the U.S. Nuclear Regulatory Commiss (NRC) staff neld a teleconference with FFC representatives to discuss NRC staff questions concerning this request. The enclosure summarizes and documents this teleconference, including our understanding of actions FPC will take to resolve NRC concerns. If the understanding of your staff conceming the agreed-to actions differ from ours, please have your staff contact me as soon as possible. The schedule for responding to the action items included in this summary were discussed with John Stephenson of your staff, and it was agreed that a response would be provided within 60 days of receipt of this letter.
Please contact me at (301) 415-1495 if you have any questions regardir,g this matter.
Sincerely, Leonard A. Wiens, Senior Project Manager, Section 2 Project Directorate il Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
As stated cc w/enci: See next page
r ISSUES ON CRYSTAL RIVER ENERGY ACTION LEVEL SUBMITTAL DISCUSSED DURING TELECONFERENCES HELD APRIL 12 AND 14,1999 The following issues were discussed during teleconferences held April 12 and 14,1999. The ,
licensee's emergency action level (EAL) is identified in bold typeface followed by a brief summary of the U. S. Nuclear Regulatory Commission's (NRC's) question or concern. The licensee's response is in italic typeface.
EAL 1.1-1 (NUMARC/NESP-007 AU1)
Please verify that all postulated gaseous releases will be monitored by RM-A1 and RWA 2.
Licensee verified that all anticipated gaseous releases will be monitored by RM-A 1 and RM-A2. If a steam generator tube rupture (SGTR) occurs and a secondary safety lifts however, there is no monitor for this type of release.
Please discuss how the thresholds for radioactive releases are set on the radioactive release permit. An example of a radioactive release permit will facilitate discussions.
The licensee stated that a new procedure will be developed to identify the Unusual Event (UE) and Alert thresholds on the radioactive release permits.
EAL 1.1-2 (NUMARC/NESP-007 AU1)
Please discuss why this EAL refers only to the noble gas instantaneous release limit.
The licensee stated that this is the only species which is monitored real-time. lodines and particulates are not monitored as a ;elease rate but rather are collected on a filter and evaluated in terms of the cumulative release.
EAL 1.3-1 (NUMARCINESP-007 AS1-1)
Please discuss the following issues:
Justification for deviation from NUMARC/NESP-007 guidance (i.e., accuracy, timeliness).
+
potential numbering error in basis.
Does a shift dose assessment capability exist and if it does, why does the emergency response team need to provide input.
Why a note which provides for classifying on real time dose assessment (when available)instead of radiation monitor setpoints was not included.
What was the source term which was used in establishing the radiation monitor setpoints.
The licensee discussed these issues and will submit the requested justificationhnformation.
Enclosure
O
.c 2-EAL 1.4-2 (NUMARC/NESP-007 AG1)
Please discuss why indication of core damage is necessary to classify this event.
The licensee discussed these issues and will submit the requested justification /infonnation.
EAL 1.7-1,1.8-2 (NUMARC/NESP-007 AU2 3,AA3 2) l Please discuss why this EAL does not include all area radiation monitors. In particular, the !
staff would like to discuss whether local radiation levels could limit access to safety equipment without causing the listed radiation monitors to exceed the specified setpoints.
The licensee discussed these issues and will consider modifying the EAL to add o- additional monitors to address the NRC concem. The licensee will submit the modified EAL and/orjustification formaintaining cunent EAL.
EAL 1.9 (also EAL 1.10.2)(NUMARC/NESP 007 AU2-1, AA2 2)
Please discuss why this EAL does not specify a water levelin the refueling cavity. l The licensee discussed these issues and will submit the requested justification /information EAL 1.101b (NUMARC/NESP-007 AA2-1)
Please discuss why this EAL refers to increasing trend instead of providing a setpoint. Further,
- the staff would like to discuss how this event would be classified if the increasing trend stabilized.
The licensee discussed theso issues and will consider modiff ing the EAL to address
~ the NRC concem. The liccusee willsubmit the modified EAL and/orjustification for maintaining cunent EAL.
EAL 2.1 (NUMARCINESP-007 HU1-1)
Please discuss why this EAL did not specify Ground motion sensed as a stand-alone condition.
In addition, please discuss the setpoint used (Revision 18 had the annunciated earthquake at the Alert level).
The licensee stated that sensing ground motion may not be a result of an earthquake but may be due to othercauses such as turbine vibration. Furthermore, the licensee stated that the seismic alarm is set et .01g which is below the operating basis !
earthquake level and is consistent with the NUMARC/NESP-007 guidance. l EAL 2.6 (NUMARCINESP-007 HU1-2) l Please discuss why high winds were not included in this EAL. l The licensee stated that, as described in its deviation document, the primary sources of high winds are hum' canes or tomados. The NRC stated that it needs to further consider whether this deviation is appropriate.
I
n.
EAL 2.7 (NUMARC/NESP-007 HA1-2)
. Please discuss an apparent editorial mistake in this EAL.
The licensee stated that it will Rx the editorial mistake and resubmit the corrected EAL.
1 EAL 2.10 (NUMARCINESP-007 HU3-2) l Please discuss why " sheltering" was not included in this EAL.
The licensee stated that it will add sheltering to the EAL and resubmit it to the NRC. \
EAL 2.11 (NUMARC/NESP-007 AU1)
Please discuss why this EAL would not be applicable if personnel protective equipment was used. (The staff would like to discuss whether there are other EALs which include statements in its basis which limit their applicability.) !
The licensee stated that it can saI61y operate equipment while using protective equipment and that this EAL is similar to one approved for Watts Bar. The NRC stated that there may be situations where operation of equipment needed for safe plant i operation with protective equipment (due to the presence of toxic gases) might represent a potential degradation in the level of safety of the plant warranting a UE
[ unusual event] classiRcation. The NRC stated that it needs to further consicer whether this deviation is appropriate.
EAL 2.15 (NUMARC/NESP-007 HA1-4)
Please discuss the statements limiting the applicability of this EAL contained in the basis for the EAL.
The licensee stated that it is considering ways of modifying the EAL to address the NRC's concems. A teleconference will be scheduled to discuss this issue further.
EAL 2.16 (NUMARCINESP-007 HAS-1)
Please discuss why it is not appropriate to declare this event as soon as possible.
The licensee stated that it is considering ways of modifying the basis for this EAL to address the NRC's concems. The licensee will submit the modified basis and/or Justification for maintaining cunent basis.
EAL 2.17 (NUMARC/NESP-007 HS2)
Please discuss the initiating condition for this EAL and its relationship to the NUMARCINESP-007 guidance. Please discuss the ease of classifying this event using the referenced procedure.
The licensee stated that its EAL does not deviate from the NUMARC/NESP-007 guidance. The NRC agreed. The licensee will evaluate the referenced procedure to ensure it provides sufficient guidance to support class lfying this type of event.
1 4
EAL 2.19, 20 (NUMARC/NESP-007 HA1, HS1)
Please discuss how this EAL corresponds to its NUMARC/NESP-007 counterpart and whether there are any other safeguards events which should be included.
The staff would like to discuss deviations from NUMARC/NESP-007 in the initiating conditions
- specified for the security event EALs. 1 The licensee stated that it would modify its EAL to meet the NUMARC/NESP-007 criteria as appropnate and willhave secunty representatives review the EAL to ensure it captures all safeguard ennis of concem.
EAL 2.21 (NUMARC/NESP-007 HG1)
Ple'ase discuss the justification for this deviation from the NUMARC/NESP-007 guidance.
The licensee stated that it will review the EAL and modify it to meet the NUMARC/NESP-007 guidance orjustify deviations as appropriate.
EAL 2.23 (no corresponding NUMARC/NESP-007 EAL)
Please discuss the statement in the basis regarding the applicability of the EAL.
The licensee stated thatitis considenng ways of modifying the EAL to address the ;
NRC's concems. A teleconference willbe scheduled to discuss this issue further. l l
EAL 3.2 (NUMARC/NESP-007 SA4-1) i Please discuss why including the condition " reactor power 5% and decreasing" is not a I deviation from the NUMARC/NESP-007 guidance.
The licensee stated that it would modifyits EAL to utilize its EOP [ Emergency Operating Procedure] terminology for the failure to trip the reactor.
EAL 3.3 (NUMARC/NESP-007 SS2-1)
Please discuss whether reactor power less than 5% power corresponds to the power level for which the safety systems are designed.
I The licensee stated that it would modify its EAL to utilize its EOP terminology for the l failure to trip the reactor.
EAL 3.4 (NUMARC/NESP-007 SG2-1)
Please discuss how this EAL relates to the NUMARC/NESP-007 guidance for including indications that heat removalis extremely challenged.
The licensee stated that it was considenng modifying its EAL to include the ,
NUMARC/NESP-007 condition. The licensee stated it would modify the EAL or submit justification for the deviation. j EAL 3.6 (NUMARC/NESP-007 SU31) )
Please discuss the purpose of the annunciator printer. j I
i l
l l
I
e The licensee described the annunciatorprinter function and will provide further information to the NRC on its use. '
EAL 3.15 (NUMARC/NESP-007 SA3-1)
Please discuss how this EAL relates to the guidance provided in NUMARC/NESP-007.
)
The licensee stated that it would modifyits EAL to meet the NUMARC/NESP-007
\
guidance. '
EAL 3.16 (NUMARC/NESP-007 SSS-1)
Please discuss how this EAL relates to the guidance provided in NUMARC/NESP-007.
l The licensee explained its use of site-specific indications in the EAL and will submit this !
justification to the NRC. The licensee stated that it would modify those parts ofits EAL b which deviated from the NUMARC/NESP-007 guidance. ,
EAL 4.4 (NUMARC/NESP-007 SG1-1) j Please discuss an apparent editorial error in this EAL.
{
The licensee stated that it would correct the editorial error.
i EAL Fission Product Barrier (FPB)- Loss of Fuel Clad based on Radiation Monitor Reading ;
Please discuss the basis for the setpoint used (e.g. RM-G29 > 100 R/hr).
l The licensee stated that it would re-evaluate the setpoint and submitjustification for the setpoint used.
EAL Fission Product Barrier (FPB)- Potential Loss of Fuel Clad based on CSFS Core l Cooling-Orange OR Heat Sink Red I 1
Please discuss whether there is any equivalent site-specific conditions which can be used to j develop an EAL which corresponds to this NUMARC/NESP-007 EAL.
The licensee stated that it would consider whether other conditions should be included in this EAL and will modify the EAL or submitjustification for this deviation.
EAL Fission Product Barrier (FPB)- Loss of Reactor Coolant System based on Steam l Generator Leak Please discuss:
-. How the loss of adequate subcooling margin is determined and how this setpoint relates to the NUMARC/NESP-007 and NEl EAL guidance.
+
How the use of the setpoint "one or more injection valves" relates to the NUMARC/NESP 007 and NEl EAL guidance.
O The licensee described how its site speci6c indications meet the intent of the NUMARC/NESP-007 guidance and will submit thisjustification to the NRC.
4 EAL Fission Product Barrier (FPB)- Potential Loss of Reactor Coolant System based on CSFS RCS Integrity - Red OR Heat Sink-Red Please discuss whether there are any equivalent site-specific conditions which can be used to develop an EAL which corresponds to this NUMARC/NESP-007 EAL.
The licensee stated that it would consider whether other conditions should be included in this EAL and will modify the EAL or submitjustiMcation for this deviation.
EAL- Fission Product Barrier (FPB)- Loss of Containment based on Steam Generator Leak Please discuss how the CR EAL relates to the NUMARC/NESP-007 and NEl EAL guidance.
The licensee described how its site-specific indications meet the intent of the NUMARC/NESP-007 guidance and will submit thisjustification to the NRC.
EAL- Fission Product Barrier (FPB)- Loss of Containment based upon ICC curves Please discuss why the CR EAL did not include the 15-minute criteria provided in the NUMARC/NESP 007 and NEl EAL guidance. In addition the staff would like to discuss why a setpoint based upon reactor vessel level was not included.
The licensee described how its site-specific indications meet the intent of the NUMARC/NESP-007 guidance and wi!I submit this justification to the NRC.
EAL Fission Product Barrier (FPB)- Loss of Containment based upon area Radiation Levels Please discuss whether this EAL might misclassify an event due to shine from the containment in the event of a severe accident.
The licensee determined that misclassification may occur due to shine and decided to delete this EAL.
EAL Fission Product Barrier (FPB)-- Loss of Containment based upon Sump indications Please discuss why CR did not include an EAL equivalent to the NUMARC/NESP-007 EAL ,
" Containment pressure or sump level response not consistent with LOCA conditions."
The licensee stated that it was modifying its EAL scheme to include this EAL.
e NUMARC/NESP-007 EAL SU4 Please discuss whether there are any monitors which may be used in this EAL.
The licensee stated that there were no monitors which could be used. However, monitors in the letdown lines isolate letdown and prompt sample analysis can be used to classify the event.
NUMARC/NESP-007 EAL HUS Please discuss whether rapid depressurization of the secondary side should be included as an EAL. Revision 18 included this condition as an EAL, classified at the Unusual Event level.
The licensee stated that this type of event would be classified as an Unusual Event under EAL 2.12 for catastrophic failure ofpressurized equipment or as an Alert under EAL . The NRC stated that it needed to consider this issue further.
GENERAL The NRC representative stated that, although the licensee had developed its EAL scheme using guidance provided in NEl 97-03, it was reviewing the EAL scheme against the guidance provided in NUMARC/NESP-007 because the guidance in NEl 97-03 had not been approved by the NRC. However, the NRC was considering insights provided in NEl 97-03 in its review.
e e
O Mr. John Paul Cowan CRYSTAL RIVER UNIT NO. 3 Florida Power Corporation cc:
Mr. R. Alexander Glenn Chairman I Corporate Counsel (MAC-BT15A) Board of County Commissioners Florida Power Corporation Citrus County i P.O. Box 14042 110 North Apopka Avenue l St. Petersburg, Florida 33733-4042 Inverness, Florida 34450-4245 Mr. Charles G. Pardee, Director Ms. Sherry L. Bemhoft, Director Nuclear Plant Operations (PA4A) Nuclear Regulatory Affairs (NA2H)
Florida Power Corporation Florida Power Corporation Crystal River Energy Complex Crystal River Energy Complex 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Mr. Michael A. Schoppman Senior Resident Inspector f' Framatome Technologies Inc. Crystal River Unit 3 1700 Rockville Pike, Suite 525 U.S. Nuclear Regulatory Commission Rockville, Maryland 20852 6745 N. Tallahassee Road Crystal River, Florida 34428 Mr. William A. Passetti, Chief Department of Health Mr. Gregory H. Halnon Bureau of Radiation Control Director, Quality Programs (SA2C) 2020 Capital Circle, SE, Bin #C21 Florida Power Corporation Tallahassee, Florida 32399-1741 Crystal River Energy Complex 15760 W. Power Line Street l Attorney General Crystal River, Florida 34428-6708 Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Mr. Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Ta!!ahassee, Florida 32399-2100
