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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
- -- -- .. - . _ - _. _ _ ^ ~ ~ ~ ~
( November 5, 1997
. Mr. Roy A. Anderson
,, 3 Sdnior Vice President Nuclear vperatior.s ,
Florida Power Corpora tion y ATTN: Manager, Nuclear Licensing Crystal River Energy Complex (SA2A)
+
15760 W Power Line Street
, _ Cr)stal River, Fiorida 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION -
LICENSE AMENDMENT RELATED TO TECHNICAL SPECIFICATION CHANGE REQUEST NO. 210, SMALL BREAK LOSS OF COOLANT ACCIDENT (SBLOCA)
D'JBMllTAL (TAC NO. M98991)
Dear Mr. Anderson:
The purpose i f this letter is to request ad6lonal information (RAl) relating to your license amendment submittal dated June 14,1997, as supplemented by letter dated September 25, 1997, regarding Florida Power Corporation's (FPC's) approach for addressing certain SBLOCA scenarios. Speci0cally, the amendment requested a Technical Specification change to support operation with hardware changes involving the Emergency Feedwater System, the High Pressure injection System, and the Emergency Diesel Generators and review and approval of FPC's integrated design and operating, strategies to resolve unreviewed safety questions identified by the U.S Nuclear Regulatory Commission and FPC. The enclosure provides the details for the requested information.
We request your response as soon as possible so that we can schedule our review effort consistent with your restart plan. If you have any questions, please call me at (301) 415-1471.
Sincerely, ORIGINAL SIGNED DY:
L. Raghavan, Project Manager Project Directorate 113 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
RAI cc wisnclosure: See next page W"Q#"Q Q' '"t p UO '- ."mm 8 m '- -
Distribution Docket Filo W. Lefave PUBLIC F. Orr CR 3 r/f J. Jaudon, Region 11 C. Jackson g B. Boger J. Zwolinski J. Bongarra g; g
/CR3- OGC .
4 l DOCUMENT NAME: G:\ CRYSTAL \r298991.RAI
- Srl PREVIOUS CONCURRINCE ,
To receive a copy of ihls document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy orriet Pois 3/me / I Poll *3/PM l PDll-3/LA l PD!l-3/D
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- a. 4 UNITED STATES 3 f) NUCLEAR REGULATORY COMMISSION
"; WASHINGTON, D.C. 30666-4001
's.... Novenber 5, 1997 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 - REQUEST FOR ADDITIONAL INFORMATION -
LICENSE AMENDMENT RELATED TO TECHNICAL SPECIFICATION CHANGE REQUEST NO. 210, SMALL BREAK LOSS OF COOLANT ACCIDENT (SBLOCA)
SUBMITTAL (TAC NO. M98991)
Dear Mr. Anderson:
The purpose of this letter is to request additional information (RAl) relating to your license amendment submittal dated June 14,1997, as supplemented by letter dated September 25, 1997, regarding Florida Power Corporation's (FPC's) approach for addressing certain SBLOCA scenarios. Specifically, the amendment requested a Technical Specification change to support ,
operation with hardware changes involving the Emergency Feedwater System, the High ,
Pressu.e injection System, and the Emergency Diesel Generators and review and approval of FPC's integrated design and operating strategies to resolve unreviewed safety questions identified by the U.S Nuclear Regulatory Commission and FPC. The enclosure provides the details for the requested information.
We request your response as soon as possible so that we can schedule our review effort consistent with your restart plan. If you have any questions, please call me at (301) 415-1471.
Sincerely, 9
L. Raghavan, Project Manager s
Project Directorate ll-3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket No. 50-302 Enclosur3: RAI cc w/ enclosure: See next page 1
l
a Mr. Roy A. Anderson CRYSTAL RIVER UNIT N0. 3 Florida Power Corporation <
CC: ,
Mr. R. Alexander Glenn Corporate Counsel Mr. Robert E. Grazio, Director Florida Power Corporation Duclear Regulatory Affairs (SA2A)
MAC-ASA Florida Power Corporation P.O. Box 14042 Crystal River Energy Complex St. Petersburg, Florida 33733-4042 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Charles G. Pardee, Director Nuclear Plant Operations (NARC) Senior Resident Inspector Florida Power Corporation Crystal River Unit 3 Crystal River Energy Complex U.S. Nuclear Regulatory Commission 15760 W. Power Line Street 6745 N. Tallahassee Road Crystal River Florida 34428-6708 Crystal River, Florida 34428 Mr. Bruce J. Hickle, Director Mr. John P. Cowan Director, Restart (NA2C) 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 Rever, Florida 34428-6708 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Robert B. Borsum Framatome Technologies Inc. Mr. James S. Baumstark 1700 Rockville Pike, Suite 525 Director, Quality Programs (SA20)
Rockville, Maryland 20852 Florida Power Corporatinn 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 !!
1317 Winewood Blvd. U.S. Nuclear Regulatory Commission Tallahassee, Florida 32399-0700 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303-3415 Attorney General De,)artment of Legal Affairs Mr. Kerry Landis The Capitol U.S. Nuclear Regulatory Commission Tallahassee, Florida 32304 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303-3415 Mr. Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Chairman Board of County Commissioners Citrus County 110 North Apopka Avenue Iverness, Florida 34450-4245
O REQUEST FOR ADDITIONAL INFORMATION - LICENSE AMENDMENT RELATED TO IECHNICAL SPECIFICATION CHANGE REQUEST NO. 210,EMALL BREAK LOSS OF COOLANT ACCIDENT (SBLOCA) SUBMITTAL Control Comolex Coolina l
- 1. The proposed 30-day allowed ot ' age time (AOT) for the chillers and associated pumps appears to be unacceptable and i.1 consistent with what the Nuclear Regulatory Commission (NRC) staff has accepted in the past. The chillers and chilled water pumps serve a number of different safety-related functions in addition to cooling the control room, A 30-day AOT for the loss of single failure protection is only allowed in the Standard Technical Specifications (TS) when it only affects control room cooling Plants that have TS for safety related chilled water systems (see CEOG-STS, NUREG 1432) that cool more than the control room, the accepted AOT has been 7 days. Therefore, it appears that the risk involved with one chiller or pump inoperable dees not support a 30-day AOT. However, for the control complex heat exchanger,30 days is acceptable because the system remains protected from single active failures.
Also, for Fuel Cycle 11, while in Modes 1,2, and 3, the NRC staff believes that the required AOT is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for a Train B chiller or chilled water pump. With CHHE-1B or CHP-1B inoperable, the emergency feedwater/ emergency core cooling system (EFW/ECCS) response to certain SBLOCAs is vulnerable to certain single failures because of the load management problems associated with emergency diesel generator (EDG)-1 A while a Train B chiller or pump is inoperable. As we understand your SBLOCA scenarios, the 1-hour verification of the emergency feedwater pump (EFP)-2 (CHHE 18 or CHP-18) only assures adequate SBLOCA mitigation capability (load management / decay heat removal)if no other single failures are assumed. The generally accepted 30-day AOT for control room chillers is based on the assumption that control room cooling is the only affected function that is vulnerable to a single failure while in the 30-day limiting condition 6f coeration (LCO) (this acceptance basis is consistent with NUREG 1430 and your proposed Bases). Because of your present EDG capacity limitations, safety functions (EFW/ECCS), other than control complex cooling, are potentially affected by the inoperability of the Train B chiller or chilled water pump.
As preposed, if a SBLOCA were to occur while in LCO 3.7.18, the associated risk may be significantly greater if a Train B chiller or pur.1p is inoperable (Condition A) compared to an inoperable Train A chiller or pump (Condition B). The reasoning behind this is that while in Condition B if a SBLOCA/EFP 2 failure were to occur, load management and the control complex cooling system (CCCS) are still available. While in Condition A, if a SBLOCA/EFP-2 failure were to occur, adequate load management will not be available without purposely disabling the entire CCCS (to manage loads) function, or prematurely securing EFP 1 A to restore the CCCS function further complicating the event. Thus, there appear to be more vulnerabilities (SBLOCA/EFP 2 failure is one, there may be more) while in Condition A than while in Condition B. Therefore, for Cycle 11, the AOT for the Train B chiller and chilled water pump should be 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (while in Modes 1,2, l
2 and 3), the same as other SBLOCA mitigating equipment. Also, the AOT for the Train A chiller and pump should, as a maximum, be 7 days to minimize the risk from total loss of coc!ing that would affect a number of different safety-related arer.s in addition to control room ecoling. You should revise your proposed TS changes to address the above, or provide arktitional information and justification as to why such changes are mt necessary.
- 2. LCO 3.7.18 requires two heat exchangers for the CCCS to be Operable. The proposed Background section of the Bases states there are "two pairs of heat exchangers." It is further stated in the Background that "A single chiller and associated chilled water pump will provide the required temperature control for either heat exchanaers." The use of the singular "either" and the plural " heat exchangers" further confuses what is needed for adequate temperature control. Please provide additionalinformation and modify the proposed Bases and LCO as necessary to clarify exactly how many and which heat exchangers are necessary to maintain adequate control complex cooling and, therefore, required to be Operable. Also, for consistency and clarity LCO 3.7.18.b should specify two " Operable" heat exchangers in lieu of just two heat exchangers, the same as you have proposed in LCO 3.7.18.a for the two " Operable" chillers and associated pumps.
- 3. The proposed applicability for LCO 3.7.18 is Modes 1,2,3, and 4. To be consistent with NUREG-1430 and your corresponding TS 3.7.12 for the control room emergency ventilation system, the applicability should be expanded to include "During movement of irradiated fuel assemblies." However the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Train B AOT discussed above, would not be required during this mode (as it would not be required in Mode 4) and the AOT for this mode would be 30 days, the same as Train A components. Please make any necessary revisions to include this additional mode in your LCO or provide additional information to justify why such changes should not be required.
Hiah Pressure lniection
- 1. The submittal (pg.1) also indicates that certain aspects of the loss of EFP 2 were not analyzed. Please describe the potential for EFP-1 to be lost due to an automatic trip or as part of the load management strategy, given EFP-2 is lost.
- 2. Please verify that the isolation of the wrong high pressure injection (HPI) line, given a HPl line break, is not a more limiting single failure for your electrical system or from the standpoint of LOCA consequences. Additionally, please evaluate the HPl line isolation criteria of 50 gpm from an instrumentation standpoint and the expected flow splits in the four injection paths. With whct frequency do you expect the operators will isolate an intact injection path. What are operators instructed to do if one of the four injection line isolation valves fails to open on an engineered safeguards signal. A review of the emergency operating procedures indicate that the operators are instructed to isolate a second HPl flow path. Is this event bounded by the accident analysis?
- 3. The submittal (pg. 3) indicates that the loss-of-offsite power is assumed to occur coincident with the reactor trip. Please explain why this is assumed and discuss if it is consistent with the design basis (for LOCA and the other systems).
I
t 3-
- 4. The submittal (pg. 4) describes the methods for once through steam generator (OTSG) cooling and then desenbes " defense-in-depth" contingencies. The discussion includes the effect of depressurizing the steam generators using the turbine bypass valves or the atmospheric dump valves. Please verify that the cooling associated with the depressurization of OTSG cooling is considered a defense-in-depth mechanism rather than a being credited in the accident analysis because these are not fully qualifted components.
- 5. Please evaluate the increased risk associated with the proposed plant and procedure '
changes including the new load management strategy that is being proposed. For comparison, assume the onsite electrical, the EFW, and HPl systems and there i interconnections were adequately sized and no load management or reliance on EFW is necessary.
- 6. Please describe the current LOCA enalysis of record that was submitted in May of 1996.
Verify that the changes in the plant and procedures are correctly modeled in that analysis and that the modeling (CRAFT 2) is consistent with the code limitations and restrictions.
- 7. Pleaue clarify Action A of TS LCO 3.5.2 which requires that if one or more ECCS trains are inoperable and "at least 100% of the ECCS flow equivalent to a single operable ECCS train available." Because you run with the discharge of the HPl cross-connected and it appears that four of four injection paths are always needed. A def:nition of a
" train" of HPl would be helpful. Is a " train" one HPl pump and two, tiiree, or four injection lines or is it the equipment associated with a particular safety bus?
- 8. Is the inoperability of an injection line (i.e., an inoperable injection line isolation valve) considered the failure of one train or both trains? The TS bases (pg. B 3.5-13) state that " flow is required through a minimum of three injection legs in the event of a postulated break in the HPl injection piping." If this is the case, how is the failure of one of the injection line isolation valves bounded by accident analysis (for a HPl line break, when one of tb four injection lines is broken; are three of the remaining three required to meet the accident analysis)?
- 9. Are there any single failures that could cause two of the four injection lines (cr isolation valves) to be inoperable?
- 10. Operator Action #4 [lsolate reactor coolant pump (RCP) seal injection), in Table 3 A of Attachment D to the September 25,1997, submittal has not been approved by the NRC.
There is not sufficient information in the submittal to make a safety determination. A description of how RCP seal cooling will be maintained after injection is isolated and under what circumstances it would be lost should be provided. Additionally, the purnp vendor recommendations should also support isolation of the sealinjection and this should be described in detail.
- 11. It is not clear from reading the submittal that a post-SBLOCA situation is precluded in which the containment conditions cause an initiation of containment spray, which,
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combined with ECCS injection, could drain the borated water storage tank to the switch over point in about 45 minutes even with the loss of one diesel. With the need for chillers (at one hour?), the need for low pressure injection to provide HPl suction from the sump, the need for the motor-driven EFP (EFP-1) (for certain scenarios), and other loads (such as valve position changes), it would appear that the operating diesel could be overloaded. Please address the worst case postulated scenario in terms of tims.
dependent diescl loading, identifying which loading actions are automatic and which are operator actions. It seems that the timing may be important, reflect timing uncertainties in the assessment.
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