Letter Sequence Request |
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MONTHYEARML20039D3771981-12-30030 December 1981
Forwards Design Details of Mods Re TMI Action Plan Items II.B.3,II.F.1.1,II.F.1.2,II.F.1.4,II.F.1.5 & II.F.1.6,per NRC 801031 Ltr.Mods Meet All Technical Requirements
Project stage: Request
ML20042A5261982-03-17017 March 1982
Requests Further Extension Until 820630 to Complete Ongoing Review of Fire Protection Program Based on Justification Presented.Notification of Concurrence Requested by 820330
Project stage: Request
ML20054C2881982-04-14014 April 1982
Forwards Updated Completion Schedule,In Response to 820317 Request,For NUREG-0737 Items I.A.3.1,II.B.2,II.B.3,II.B.4, II.E.1.2,II.E.4.2,II.F.1 & II.K.2.10
Project stage: Request
ML20054G6941982-06-18018 June 1982
Informs of Delay in Completing Installation of Emergency Feedwater Initiation & Control Sys by Spring 1982.Equipment Procurement Not Proceeding at Rate to Assure Scheduled & Safe Installation
Project stage: Other
ML20027A8061982-06-30030 June 1982
Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4, Technical Evaluation Rept
Project stage: Request
ML20054L1771982-06-30030 June 1982
Provides Addl Clarification in Response to NRC Re Status of NUREG-0737,Items II.B.2,II.B.3 & II.F.1.1-6. Analysis to Support Redesign of Refuel III Scheduled for Completion by 820930
Project stage: Other
ML20065B0391982-09-0808 September 1982
Clarifies Completion Schedule & Restates Compensatory Measures for NUREG-0737,Items II.B.2,II.B.3,II.E.1.2, II.F16.1-6.Item II.E.1.2 Completed During Refuel V.Other Items Completed During Refuel IV
Project stage: Other
ML20071L9951982-09-17017 September 1982
Submits Revised Completion Schedules for NUREG-0737,Items I.C.1,II.D.1.2,II.D.1.3,II.K.3.30,II.K.3.31,III.A.1.2 & III.A.2.2
Project stage: Other
1982-06-18
[Table View] |
Forwards Design Details of Mods Re TMI Action Plan Items II.B.3,II.F.1.1,II.F.1.2,II.F.1.4,II.F.1.5 & II.F.1.6,per NRC 801031 Ltr.Mods Meet All Technical Requirements| ML20039D377 |
| Person / Time |
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| Site: |
Crystal River  |
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| Issue date: |
12/30/1981 |
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| From: |
Mardis D
FLORIDA POWER CORP. |
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| To: |
Eisenhut D
Office of Nuclear Reactor Regulation |
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| References |
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| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM 3F-1281-44, NUDOCS 8201040033 |
| Download: ML20039D377 (17) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F9941999-10-15015 October 1999
Discusses FPC 970819 Request for Temporary Relief from ASME Code Section XI Requirements to Repair ASME Class 3 Nuclear Service & Decay Heat Sea Water System Piping.Forwards SE Containing Results of Staff Review
ML20217J5171999-10-13013 October 1999
Informs That on 990930,NRC Staff Completed mid-cycle PPR of Plant,Unit 3 & Did Not Identify Any New Areas That Warranted More than Core Insp Program.Previously Planned Regional Initiative Insp of safety-related Mod Will Be Performed
3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999
Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed
3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999
Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made
ML20212L0771999-10-0404 October 1999
Forwards SER Accepting Licensee Relief Requests 98-012 Through 98-018 Involving Containment Insps at Crystal River Unit 3 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(a)(3)(ii)
ML20217D6551999-10-0101 October 1999
Requests That Natl Communication Sys Arrange for Licensee Participation in Government Emergency Telecommunications Service,Per NRC Info Notice 99-025
ML20212J8481999-10-0101 October 1999
Forwards Safety Evaluation Re Second 10 Yr Interval ISI Program Requests for Relief 98-009-II.Reliefs Granted for 98-009-II,Parts B & C & 98-010-II & 98-011-II
3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999
Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment
3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999
Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331
ML20212F7251999-09-23023 September 1999
Discusses Staff Review of Util 980330 Response,As Suppl on 990514,to GL 97-06, Degradation of SG Internals. Staff Concludes That Licensee Responses to GL Provide Reasonable Assurance That Condition of SG Internals Acceptable
ML20212F7331999-09-23023 September 1999
Discusses Util Licensing Action for GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants. NRC Ack Efforts Util Completed to Date in Preparing Crystal River,Unit 3 for Y2K Transition
3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999
Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46
ML20212E6741999-09-21021 September 1999
Forwards Safety Evaluation Accepting Proposed EAL Changes Submitted by ,As Supplemented by 981120,990713 & 0831 Ltrs,Incorporating Guidance in NUMARC/NESP-007,Rev 2, Methodology for Development of Eals
3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999
Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)
3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999
Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief
ML20212F3141999-09-13013 September 1999
Forwards Insp Rept 50-302/99-05 on 990704-0814.Violations Noted,But Being Treated as non-cited Violations
ML20211L9081999-09-0303 September 1999
Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Crystal River Unit 3
ML20211Q7581999-09-0101 September 1999
Forwards Summary of 990812-13 Training Managers Conference in Atlanta,Georgia Re Recent Changes to Operator Licensing Program.List Conference Attendees,Copy of Presentation Slides & List of Participant Questions Encl
3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999
Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals
ML20211G7111999-08-30030 August 1999
Modifies Approval of 980521 Request for Exception to 10CFR50.4(b)(6) & Grants Util Approval to Submit Copies of Future Updates to FSAR as Listed
ML20211G7031999-08-30030 August 1999
Informs of Approval of Util 980521 Request for Exception to 10CFR50.4(b)(6),allowing Util to Submit Updates to Plant Ufsar.Ltr Modifies That Approval & Grants Util Approval
3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999
Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002
ML20212C1351999-08-27027 August 1999
Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input
3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999
Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71
3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999
Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3
3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999
Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05
3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999
Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal
3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999
Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2
3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value
05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999
Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented
ML20210Q4511999-08-0505 August 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006
ML20210P0741999-08-0505 August 1999
Forwards SE Accepting Licensee 980416 & 1130 Ltrs Re Third 10-year Interval ISI Program Plan & Associated Requests for Relief for Plant,Unit 3
3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999
Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603
ML20210G8551999-07-27027 July 1999
Forwards Insp Rept 50-302/99-04 on 990523-0703.One Violation Identified & Being Treated as Noncited Violation
3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999
Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments
ML20209H5211999-07-16016 July 1999
Forwards Request for Addl Info Re Licensee Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in CR-3 once-through Steam Generators in Order to Complete Review
ML20209G3231999-07-15015 July 1999
Forwards Biological Opinion Issued by Natl Marine Fisheries (NMFS) of Dept of Commerce.Nmfs Concluded That Operation of Cw Intake Sys of Crystal River Not Likely to Jeopardize Existence of Species Listed in Biological Opinion
ML20209G3481999-07-15015 July 1999
Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon
3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999
Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl
3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999
Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl
3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999
Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl
3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999
Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730
3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999
Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held
3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21
ML20196L1261999-07-0707 July 1999
Discusses Closeout of TAC MA0538 Re License Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Unit 3
3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999
Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3
ML20196J4991999-07-0101 July 1999
Advises That Info Contained in ,Which Included TR BAW-2346P,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20209C0811999-06-25025 June 1999
Forwards Overdue Controlled Document Transmittals for Listed Documents
3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999
Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl
1999-09-03
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEAR3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999
Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed
3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999
Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made
3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999
Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment
3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999
Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331
3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999
Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46
3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999
Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)
3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999
Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief
3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999
Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals
ML20212C1351999-08-27027 August 1999
Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input
3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999
Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002
3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999
Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71
3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999
Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3
3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999
Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal
3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999
Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05
3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999
Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2
05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999
Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented
3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value
3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999
Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603
3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999
Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments
ML20209G3481999-07-15015 July 1999
Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon
3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999
Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl
3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999
Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl
3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999
Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl
3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999
Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730
3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999
Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held
3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999
Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3
ML20209C0811999-06-25025 June 1999
Forwards Overdue Controlled Document Transmittals for Listed Documents
3F0699-12, Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested1999-06-23023 June 1999
Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested
3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999
Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl
3F0699-08, Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments1999-06-21021 June 1999
Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments
3F0699-09, Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl1999-06-0404 June 1999
Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl
3F0599-21, Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads1999-05-28028 May 1999
Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads
3F0599-10, Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl1999-05-26026 May 1999
Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl
ML20207E4341999-05-25025 May 1999
Submits 30-day Written Rept on Significant PCT Changes in ECCS Analysis for ANO-1.CRAFT2 Limiting PCT for ANO-1 Was Bounded by 1859 F PCT Calculated at 2568 Mwt for Crystal River 3 Cold Leg Pump Discharge Break Size of 0.125 Ft
3F0599-22, Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs1999-05-21021 May 1999
Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs
3F0599-18, Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM1999-05-14014 May 1999
Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM
3F0599-17, Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments1999-05-14014 May 1999
Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments
3F0599-07, Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 19781999-05-14014 May 1999
Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 1978
3F0599-03, Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR1999-05-12012 May 1999
Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR
3F0599-05, Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl1999-05-12012 May 1999
Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl
3F0599-08, Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments1999-05-0303 May 1999
Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments
3F0599-09, Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 19981999-05-0101 May 1999
Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 1998
3F0499-24, Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent1999-04-30030 April 1999
Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent
3F0499-09, Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 9907301999-04-30030 April 1999
Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 990730
3F0499-23, Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements1999-04-23023 April 1999
Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements
3F0499-18, Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl1999-04-20020 April 1999
Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl
3F0499-05, Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin1999-04-16016 April 1999
Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin
3F0499-08, Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 19981999-04-16016 April 1999
Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 1998
1999-09-27
[Table view]
Category:UTILITY TO NRC
MONTHYEAR3F0990-11, Forwards Final Status Update Re Design & Operations Verification for Instrument Air Sys Per Generic Ltr 88-141990-09-20020 September 1990
Forwards Final Status Update Re Design & Operations Verification for Instrument Air Sys Per Generic Ltr 88-14
3F0990-05, Forwards 1990 Inservice Insp Summary Rept. Rept Contains Owners Data Rept,Data Summary Sections for Class 1,2 & 3 Components,Rept for Repair & Replacements & Listing of Exams1990-09-14014 September 1990
Forwards 1990 Inservice Insp Summary Rept. Rept Contains Owners Data Rept,Data Summary Sections for Class 1,2 & 3 Components,Rept for Repair & Replacements & Listing of Exams
3F0990-08, Forwards Response to Violations Noted in Insp Rept 50-302/90-23.Corrective Actions:Training Session Conducted to Stress Importance of Attachments Being Part of Work Package When Required by Procedure1990-09-13013 September 1990
Forwards Response to Violations Noted in Insp Rept 50-302/90-23.Corrective Actions:Training Session Conducted to Stress Importance of Attachments Being Part of Work Package When Required by Procedure
3F0890-23, Discusses Decommissioning Financial Assurance Rept Dtd 900726.Amount Util Collecting Exceeds Amount Necessary Based on NRC Formula & Does Not Include Estimated Cost of Removal & Disposal of Nonradioactive Structures & Matls1990-08-30030 August 1990
Discusses Decommissioning Financial Assurance Rept Dtd 900726.Amount Util Collecting Exceeds Amount Necessary Based on NRC Formula & Does Not Include Estimated Cost of Removal & Disposal of Nonradioactive Structures & Matls
ML20028G8251990-08-29029 August 1990
Advises That Supplemental Response to Insp Rept 50-302/89-18 Will Be Submitted by 901030
ML20059G1721990-08-24024 August 1990
Submits Info Re Change in Operator License Status.Re Rawls & Wa Stephenson Senior Reactor Licenses Should Be Terminated, Effective 900817 Due to Reassignment from Position Requiring Licenses
3F0890-15, Forwards Fitness for Duty Program Performance Data for Period of Jan-Jun 19901990-08-23023 August 1990
Forwards Fitness for Duty Program Performance Data for Period of Jan-Jun 1990
3F0890-21, Forwards Semiannual Radioactive Release Rept Jan-June 1990 for Crystal River Unit 3 & Rev 15 to Crystal River Unit 3 Odcm1990-08-23023 August 1990
Forwards Semiannual Radioactive Release Rept Jan-June 1990 for Crystal River Unit 3 & Rev 15 to Crystal River Unit 3 Odcm
ML20059A0031990-08-16016 August 1990
Responds to NRC 900613 Request for Addl Info Re Util 871222 Response to Violations Noted in Insp Rept 50-302/87-30
3F0890-03, Forwards Rev 11 to Inservice Insp - Pump & Valve Program, Crystal River Unit 31990-08-16016 August 1990
Forwards Rev 11 to Inservice Insp - Pump & Valve Program, Crystal River Unit 3
3F0890-10, Advises That Util Completed Mods to Comply w/10CFR50.62 Requirements Re Reduction of Risk from ATWS Events1990-08-16016 August 1990
Advises That Util Completed Mods to Comply w/10CFR50.62 Requirements Re Reduction of Risk from ATWS Events
3F0890-05, Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 1741990-08-10010 August 1990
Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 174
ML20058L2001990-08-0202 August 1990
Provides Current Status of Reg Guide 1.97 Activities. Pressurizer Heater Status & Main Steam Safety/Relief Valve Position Indications Completed
3F0790-10, Forwards Justification for Continued Operation Re Emergency Diesel Generator Block Loading Voltage Dips.Util Will Install Higher Accuracy Relays to Improve on Accuracy & Repeatability of Load Intervals1990-07-18018 July 1990
Forwards Justification for Continued Operation Re Emergency Diesel Generator Block Loading Voltage Dips.Util Will Install Higher Accuracy Relays to Improve on Accuracy & Repeatability of Load Intervals
3F0790-06, Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-81990-07-12012 July 1990
Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-8
ML20055D5561990-06-29029 June 1990
Forwards 890505 & s to Be Placed in Plant File
3F0690-15, Informs That Tech Spec Actions Identified in Util Addressed as Part of Tech Spec Improvement Program,Per 900518 Request for Programmed Enhancements for Generic Ltr 88-171990-06-29029 June 1990
Informs That Tech Spec Actions Identified in Util Addressed as Part of Tech Spec Improvement Program,Per 900518 Request for Programmed Enhancements for Generic Ltr 88-17
3F0690-22, Forwards Annual Financial Repts for 1989 for Orlando Utils Commission & Cities of Bushnell,Leesburg,Ocala & Tallahassee,Per 10CFR50.71(b)1990-06-27027 June 1990
Forwards Annual Financial Repts for 1989 for Orlando Utils Commission & Cities of Bushnell,Leesburg,Ocala & Tallahassee,Per 10CFR50.71(b)
3F0690-19, Responds to Deviations Noted in Insp Rept 50-302/90-15. Corrective Actions:All Reg Guide 1.97 Category 1 Instruments on Main Control Board Marked & Engineered Safeguards Matrix Indicating Lights Arranged in Unique Array1990-06-25025 June 1990
Responds to Deviations Noted in Insp Rept 50-302/90-15. Corrective Actions:All Reg Guide 1.97 Category 1 Instruments on Main Control Board Marked & Engineered Safeguards Matrix Indicating Lights Arranged in Unique Array
ML20043H5781990-06-21021 June 1990
Responds to Generic Ltr 89-06, Spds. All Open Issues Identified in NRC SER & Plant SPDS Satisfies NUREG-0737, Item I.D.2 & Suppl 1
ML20044A6121990-06-21021 June 1990
Forwards Payment of Civil Penalty,Per NRC 900524 Order Based on Findings in Insp Rept 50-302/89-09
ML20043J0221990-06-21021 June 1990
Submits Info in Support of Tech Spec Change Request 175,Rev 1,Suppl 1 Re Spent Fuel Pool Storage Capacity at Plant
ML20043H4151990-06-21021 June 1990
Forwards Response to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions.
3F0690-18, Responds to Violations Noted in Insp Rept 50-302/90-09. Corrective Action:Temporary Lettering Placed on Index Plates for Consistency W/Previous Markings Immediately Following Discovery of Error1990-06-20020 June 1990
Responds to Violations Noted in Insp Rept 50-302/90-09. Corrective Action:Temporary Lettering Placed on Index Plates for Consistency W/Previous Markings Immediately Following Discovery of Error
ML20043H2901990-06-15015 June 1990
Forwards Results of Refuel 7 once-through Steam Generator (OTSG) Eddy Current Insp,Per Tech Spec Section 4.4.5.5.Eight Defective Tubes & Two Administratively Plugged Tubes in OTSG a Resulted from Review of Insp Data
ML20044A0641990-06-13013 June 1990
Forwards Rev 5 to Physical Security Plan,Replacing Currently Approved Rev 4 W/Amends.Rev Withheld (Ref 10CFR73.21)
ML20043G2271990-06-12012 June 1990
Suppls 900604 Ltr Describing How Control Room Habitability Dose Would Be Adversely Affected by Elimination of Reactor Bldg Flood Vol Unless Overly Conservative Failure Postulations Also Changed.Quarterly Updates to Be Provided
ML20043G3711990-06-12012 June 1990
Forwards 1990 Internal Cash Flow Projection for Plant Which Updates Utils Utilization of Alternative (E)
ML20043G2361990-06-12012 June 1990
Forwards Info Re Fire Protection Sys Reliability for Providing Water to Intermediate Bldg Following High Energy Line Break.B&W Issued Contract to Verify Mass/Energy Release & Motor Starters & Terminal Blocks Insulated
ML20043F1601990-06-0404 June 1990
Provides Supplemental Info on Reactor Bldg Flooding,Per Util 900517 Ltr Describing Resolution Plan Being Pursued.Util Has Limited Vol of Water Contributed by Borated Water Storage Tank & Sodium Hydroxide Tank to Flood Level
ML20043C8721990-05-31031 May 1990
Forwards Rev 0 to Crystal River Unit 3 Cycle 8 Core Operating Limits Rept, Per Tech Spec 6.9.1.7
ML20043B8431990-05-24024 May 1990
Describes Alternative Testing of Reactor Bldg Spray Suction Valves BSV-1 & BSV-8,per Generic Ltr 89-04.At Least One Valve Will Be Disassembled & Inspected During Each Refueling Outage Using Alternate Insp Method
ML20043B2771990-05-18018 May 1990
Advises of Mod to Original Commitment & Plans to Store Seal Ring in Original Storage Location During Plant Operations, Per 790606 Ltr.Mod Minimizes Personnel Exposure & Enhances Seal Plate Leak Tightness Due to Less Handling
ML20043B0321990-05-17017 May 1990
Provides Details of Resolution Util Will Pursue Re Reactor Bldg Flooding Detailed in Encl LER 90-005.Mod Will Be Installed to Add Alarm in Main Control Room to Indicate When Flood Level Reaches Point & Operator Action Begins
ML20043A5441990-05-16016 May 1990
Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project
ML20042G7681990-05-10010 May 1990
Submits Unsatisfactory Performance Testing Incident Repts, Per 10CFR26, Fitness for Duty. Results of Three Positive Blind Test Samples Certified to Contain No Drugs
ML20043A4931990-05-10010 May 1990
Forwards Executed Amend 8 to Indemnity Agreement B-54
ML20042G2101990-05-0707 May 1990
Provides Notice of MW Kirk Permanent Reassignment from Position & Requests Termination of Senior Reactor Operator License 20481-1,effective 900505
ML20042E8611990-04-26026 April 1990
Forwards Annual Financial Repts for Six Participating Owners of Plant
ML20012F2941990-03-30030 March 1990
Forwards Nonproprietary Rev to 51-1176431-02, Crystal River 3 Reactor Vessel...Temp Overpressure Protection, in Support of Tech Spec Change Request 174,Suppl 1 Re Response to Generic Ltr 88-11
ML20042D8321990-03-30030 March 1990
Provides Supplemental Response to Station Blackout Rule Implementation & Affirms That Diesel Generator Target Reliability Will Be Maintained
ML20012E2041990-03-23023 March 1990
Requests Temporary Waiver of Compliance Granted on Tech Spec 3.9.8.2 Re DHR Power Source Requirements
ML20012D9471990-03-21021 March 1990
Requests Approval of Capsule Withdrawal Schedule in Table 3-19 of BAW-1543,Rev 3, Master Integrated Reactor Vessel Surveillance Program to Allow Plant Refuel 7 Outage Plans to Continue on Schedule.Changes Needing NRC Approval Listed
ML20012D7371990-03-19019 March 1990
Responds to Generic Ltr 89-19 Re Resolution of USI A-47. Util Will Implement Appropriate Sys to Protect Against Overfill Concerns
ML20012C4501990-03-13013 March 1990
Forwards Listing of Insurance Policies in Place for Plant as of 900225
ML20012B4821990-03-0707 March 1990
Forwards Inservice Insp Pump & Valve Program Relief Request V-371 Proposing Alternate Acceptance Criteria Requirements for IWP-4150 for Fluctuations in Hydraulic Instrument Readings
ML20012B3651990-03-0101 March 1990
Lists Five Addl Drugs Included in 10CFR26 Re fitness-for- Duty Testing Program.Specimens Identified as Positive on Initial Screening Will Be Confirmed Using Gas Chromatography or Mass Spectrometry at Listed cut-off Levels
ML20012A4041990-02-27027 February 1990
Forwards 1989 Annual Rept of Personnel Exposure in Accordance w/10CFR20.407 & Tech Spec 6.9.1.5.(a) & Annual Rept of Facility Changes,Tests & Experiments in Accordance w/10CFR50.59
ML20006G1731990-02-23023 February 1990
Advises That Util Voluntarily Agrees to Participate in Emergency Response Data Sys Proposed in Generic Ltr 89-15
ML20011F2411990-02-21021 February 1990
Provides Followup on & Documents Discussion in 900116 Meeting Re Emergency Diesel Generator Loading
1990-09-20
[Table view] |
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Mr. Darrell G. Eisenhut, Director N # Ec Division of Licensing /
C .:. D U.S. Nuclear Regulatory Commission ~~
Washingcon, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. OPR-72 NUREG-0737 - Post-TMI Requirements Items II .B.3 and II .F.1.
Dear Mr. Eisenhut:
Pursuant to your October 31, 1980 letter and our October 30, 1981 letter, Florida Power Corporation hereby documents the design details of our modiff-cations to address the subject NUREG-0737 items. Specifically, we have included descriptions of the following:
ITEM DESCRIPTION II.B.3 Post-Accident Sampling System II.F.1.1. Noble Gas Effluent Radiological Monitor II.F.1.2. Containment and Auxiliary Building Effluent Monitors il.F.1.4. Containment Pressure Monitor II.F.1.5. Containment Water Level Monitor II.F.1.6. Containment Hydrogen Monitor Item II.F.1.3 (High Range Radiation Monitors) information was provided to you in our October 30, 1981 letter.
The systems described in this submittal meet all the technical requirements of Item II .B.3, II .F .1.1. , II .F.1.2. , II .F.1.4. , II .F.1.5. , and II .F.1.6. of NUREG-0737. Therefore, Florida Power Corporation confirms that no technical deviations exist. (reference your December 9, 1981 letter, Stolz to Hancock) 8201040033 011230" /
f'ph 1 PDR ADOCK 05000302 P PDR $ri General Office 32o1 inirty-tourtn street soutn . P O Box 14042. st Petersburg. Florida 33733 e 813-866-5151
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. Mr. Darrell G.- Eisenhut, Director Page Two December 30, 1981 Should 'you have any questions regarding the attached information, please contact this office.
Very truly yours, 0 MS David G. Mardis Acting Manager Nuclear Licensing Klein(W01)D37-1 Attachments
- Attachment 1 II.B.3 Post-Accident Sampling Capability The post-accident Reactor Coolant System and Containment Atmosphere System (RCS and CAS) monitoring and measurements systems for Crystal River Unit 3 are shown in Figures 1 and 2 (attached). These systems satisfy the technical requirements of item II.B.3 of NUREG 0737.
Ihe sample delivery portion of the RCS post-accident radiological and chemical analy-sis system consists of the capability to utilize the existing RCS sample points as well as two new cold leg sample points from either loop A or B. In addition, a low pressure sample delivery system provides samples from the Reactor Building sump, Decay Heat system (both loops) or Miscellaneous Radwaste Storage Tank. The sample after undergoing radiological analysis can either be returned to the Makeup tank, Miscelan-eous Radwaste Storage Tank, or the Reactor Building sump, while the chemical analysis sample return goes only to the Miscellaneous Radwaste Storage Tank or the Reactor Building sump.
The RCS liquid post-accident radiological analysis system consists of an on-line isotopic analysis system which will identify and quantitatively measure the radio-nuclides in the Reactor Coolant and Reactor Building sump samples. The Automated Isotopic Measurement System (AIMS) utilizes a high resolution germanium detector to provide gama-ray spectroscopic informatica by which the individual fission product concentrations within the reactor coolant and other liquid streams can be determined.
The AIMS is automatically controlled by an internal computer system which also pro-vides the computational ability needed for reduction of the gama-ray spectral data to produce individual concentration values.
The wide range of measurement capability, normal to accident levels, is achieved by the use of multiple counting geometries for both samples. A tungsten-lined collimator with multiple apertures is used to view the appropriate sample line. Sample flow through close in (routine) and faraway (accident) sample lines is automatically directed by computer controlled solenoid valving based on gross count rate measure-ment. All liquid flow paths are designed for reactor pressure conditions to assure representative samples and to minimize degradation and crud buildup. A planar or coaxial germanium detector is selected based on the measurement emphasis desired. The coaxial detector is favored for low count rate and high energy (normal) conditions.
The planar detector is favored whenever accuracy of high count rate and lower energy range measurements (accident) is deemed most important. Automatic calibration is per-formed using a mixed radionuclide calibration source.
Emerging from the AIMS, the RCS sample is conditioned by passing first through a cooler (heat excnanger) followed by pressure reduction valves before entering the chemical analysis section. In the case of severe core damage, where cladding-water chemical interaction has occurred, the dissolved Hydrogen concentration may exceed the limits of solubility in the depressurized sample and a two-phase condition may exist in the fluid at this point. A phase (or gas) separator is incorporated into the system to permit the removal of the gas phase. The capability to improve the opera-tion of the phase separator under conditions of low disolved gas concentration is pro-vided by the optional addi tion of Nitrogen sparge gas just prior to the phase separator.
Klein(II.B.3)NO37-1 r
. Tne separated gas and liquid phases are then subjected to detailed chemical analyses.
The gas phase is analyzed for Hydrogen content by in-line thermal conductivity. Known Hydrogen gas mixture concentrations may be injected for calibration. Total dissolved gases may be determined by flow rate instrumentation incorporated into the system.
The liquid phase flows through analytical 6 nodules which measure Boron and Chloride concentration as well as determing the pH value.
The pH and Boron determinations in the RCS sample will be made by a post-accident Boron (Boric acid) analyzer. This unit utilizes specific fon electrode technology to measure the Boric acid content of the RCS sample. The pH value is also provided by this unit. Another specific ion electrode module measures the Chloride ion concentra-tion. Both the Boron /pH and Chloride analyzer units incorporate routine standardized solution injection to maintain system calibration. The electrode systems used in systems have been tested by exposure to intense gama radiation fields without problems.
The sample delivery portion of the CAS Post-Accident Radiological Analysis System con-sists of three possible sample points within the Reactor Building. fwo of these sample points are shared by the Hydrogen Monitoring System and the other is used by the existing Reactor Building monitor RM-A6. The sample after undergoing radiological analysis is returned to the Reactor Building through the RM-A6 return penetration.
The CAS gaseous post-accident radiological analysis system consists of an AIMS, basically identical in function to the one utilized for the RCS system. The CAS AIMS has the same dual sample high and low range flow paths with one side used for plant effluent monitoring and the other for containment atmosphere monitoring.
All sample flow outside the AIMS on both the RCS and CAS Post Accident Radiological Analysis Systems is manually controlled by solenoid valves from mimic control panels located in the count room. These panels contain flow path diagrams, valve control switches (except for valves designated containment isol ation), valve position inaicator lights, and instrumentation necessary to provide the operator timely information on system status.
Both the RCS and CAS sample line analysis system incorporate the ability and hardware to permit collection of grab samples in shielded containers for onsite off-line analysis or for shipment to Oak Ridge National Laboratory for additional analysis.
AIMS Operation and Calibration The AIM's are equipped with a mixed nuclide standard calibration source containing Ba-133, Cs-137, and Co-60 to provide gamma-rays in the range of 80 to 1332 KEV. The automated system will regularly perform a calibration against this standard. The operating software for the AIMS contains stored absolute counting efficieny data for each of the sample line/ moving collimator combinations which were experimentally measured at the factory. Any changes in the built-in source counting efficiency curves will reflect changes in detector operating parameters that will affect the actual sample line counting efficiencies in a proportional fashion. Therefore, changes in the counting efficiency as measured for the built-in standard will be used to correct or modify the stored efficiency coefficients for each actual sample geometry.
Klein(II.B.3)ND37-1 Chemical Analyses Operation and Calibration The cooled and depressurized RCS sample passes to the phase separator, where the liquid and previously dissolved gases part company. The liquid phase continues on through the boron and chloride analyzers which are microprocessor controlled.
Reservoirs of standard solutions of Boric acid /pH buffer and Sodium Chloride are in-cluded in these respective analyzers, so that routine calibration is automtically performed at operator-selected intervals.
The separated gas stream is analyzed for hydrogen by thermal conductivity sensors which are routinely calibrated by passing known concentration Hydrogen gas mixtures through this analyzer.
The specifications for the Boron /pH and Chloride Analyzer units are:
RCS Boron /pH Analyzer Specifications Measurement Technique Boron Ion-selective electrode measurement of Sodium and pH after addition of Sodium Hydroxide to sample and calculation of Boron concentration by computer.
pH Direct ion-selective electrode measurement Measurement Range Boron 10-6500 ppm as Boron pH 0-14 pH Analyzer Operation (a) Continuous sampling under manual or computer control (b) Multiplexed measurement of Boron or pH with minimum multiple interval of 5 min.
(c) Manual or automatic calibration Sample Input Requirements Pressure: 40-100 psig Flow rate: 20-50 ml/ min Temperature: 10-50*C Mdste Outlet Requirements Pressure at analyzer outlet not to exceed 10 psig at 50 ml/ min i
Klein(ll.B.3)NO37-1 Ambient Conditions for Temperature: 10-50*C Sensors - Max Radiation 00se: .1.5x107 Rads TID Max Radiation Dose: 1.5x106 Rads /hr Max Relatived Humidity: 98%
Accuracy and Repeatability Boron.+5%
pH + 0.01 Response Time 2 min. for 90% of step change, minimum Boron /ph multiplex interval 5 min.
Interference Lithnium Hydroxide not to exceed 50 ppm.
RCS.Chioride Analyzer Specifications Measurement Techni_que Ion-selective electrode measurement after addition of conditioning reagent.
Measurement Range 0.1-100 ppm as chloride Analyzer Operation (a) Continuous sampling under manual or computer control.
(b) Manual or automatic calibration.
Sample Input Requirements Pressure: 40-100 psig Flow Rate: 20-50 ml/ min-Temperature: 10-50*C Waste Outlet Requirements Pressure at analyzer outlet not to exceed 10 psig at 50 ml/ min Ambient Conditions for Temperature: 10-500C Sensor Max Radiation Dose: 1.5X10 7 Ra s TIO Max Radiation Dose Rate: 1.5X10 grads /hr Max Relative Humidity: 98%
Accuracy and Repeatability iS% or 0.1 ppm, larger of two Response Time 2 min for 90% step change Interference Total Iodine (as I) not to exceed 10 ppm.
Klein(II.B.3)NO37-1 1
Attatnment 2 II.F.1. & .2 Effluent Monitors The piping and instrument diagrams of the' Reactor Building and Auxiliary Building Effluent Monitors 'for Crystal River Unit 3 are shown in Figure 2. This system is an update of-the' preliminary design of the Additional Accident Monitoring-Instrumentation submitted by Florida Power Corporation 'on August 17, 1981.
) UPGRADED CONTAINMENT AND AUXILIARY BUILDING EFFLUENT MONITORS i.: The existing Radiation Monitoring System (RMS) equipment permits the measurement of
, noble gas fission products in the effluent streams from the Reactor Buil_ ding vent (RM-A1) and the combined Auxiliary and Fuel Handling Building vent (RM-A2). The units also collect and monitor particulate and Iodine -activities. The existing equipment progides megsurement capability for noble gas fission products in the range of 10-6 to 10- C1/cm (as Kr-85). To comply with Regulatory ' Guide '1.97 and NUREG-0737 post-accidpt to 10 requi{ements, Ci/cm _for the Reactor Building the upper limits for noble vent gas measurements monitor- and to 103must M Ci/cm3 "for - the
. Auxiliary and Fuel Handling Building monitor. This will be accomplished by installing additional wide range, halogen-quenched GM detectors and ionization chambers on the 4
sample lines from each exhaust vent. These will measure the noble gas content after the existing monitoring units (i.e., 'RM-Al and RM-A2) are off-scale. The mid-range 3
detector (GM tube) will measure the noble gas content of the flowing gas stream in a 10 liter chamber with " reentrant" geometry, 1.e., similar to a Marinelli beaker 1 configuration. The high-range ionization chamber detector will view the shielded
! sample line through a collimator slot. The GM degector aqd ionization chamber pairs will - cover the C1/cm3 to >10 C1/cm3 (for the Reactor Building
< air effluent) orrange to >103 of from <g0-2 C1/cm (for the Auxiliary Building air effluent).
The lower range detector systems will be bypassed by the sample air flow and purged 4 with clean air when the noble gas concentration exceeds their range so as to protect l 3
their integrity and keep them operable for use when the radioactive noble gas con-centration returns to normal.
All exhaust air from these sampling and monitoring systems will be returned to the
[ appropriate exhaust duct so as to avoid contamination of the room air in the vicinity of the monitor units.
l Noble Gas Monitor Operation and Calibration L Following modifications, the RM-Al and RM-A2 units will still function as before in a
" normal" operating mode. Should the normal- range of measurement on the low and mid-
- range units be exceeded, valves will isolate the lower range measurement components to '
- prevent excessive contamination and over-range damage' to the sub-system. As the con-centration returns towards normal levels, the more sensitive low-range sub-systems l will be re-activated by appropriate valve actuation.
! ' Existing, low-range calibrations for RM-Al and RM-A2 will be used with necessary cal-L culated conversion from Kr-85 units to Xe-133 equivalents .provided to the system
- operators. The newly added mid-range and high-range detectors will be supplied with
- Klein(II.F.1)ND37-1~
w e e rd na er w-e e-w- v.w-g-,pn.,,,.rv,-%.,%,,-,-y,pepy , , _
. factory calibrations to standardized Xe-133 concentrations where practical. Other-wise, calculated sensitivity values will be used. Check source respo'nse will be employed to routinely determine the relative detector response after installation.
The high-range particulate and Iodine grab samples utilize dual shielded combination cartridges which contain a standard particulate filter and Iodine absorption canis-ter. Ir. dependent isokinetic lines from the effluent ducts supply these shielded samplers which have a flow rate of one liter per minute. Shielding is provided by about three inches of lead around the cartridges which should be adequate for the <3 I Ci of particulate and Iodine activity expected to be collected in a 30 minute sampling period at a maximum effluent concentration of 100 Ci/ml. Each of the samplers has duplicate shielded cartridges connected in parallel so that continuous sampling can be achieved while one sample is removed for lab analysis.
Connections are also provided so that the effluent sample flows may be routed through the AIMS provided for Reactor Building atmosphere isotopic analysis. The AIKS will provide plant personnel with detailed qualitative and quantitative isotopic analyses of both effluent streams. Discussion of the AIMS is contained in the Post-Accident Sampling System descriptions (Item II.B.3).
i Klein(II.F.1)ND37-1
Attachment 3 II.F.1.4. Containment Pressure Monitor Florida Power Corporation will install two safety-related instrument strings to monitor wide-range containment pressure. Each instrument string shall con-sist of the following components:
- Rosemount Pressure Transmitter
- Lambda Power Supply
- Foxboro Current to Voltage converter
- Foxboro Voltage Isolation Circuit
- Bailey Edgewise Indicator
- Leeds and Northrup Speedomax 100 series Recorders
- Miscellaneous electrical equipment (cable, conduit, terminal boards, fuses and resistors).
Each system has been designed and will be installed to meet the design re-quirements of NUREG-0737 (including Regulatory &Jide 1.97, Revision 2).
Pressure Transmitters The requested ranges for these transmitters is 10 psia to 3 times design pres-sure for concrete containments. Design pressure for the Crystal River Unit 3 containment is 70 psia. The Rosemount transmitters have been purchased with a 0-300 psia range. The pressure transmitters have been subjected to a type testing qualification program to demonstrate qualification for Cl ass 1E service.
Power Supplies The power supply is presently scheduled for qualification to Class 1E service in accordance with IEEE 323-1974 with a projected completion date of the third quarter 1982. It is presently qualified to IEEE 323-1971 Class 1E require-ments. These power supplies are to be seismically mounted, one each, in the ES Test Cabinets 3A and 3B.
Foxboro Equipment The Foxboro current-to-voltage converters and the voltage isolation circuits are Class 1E qualified modules used to process the signals from the transmit-ters and relay them to the main control board indicators and the recorders.
These modules are seismically mounted in Relay Racks 4A and 4B.
System (Desc)D69-3 The Engineered _ Safeguards sections of the main control board presently have containment pressure indication on a Bailey RY indicator with a single indica-tion. -These indicators will be replaced with new Bailey RY 2331 indicators with both wide and narrow-range indication. The seismic integrity of the main control board is not impacted; however, the Bailey Type RY indicator itself requires ' qualification for Class 1E service. In order to demonstrate that qualification, an existing RY indicator, in service at Crystal River Unit 3 for 5 years was seismically . tested and qualified at Wyle Laboratory in accordance with the requirements of IEEE-344-1975.
Leeds and Northrup Speedomax 100 Series Recorders The existing narrow range containment pressure signal is presently recorded in the control room. In order to supplement that,the wide range signal will be recorded, but at Relay Racks 4A and 4B. The recorders purchased for this, the Leeds and Northrup Speedomax 100 Series, are presently being qualified for
' Class 1E service with a projected completion date of June 1982.
Pressure Monitor Response Time The fixed response time (63%) of the Rosemount Pressure Transmitter at 1000F is 0.2 seconds. Since this instrument is for indication only, this response time is adequate.
Pressure Monitor Accuracy Transmitter i0.25% of span Foxboro modules i0.25% of span Bailey indicator tl.0% of span L&N recorder 0.5% of span Indicator string (transmitter and indicator) tl.25% of span.
Recorder string (transmitter, 2 Foxboro modules, and recorder) 11.75% of ' span.
System (Desc)D69-3 '
Attachment 4 II.F.1.5 Containment Water Level Monitor Florida Power Corporation will install four (4) safety-related instrument strings, two to monitor containment sump level (elevation 85'0" to 95'0") and two to monitor containment flood level (elevation 95'0" to 105'0"). This system shall replace the existing sump level monitors. Each instrument string shall consist of the following components:
Transamerica Delaval Level Transmitter
- Transamerica Delaval Level Receivers.
- Foxboro Power Supply Foxboro Current Isolation Circuit
- Foxboro Voltage Isolation Circuit
- Bailey Eagewise Indicator
- Leeds and Northrup Speedomax 100 series recorder
- Miscellaneous electrical equipment Each system has been designed and will be installed to meet the design re-
- quirements of NUREG-0737 (including Regulatory Guide 1.97, Revision 2).
Level Transmitters and Receivers The specified range of the level transmitters, in accordance with Regulatory Guide 1.97, is from the bottom of the sump to the level of the containment filled if 600,000 gallces of water were dumped into it. This level cor-responds to an elevation of 102.44' at Crystal River Unit 3. Two of the new instrument strings will measure the sump level and two will measure level to elevation 105'0". The transmitters purchased (and their associated receivers which are to be mounted in the Relay Racks 4A and 4B) are presently being qualified to Class 1E. standards in accordance with IEEE-323-1974 with project-ed completion being mid 1982.
Foxboro Equipment The Foxboro Power Supplies, Current Isolation Circuits and Voltage isolation circuits are Class 1E qualified modules used to process the signals from the -
transmitters / receivers and relay them to the main control board indicators and-the recorders. These modules are seismically mounted in Relay Racks 4A and 4B.
i System (Desc)D69-3 i
Bailey Edgewise Indicators The Engineered Safeguards sections of the main control board presently have -
containment sump level indication on a Bailey RY indicator with single indica-tion. Those indicators will be replaced with new Bailey RY2111 indicators with both a sump and a flood level indication. . Qualification of these indica-tors is included in the program described in a similar paragraph in the System Description - Containment Pressure Monitors.
Leeds and Northrup Speedomax 400 Series-Recorders Two recorders, mounted one each in Relay Racks 4A and 4B, are used to . record the four signals. . Class 1E qualification program for these reccrders is projected for completion by June 1982.
Level Monitor Accuracy Transmitters 1/2 inch (0.42% of span)
Receivers 10.5% of span Foxboro modules i0.25% of span L&N recorders 0.5%
Bailey indicator 11.0% of span Indicator string (transmitter, receiver, 2 Foxboro modules, and indicator) 12.42% of span (!2.9 inches)
Recorder string (transmitter, receiver, 2 Foxboro modules, and recorder) 1.92% of span (!2.3 inches)
System (Desc)D69-3 -
4 m %
(,
4 3- .
' Attachment-5 .
II.F.1.6 CONTAINMENT HYDR 0 GEN MONITOR- i In order = to meet' the. requirements of NUREG-0737 Item II.F.1.6, two Teledyne - q model 225CM Hydrogen monitors will be ' installed. LE ach. of .these monitors will . .
; be powered. from a different -vital AC bus. All associatedi remotely operated *i esample valves will be powered from.the same power. Two connon; sample loca-i tions will:be available. to each monitor through . independent series' containment ~ ^
' isolation valves . located outsidei the containment. The two. sample points dre: s .-
1)' Reactor Building dome area - 282' elevation; and, 2)L , Reacto.r Building-
/ : .,
l emergency recirculation duct 233' elevation. The sample return point for$oth ,
mnitors . is into the Reactor Building at .the 127' elevation, throu)ghlinde-per.@nt, series connected containment -isolation valves - outside~the Reactor
~
LBuilaing. This penetration is also the existing return" forAM-A6 (Reactor ,
Buildi.ng Atmosphere - Radiation - Monitor). The"above ' sample ~ supply and caturn - A .
~
valves. are 1/2" solenoid Target Rock Valves,125 VDC- Actuated with 7 spring closure. The remote operation / recording station for the monitors are twolnew independent cabinets located in the Control Complex . elevation 124' (Relayw[ q Room). Within each of these cabinets is located the controls for containment ,
isolation / sample valves,. main Tele @ne control , panel, hydrogen sanalysis? ;
c nal because they are normally. closed -during plant operation and under-~ admin- +
istrative control with the power locked-out. Actuation cf the c Hydrogen. ~ N s ^ ..
monitors 'will be under manual control from the individ0al Tele @ne, control. ?4 panels located in the' Relay Room. j - 1 'c}
The Containment Hydrogen Monitor System is designated Nuclear safety *related.'
The Reactor Building sample supply and return tubing.and valving fona c" closed N-safety class' 2 system outside the containment.- The Tele @ne monitors and, ,_
Target Rock isolation valves are qualified to IEEE 323-1974 an,d IEEE*S44-1975.
The purpose of the monitor is to give .real-iime infoWItfon on a7 continuous basis of - the -hydrogen gas released into the containment vessel follhing a '
Loss-of-Coolant ~ Accident (LOCA) or Main Steam Line Break (SLB). This Britical ,
information can then be used by plant operators to initiate Hydrogen,~ control _ ,
through Reactor. Building purging. Since Hydrogen levels f are indicative off '
over-heating and ' damage to the zircaloy clad fuel rods. ,the informatio_n is - -
also helpful in assessing the' extent of damage to the. reactor. Range of ' con-
~
centration ' measurement is up to 30% Hydrogen under both positive and. negative
~
s -
ambient pressure (-5'to +49 psig). ,
The system consists of two major assemblies. An analy. is unit is 1.ocated in~ -
the Auxiliary Building and contains the Hydrogen dotectors dnd allEnecessary - '
equipment necessary to extract, cool, and meter the-sample.
~
The remote control unit -is mounted in a 19" relay ~ rack. All supporting elec- ~ .
tronics, signal > conditioning, digital -readouts, recorder output, caution and high alarm setpoint controls, span- gas controls, zero and span 4djdstments, and main ~ system power controls ar,e contained in' this unit. ' '
The system is designed to connence sampling operatiohs.afterJie t occurrence of either a LOCA or SLB and continue functioning,',ti thout mainte6asce for a mini-mum of 30 days after the accident. Qualified life"oD the system is 40 years. -
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- Tibbs(II.F.1)D65-3: s-1 . . ,.
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M:N T The Hydrogen is measured by a thermal conductivity cell that produces a cur-rent flow proportional to the percent concentration of Hydrogen in the sample
. .gos. .This signal is converted to a voltage, amplified, linearized, and con-nected to a digital readout at the control unit.
EQUIPMENT FEATURES:
, A. REMOTE CONTROL UNIT
- 1. Main System Control Panel A. Power On/0ff/ Standby controls.
~
B. System status indicator lights: Standby, Ready, On.
C. System alarm indicator lights: H 2 , 0 2 , system failure.
- 2. Hydrogen Analysis Control Panel A. Digital indicator: 0-10, 0-30% H2 B. System status indicator lights: Standby, Ready, On.
C. Caution and high alarm setpoint controls.
. D. Safe, Caution, and High indicator lights.
E. System pressure, flow and wmperature alarm indicator lights.
F. Alarm, test and interrup': controls.
- G. Five (deadman) scan gas control switches.
H. Recorder output 4-20 mADC.
B. ANALYSIS UNIT -
- 1. 60" wide enclosure.
- 2. Hydrogen detection is based on the principle of thermal conductivity.
All necessar;. controls and adjustments are located in the Remote Con-3.
trol Unit. -
4 Solid-state sample cooler.
- 5. Loss of power will not prevent samplc pump from rc-starting against full containment pressure.
- 6. No catalysts are involved in the analytical measurements which poten-tially can be poisoned by compounds found in containment following a LOCA.
- 7. No reagent gases (02 ) are required.
SPECIFICATIONS:
_ *IEEE Margin not included.
A. DESIGN CRITERIA
- 1. Seismic I
- 2. Safety Class 1E
- 3. IEEE 279-1971, 323-1974, 344-1975 B. ENVIR0tNENTAL CONDITIONS
- 1. Control Unit A. Ambient Temperature: 400F to 900F B. Pressure: Atmospheric C. Relative Humidity: 10-987, D. Radiation: 1.0 X 103 Rads integrated 40 year dose
-Tibbs(II.7.1)D65-3 }
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'it 12 . Analysis Section
-?- A. Ambient Temperature: 400F to 900F normal (1220F Accident)
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, B. Pressure Atmospheric (acc' dent same)
C. Relative Humidity: 30-80% (100% acciden
- . D. Radiation: SmR/hr. dose rate (1.6 X 10g) rads integrated) 40 year
) 7' ,
, N dose and 30' day. accident
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NC. SAMPLE ENVELOPE (LOCA + 30 DAYS) a ~,
- 4. _ Relative Humidity:
~
, 10-100%
- 2. Temperature: ~400F to 4300F
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_s ;3. Pressure:fi-5 to +49 psig-j[ '4. Saturatedjwith steam spray containing 1.3 WT/% Boron as Boric Acid and J' O.52 WT/% Sodium Hydroxide
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- 5. Trace quantities of Helium, Iodine, Xenon, Krypton and Argon i 6. Integrated Radiation Exposure: 1.6 X 106 rads
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, D.-LEQUIPMENT SPECIFICATIONS
- 1. Accuracy: 2.5% of full scale (corrected)
- 2. Stabili ty: 2% of full scale (per month)
- " 3. - Response Time
- 90% of reading in 120 seconds 8, , .4. -Warmup Time: 10 minutes L %, . S. Wetted Parts: Stainless steel and viton
<6. Zero Gas Media: N2
' 7. Span Gas Media: H2 in N2 p3 8. Sample Flow Rate: 4 SCFH
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