Letter Sequence Other |
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MONTHYEARML20126C6521980-03-13013 March 1980
Summary of 800304 Meeting W/Util,B&W Licensees Re Facility 800226 Nonnuclear Instrumentation Power Supply Failure Resulting in 43,000 Gallons of Coolant Escaping Primary Coolant Sys Into Reactor Bldg.Supporting Documentation Encl
Project stage: Meeting
ML20126D1631980-04-0101 April 1980
Forwards Annotated Sequence of 800226 Events & Simplified Electrical Circuitry Schematics Per 800227 Request
Project stage: Other
ML20054F3031982-06-11011 June 1982
Submits Status of Engineering Studies Resulting from Nuclear Safety Task Force Recommendations Re 800226 Transient
Project stage: Other
1980-04-01
[Table View] |
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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:NRC TO PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA
[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
_ _ - - . - - _.
v<-(n a Yr
/.
APRll 1 1980 M: 39 I
I Dr. Richard E. Webb 2858 111 Street I Toledo, Ohio 43611
Dear Dr. Webb:
This is in response to your letter dated February 27, 1980 regarding the Crystal River sequence of events.
Mr. John 01shinski and Mr. Gerald Mazetis of g staff have contacted you concerning your questions. I an enclosing an annotated sequence of events as well as simplified electrical schematics of the Crystal River circuitry for your information.
I trust that you will find the discussions with g staff and the enclosures to this letter responsive to the questions you expressed in your letter.
Sincerely, Odginal Signed by il R. Denton Harold R. Denton, Director l Office of Nuclear Reactor Regulation !
Enclosurus:
As stated I
l l
l l l
8004180 l 1
387* 3
SEQUENCE (AS OF 2300 3/1/80) 26 7ebruary 'iransient C1-3 '
E7EST SYNOPSIS At 14:23 on 7ebruary 26, 1980 Crystal River -3 Nuclear Station experienced a reactor trip from apprcatinately 100% full power. A synopsis of key events and parameters was obtained from the plant computer's post-trip review and plant alarm summary, t'be sequence of events monitor, control rcm strip charts, and the Shift Supervisor's log.
The reactonwas operating at approximately 100 ~ full power with ' Integrated Centrol System (ICS) in auto =atic. No tests were in progress and 'mo main-tenance cabinet "Y". was being perfo:=ed in the Non-Nuclear Instrume=tation (LYI)
Time Eve :
Cause /Cece:ents
- 11. :23:00 The following is a summary of i
plant conditions prior to the trip T1ux 98.6%
RC Pressure 2157 psig r" PZR level 202 inches - j MD tank level 71 inches i g ""A" 599*I.
1 E" 600*T.
EE"1"55-r. -
T "3" 556 *F.
?$ now "A" 73 I 10 6 lbs/hr RC Eev "B" 73 I 106 lbs/hr Letdown nov 48 gpc OTSG "A" lvl (OP) 67 OTSG "I" Ivl * (OP) 65:
OTSG "A" TELV 242 inches OTSG "3" FRLV 254 inches OTSG "A" Pressure 911 psig OTSG "B" pressure 909 psig Main Stes: Pressure 894 psig Main Stes: Temp. 589'F.
Condenser Vacuum 1.76 Generated L' 834 Dr2 level 12.7 ft.
Feed now "A" 5 I 100 lbs/hr Feed now "E" 5 2106 lbs/hr Teed Pressure "A" 970 psig Feed Pressure "3" 968 psig 3 :22:21
+26 V:10 lus Fa11ure (NN' Caus e s t' ~ ' --+- vr. . Arp erently ,
pon: 1 ss. "I" supply) the positive 2! CO b:s sherred dragging .he bus voltage down te a
l zev. 3 Ege 2
' Time Event Cause /Co=nnents low voltage trip co-d' ion. There is a built-in h to % second delay e at which time all pcwer supplies will trip. There was e.r; :rdop .
indication on negative (-) voltage.
This event was missed by the
, annunciator. Following the KNI power failure, much of the c.ontrol room izidication *vas lost. Of the in5tPUD-
'entation that remained operable transient conditions made their indic-cation qu'estionable .o the operators.
14:22:2* POI?'and Spray open ,
When the positive 217"DC supply was lost due to the segr.ar.ce disenased abeve '
the signal monitors i= N!C changed sitte i causing PORV/ Spray valves to open. he PORV circuitry is designed to seal in upon actuation and did so. The resultznt loss of the negative 24 VDC haltad spray valve motor operator and prevented ,
PORV seal in fre: clezring on lov
,= pressure. It is postn1.ated that the PORT
.;_ opened fully and the spray valve stroked I for approximately h se. end. The 40% open l indication on spray va.1ve did no l actuate, therefore, the spray valve did I not exceed 40% open. l 14:13:21 ledu::ie: in Feedwa:er As a result of the "I" power supply failure many primar7 plan: control signals responded errrneously. Tec'd _
f ailed to 570*T (no-? Andication vas 557'T) producing several spurious ala_ s l Tave failed to 570*7 (dee eased) . 7:ee resultant Tave erre =:riified the reacto demand such that co_t-ol rods were dthdraves ,. to increse Tave and res.::cr power. The power in::rease was ter d-=ted at 103: by the ICS rnd a "Reacter > -d :
Eigh 11=it" alar: vs.s rece.ived. ~~he:
f ailed to g70* 7 (lev) and RC flev f t.iled '
to 40 % 10 lbs/hr in each loop (lev) .
. Both these failures created a IC .Lar:
and id 't on feedva:er which reduced feedvater flow to b:th OTSG's t:
essentially zero. I:: tine Header Pressur
, f ailed to 900 psig "high) which :t.aei the turbine valves :: Open sligh:1 ::
e mo e see me.e e e om ae* Wo e a e *e o e o e e. ..
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Rev. 5 '
\
Page 3 I Time _ Event Cause /Coennents
. regulate header pressure thus increasing
- generated megawatts. Toese combined failures resulted in a loss of heat sink to the reactor initiating an excessively high RC pressure condition.
14:13:25 Isactor "ti;/'~u:51:me Rx trip caused by high RCS pressure at 2300 psf Trip Turbine was tripped by the reactor.
14:24:02 Ei Pressure I=j. This was a computer printout and indicates Req. (nas) <50* subcooling.* See attached graph of RC Pressure /Te=. vs. Ti:ne. This graph is based on Post Trip data and actual incere thermo-couple data. Iron the reactor trip point (14 :2*
to 14:33, core exit temperature data was obtained by extrapolation and calculated data. 4 This is suppcrted by .tvo alarm data points l plotted at 18* and 21' of subcooling during this period Irom the computer. It is important
. to note that lowest level of subcool'ing was 8'F' for a ve: r short period of time.
- EDTE: This co=puter program was initiated as a resr.1: cf the TEI incident.
14:24:C2 Loss Of Ecti Suspect condensate pu=p tripped due to high Cendensate ,s ITI level. " de is verified by ???? printed by co:puter, i=dicating the level instrument ;
was over rr.nged as well as a low flov indication in the gland stea= condenser as alst !
indicated by co=puter.
14:25:50 POI 7 Isolated At this ti=e a high 10 Drain Tank level alarm var received.1"his was resultant fron the
? ORT re-d g open and was positive indicatio:
that the POK7 was open. At this time, the operator closed the PORY block valve due to ROS pressure decreasing and high RCDT level.
14:26:L*. EP: Auto - -
- t :n EPI initiated automatically due to lov RCS pressure of ".500 psis. The low pressure cendition was resultant from the PORT remainin;
'u' epen whi.le the plant was tripped. Tull E?! vas initiated with 3 pt* ps resulting in apprcximately 1100 gyn flow te the RCS. At this ti:ne, al.1 re-Wing non- essen ial R.S. l
~
isolation vs.'ves -
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R"v. 5 ,
Paga 4 T bne Eve = Cause /Com:nents were closed per TMI Lessons Ilearned Guidelines.
1 1
14:26:51 RC Pisaps Shu*dourn Operator turned RC pumps off as required by the applicable emergency procedure and B & W '
small break guidelines.
14 :27:2C R3 Pressure '-"- east =g This is first indication that RCDT rupture I disc had Yuptured. RB pressure increase data was obtained fren Post Trip Review and Strip Chart indication.
1 1- :21:30 23 ? essure Eig= This alarm was initiated by 2 psig in RE. Thisl is attributed to steam release, from RCDT. Code :
safeties had not opened at this time based upot tail pipe te=peratures recorded at 14:32:03 (Co=puter). I 1 - :21 :4 9 0500 "A" Rupt=re bat =$2 This occurred due to <600 psig in OTSG "A.
A: uatio: The low pressure was caused by OTSG "A" boilinti dry which was resultant from the BTU limit and l f ailed OTSG 1evel transmitter. This resulted l in the closure cf all feedvater and steam bloclI valves which service OTSG "A".
1.:. :21:59 br.i: 7eedvs.te- Pu:= 1. Caused by suction valve shutting due to Tripped matriz actuation in previous step.
le:22 4 :t ". IS A/I Bypass Ma=ually bypassed and HPI balanced bhtveen n11 4 no::les (Total flev approximately 1100 gy:
-small break operating guidelines).
1 - :22: 23 Started Staa: Dr:.ve: Started by operator to ensure f eedvate vas Isergency Teedvate- Pu=p available to f eed OTSG's.
1-. : 23 Cere Exit Te::. Teified The core exi: incere ther:ocouples indicated the highest core outlet te=perature value was 560*?. RCS pressure was 2353 psig atthis time,.
therefore, the subcooling margin at this time was 100*T. vd-4-un subcooling cargin for the entire transient was 8 T. It is
, postulated thai: so=e localis.ed boiling occurred is .he core at this peint as indicated by the self povered neutren dete:ters.
1 - : 1~ - :- 5:ar ed h:trr ?ri t: I:er- Same discussie as'" Started Stea= Driven-* e:-
ger:7 Teedvate ?: p gency yeedva:er Pu=p."
.- : 22 : 2 ?.: ?ressure Ei.;h :12~-5 psis) At this point, pressurizer is solid and code safety lifts (F.07-8). This is the highest RCS pressure as recorded on Post Trip Reviev.
Appcrently, -C -E lifted early due to sea
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g,go4 1eakage prior to the transient 'shd 1C7-94,1d" not lift. ,
l( 14:34:: 3 E3 Dome Ei Bad Level EM3-19 =1= w at this point Righestllavely;y
- indicated during course of incident yes 50 Qgg.
1/hr. Eigh r=Mation levels in RB caused by release of non-condensable gases in the press-
'l i, urizar and coolant.
- q. *4:33:7 3
. A:ta=pted 2:NI Repover With- This resulted in spNa observed 6n de-saar M C * '
out S.uccess gized scrip charts.
. Cc=pe:er overload Caused by overload of buffer. Resulting.'isil no further cot:puter data until buffer' catches up with prin.out.
- i 4 :3E: 2 TW-34 :'losed This valve was closed to prevent . overfeeding OTSG "3" b,eyond 100 ' indicated Operating Rangea
. ICTI ?:nn lestored Success- NNI was restored by renoving the I-NKI Power l
~".. f.2217 Supply Honitor Module. This allowed the l breakers to be rec.losed. At this' time, it was' observed that the "A" OTSG was dry, the press- l urizer was sclid (Indicated off scale high),
RC outlet te=perature indicated 556*7 (Loop A
& B ave: age), and PC average te=perature indi-cated 532*7 (Loo; A & B). "'he highest core er; thermoenuple te=;erature at this time was 531"
, RSC pressure was 2400 psis (saturation tenp. a:
this pressure is 662*?.) . This data veri.(*_d natural cirec.lation was 1: procress anci thi plant su'ocooling nargin was 131*7. (based o core exit ther=ocouples) .
- 4
- 4-: r. E.3 selstion and Cooling Ant:a ien At this time, E3 pressure increased to 4 psig and initiated E3 Isolation. The operator verified all i=:ne.diate actions . occurred propei, for EPI, LPI, and R3 ! solation and Cooling. *n increasing RI pressure was resultant fron RCV-!
passi=c EFI at this tine. /
14 : -i : ~. ~. 1- ps. set EPI,1PI and RE These "IS" systens were bypassed at this' time 1 scla tte_ and Cooling to again balance EP: flow and restere cooling water to assentia*. ar '
RCP's, letdor: ccolers , CI.OM's etc.) .'
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. Rev. 5 f.
e*
Pass 6 "ime Eve:: Cause!Comsants 14:31:5~ Rupture Ma"d=- Ara;tsation on The ac snHan was resultant from a deg- '
OTSG-B radaties of 0 S3-3 pressura. Cold emer-ger y feed uns being injected into the OTSG .
at this time. "his matriz actuation isolated all feedustar and steam block valves 'so the B-0TSG and tripped the "B" sain FW pump. Both q Emergency Ti pu=ps were already in operation '
at this time. 5-OTSO level at this time was I 70: (Operation Range).
l 14:52 EP! Thre:tled and RCS At this time, the maximum c'ere exit thermo-Pressure Ts-red :o 2300 couple temperr.:tre was 515*T, RCS pres's ure psig was 2390 psig. Therefore, the subcooling margin was 147*7. Natural circulation was in effae: as verified previously. All con-ditio=s ha.d bee: satisfied to throttle EPI.
There. fore, flow was throttled down to approx-ima:aly 250 sp= to reduce RCS pressure to l 2300 psig 1: crder to at:empt to reduce the flow ra:e threugh RC~-6 and into the RB.
l 14:53 Reastablished Letiow c-At this time, the operator va's attempting to establish RCS pressure control vis normal l
RC akeup a=i le:dovr..
14 :56 Opesed !C P =s Ie:1re.
This was done te assure the 10 pumps would Talves hav e "d - d --"- fiev at all tisnes to preven possible pu=; dz= age.
14:56:43 Bypassed :he 1-0~20 Ruptu:e *
- 7eedveter was slowly admitted '
Mz:rix a:d Reer:tilished to the I.-CTS" which' ves dry up to this peint.
Teed :: th e 1-~~ S~
Teedvs.:er vs.s ad=itted through the Auxiliary FW has.de.: vit :he ITi bypass valves. The .
feedra:e was va 7 siev in order to minimize ther:a.1 sboci :o the OTSG and resultant cepres-;
suriza: ion cf the ROS. RCS pressure control was ve y uns.ahle at this time, It 1.s postulctr that se:e,le 2* 5d'iciling.oecured in core
- at this pein:' a.s i=dicated by .self .neutren dete: ::s.
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Rev. 5 Paga 7 ;
i l
l Time Event Cause / Comments 14t57:09
- Bypassed the B-CTISG This was done to regain W control of the l Rapture Matrix B-0TSG. Level was still high in this OTSG (approximately 65: Operating Range). Therefore, feed was not necessary at this time. The Main Steam Isulation valves were open in preparation for bypass valve operation (when necessary) . .
14:57:15 Established RC Pu=p This was done in preparation for a RCP start Seal Return (vben necessary) and to *4n4=4 e pump seal ,
degradation. l i
i 15:00:09 Reestablished laval This verified feedvater was being admitted to l In A-0TSG the OTSG and made it available for core ;
cooling via natural circulation. Feed to this, generator was continued with the intent of ;
proceeding to 95% on the Operating Range.
15:00:09 77'I Subcooled "A" Loop This value was based upon "A" RCS loop parameters at this time. The "A" loop.vas being cooled down at this time by the A-0TSG fill and the operator was attempting to equalize loop temperatures.
15:15 13*7 Delta-T/Mr ned the At this time, loop temperatures were nearing Te + ' cal Suppert Cente: equalization. This delta-T was calculated from loop A & B T 's and core exit thermo-couples.
15 :17 De *
- ed Class "E" Imerge:1cy This was done based on the f act there was a
~
loss of coolant through RCV-8 in the containment and EPI had been initiated. All non-essen,ial C731 personnel vare directed re evacuate 'and; contact off-site agencies'.be-
'gan . Survey"tes: was'sen; to' Auxiliary B"4 W"g 15 :1c Opeced E=ergenry W Block At this point the A-0TSG 1evel was increasing te I-CCSG and the decision was made to comnence filling the 3-0TSG si=ultaneously. The intent was to go 95% on both OTSG's without exceeding RCS cooldown 11=its (107'F/hr) while maintaining 205 pressure control .
l
U Revo5
( Page B Time Event Cause/ Comments .
15:26 Lo Level A~ a= in Sodi=n "his.was recultant from the tank supply valve Hydroxide " a:1 cpening when the 4 psig RB isolation and cool-ing signal actuated. The sodium hydroxide was released to both LPI trains.
- Sodium Hydreizide was admitted to the RCS via. HPI fron .the BWST.
CAPProsimately 2.ppe injected into the RCS.)
15:50 Terr.inated EP: it this time, all conditions had been satis-find (per small break operating guidelines)
.c terminate EPI. RCS pressure control had been established using normal makeup ,and letdown. EPI was ter=inisted and essentially all releases to the RB were discontinued.
16:00 Commenced Pressu-1:ar At this time, RCS pressure and ta=peraturn Heatup, wre ve.11 under control. Natural circu~ ation sas functioning as designed (apprezimately 23*
dalta-T). RCS temperature was being maintaine at approxi=ately 450' . RCS pressure was apprc:
inately 2300 psig. The decisien was made at this point to commence pressurirer heatup in preparation to re-establish a stea= space in the pressurizer.
16:07 Survey Tea: Resert the Emergency Survey Tea = reported no radiatic ;
s=rvey results taken of# site were above back-s~ound.
16:05 :0- Shutdown Stez: Ori e Emergency TI Q ~2e ector driven Emergency TW pu=p was u=nin; <
heref ore, the steam driven pc=p var net neede;
~.se plant re=ained in this condition f or app-rnri=ately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, wh'.le heating up the press .
tri. er te saturation te=perature for 1800 psig ;
16:15 Press Release Eedia was notified of plant status.
15:05 Established Staa= Spa.:e Pressurizer it this point, pressurizer te=erature was typrezi=ately ( ~'O'T. Pressuri:er level was trought back on scale by increasing letdown.
Iren this peint pressurizer level vs.s reduced
. nor=al operating leve.1 and tetr.a1 ;; essure was established via pressure heaters.
. I:2: "erninated ~1us 3 In.er;es:: itate and Feder h Agencies notified.
.m_. .m _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _
! Rav 5 Page 9 l-
/
Time Evac- Cause/ Comments, g i 21:07
- Forced Tiow m'-d"M "he decision was made to re-ase=M 4=h forced in RCS flow coolir.g in the RCS at this tima. B&W and NRC vere consulted. RCP-13 and 1D were started. At this point,,RCS parameters were ,
stabilized and mat.ntained at RC pressure-2000!
I psig, RCS temperature-420*F. Preasurizar l 1 eval-235 inches. The plant was considered fW a normal configuration.
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CRl SE0lENCE OF E\ENTS TT1E E\ENTS 14:23:00 LNIT AT 98.6% POWER 14:23:21 +24 \0LT BLS FAILlRE (NNI POWER LOSS) 14:23:21 PORV AND SPRAY OPEN 14:23:21 REDLETION IN FEEDWATER 14:23:53 REACTOR TRIP /TLRBINE TRIP 14:24:G2 -
HI PRESS LRE INJ, REO. (RX2) 14:25:50 PORV ISOLATED 14:26:41 HPI ALTO' INITIATION 14:26:54 RC PDiPS SHLTDOWN .
14:27:20 RB PRESSLRE INCREASIfG 14:31:49 OTSi "A" RlPTLRE 'i ATRIX 14:32:10:M STARTED 30TH EiERiENCY FEEDWATER PC4PS 14:33 CORE E(IT TEiP. VERIFIED i 14:h3:30 RC PRESSLRE HI3H (2395 PSli) 12:34:23 RB D01E HI RAD LE\EL ;
14:M:12 NNI POWER RESTORED SLCCESSFLLLY i
14:4:31 R3 ISCLATION AND C00LItra ACTl% TION 14:45:13 BYPASSED HPI, LPI, AND RB ISOLATI0il AND C00LItG -
14:51:E7 RlPTLRE 'i ATRI( ACTlA' TION ON OTSi-3 1L: 52' HPI THROTTLED AND RCS PRESSLRE RDLCED TO 2300 PSli 1L: E5: 23 EYPASSED THE A-0TS5 RLPTLRE U.TM( AilD RE-ESTABLISHE FEED T:' THE A-0TSi 11.- : i 'EY?ASSED THE 3-0TSi RLPTLRE 'i ATRIX 1E:::::5 EE-ESTAE' ISHED ' EVEL It! A-0TS~.
15:1E
'i Ai'ilED THE TEC$11 CAL S LDPORT CENTER I
CD 3 - SEGENCE OF E\ENTS (C0ffT'D)
Tr1E E\ENT 15:17 DECLARED CLASS "B' EiEEENCY 15:50 TERiINAito HPI 16:00 C0fiENCED PRESSLRIZER HEATlJP 15:07 SLR\EY TEAi REPORT 15:08:0'4 SHLTDOW STEAi DRI\EN EiERiENCY FW P[iP .
16:15 PRESS PELEASE 18:05 ESTABLISEE STEAi SPACE IN PRESSLRIZER 18:30 TERiINA1to CLASS 'B" EiEFG ENCY 21:D7 FORCED FLOW INITIATED IN RCS I
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DESCRI? TION 07 EOUIPMENT DE7ICIENCIES The following equipment deficiencies were noted during an in depth ~'
review of the Crystal River Unit 3 transient on February 26, 1980.
- 1. Loss of the Non Nucicar Instrumentation (NNI) System (I) DC
- 2. Power operated relief valve (?ORV) failed open.
.3. Pressurizar spray valve f ailed open. .
4 Loss of indication of major plant para =eters.
- 5. Integrated Control System (ICS) response to NNI (X) fai. lure.
A. Auto initiation of Emergency Teedwater.
B. Reactor trip on loss of f eedwater.
- 6. ICS loss of 120 v AC f or 2 seconds.
- 7. Events recorder degradation.
- 8. Ccmputer alar = bu.ffer overflev.
- 9. Systems that perfor=ed adequately.
A. Reactor Protective Systa=.
B. Ingineered Safeguards Activation.
C. Control Rod Drive Systa=.' -
D. Steam Rupture Matrix. .
E. Secondary Plant Equipment.
T. Radiati:n Monitoring System.
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k h h h h h P" h hh ;z l.
>=
n f i
>- llP I N =
C - C 6 O J
+
{ ;
e- m - sg 1
- o
+ -4 Y y $ 4 h N h hh w l M
= 1 4 E 4 O -
4 E < % 4 =
S^ M 6 Y W d in m 4 C Cm
> W J E E ag W M aC <
a 3 4 W H ad t.
C . 3l", '3 E A 5.s 3 0 J W. O O to . - ;
y A m . to E. A =- A ag j M H W H >=8 1 0 C U k -
N k A ,
.a e
