|
|---|
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 UTILITY
MONTHYEARML20062E6821990-11-14014 November 1990
Forwards Insp Rept 50-302/90-30 on 900924-28.No Violations or Deviations Noted
IR 05000302/19900261990-11-13013 November 1990
Ack Receipt of Responding to Violations Noted in Insp Rept 50-302/90-26.Response Meets Requirements of 10CFR2.201
IR 05000302/19900321990-11-0707 November 1990
Discusses Insp Rept 50-302/90-32 on 900918-1005 & Forwards Notice of Violation
ML20062E0781990-11-0202 November 1990
Forwards Requalification Exam Rept 50-302/OL-90-01 Administered During Wk of 900917.Attention Should Be Given to Concern Over Exam Matl Development
ML20058F6371990-10-31031 October 1990
Forwards Insp Rept 50-302/90-29 on 900908-1005.No Violations or Deviations Noted
ML20058D6621990-10-30030 October 1990
Informs That Util Response to Bulletin 90-003, Relaxation of Staff Position in Generic Ltr 83-28, Acceptable
ML20062C1891990-10-24024 October 1990
Forwards Evaluation Rept Re Implementation of B&W Owners Group Safety & Performance Improvement Program at Plant
ML20058F1491990-10-23023 October 1990
Confirms Arrangements for Enforcement Conference to Be Conducted on 901031 at Region II Re Containment Integrity & Design Requirements for Maintaining Containment Integrity
ML20058B0811990-10-19019 October 1990
Forwards Insp Rept 50-302/90-32 on 900918-1005.Violations Noted
ML20062B5701990-10-15015 October 1990
Advises of Suspension of Action on Tech Spec Change Request 170 Re Pressure/Temp Limits Rept Until Suitable Solution Can Be Worked Out within Framework of Tech Spec Improvement Program,Per 890726 & 1031 Ltrs
ML20058B1561990-10-12012 October 1990
Ack Receipt of 900928 Response Re Violations Noted in Insp Rept 50-302/90-24
ML20062B6691990-10-12012 October 1990
Requests Analyses of Liquid Samples Spiked W/Radionuclides Be Completed within 60 Days of Sample Receipt
ML20058A9621990-10-11011 October 1990
Forwards Insp Rept 50-302/90-31.No Violations or Deviations Noted
ML20059N4111990-10-0404 October 1990
Forwards Insp Rept 50-302/90-27 on 900917-21.No Violations or Deviations Noted.Rept Withheld (Ref 10CFR2.790 & 73.21)
ML20059L9501990-09-24024 September 1990
Forwards Insp Rept 50-302/90-25 on 900812-17.No Violations or Deviations Noted
ML20059M1791990-09-11011 September 1990
Advises That Objectives & Scenario Package for Emergency Response Plan Exercise,Scheduled for 900927,acceptable
ML20059G7391990-09-0606 September 1990
Accepts Util 890601 & 1218 Responses to Item 1.b of Bulletin 88-11, Pressurizer Surge Line Thermal Stratification. Certain Issues Must Be Resolved Before Plant Meets All Appropriate Code Limits for 40-yr Plant Life
ML20059G5941990-08-31031 August 1990
Forwards Insp Rept 50-302/90-24 on 900707-0810 & Notice of Violation
ML20059H1421990-08-28028 August 1990
Requests Approved Ref Matl Listed in Encl 1,by 900926 for Reactor Operator & Senior Operator Licensing Exams Scheduled for 901126
ML20056B5321990-08-23023 August 1990
Forwards Safety Evaluation Re Util 890417 & 900330 Responses to Station Blackout Rule.Plant Not in Conformance W/Station Blackout Rule.Revised Response Should Be Submitted within 60 Days of Ltr Date.Rev 1 to SAIC-89/1150 Also Encl
ML20056B2651990-08-22022 August 1990
Advises That Review of Auxiliary Feedwater Pump Conceptual Design,Submitted in ,Continuing.Nrc Offers No Comment Presently
ML20058L4241990-07-31031 July 1990
Forwards Request for Addl Info Re Spent Fuel Pool Rerack Amend.Response to Items Should Be Submitted by 900820
ML20058N2901990-07-31031 July 1990
Advises That 900613 Rev 5 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable
ML20058Q2001990-07-31031 July 1990
Requests Supplemental Response Describing Util Corrective Actions & Date of Full Compliance,Per Insp Rept 50-302/89-18
ML20056A9191990-07-27027 July 1990
Forwards Insp Rept 50-302/90-21 on 900602-0706.No Violations or Deviations Noted
ML20055H3561990-07-11011 July 1990
Advises That 900620 Response to Notice of Violation of Insp Rept 50-302/90-09 Meets Requirements of 10CFR2.201
ML20055H3701990-07-10010 July 1990
Forwards Insp Rept 50-302/90-17 on 900501-03.Noncited Violations Noted.Corrective Measures to Assure Randomness of Chemical Testing Program & to Improve Reporting of Chemical Test Results to NRC Will Be Reviewed in Future Insps
ML20055H5751990-07-10010 July 1990
Forwards Insp Rept 50-302/90-22 on 900612-16.Violations Noted But Not Cited
ML20055H4361990-07-0505 July 1990
Advises That Requalification Program Evaluation Visit Scheduled for Wk of 900917.Licensee Requested to Furnish Approved Items Listed in Encl Ref Matl Requirements by 900716.NRC Rules & Guidance for Examinees Also Encl
ML20055E5121990-07-0202 July 1990
Forwards Safety Evaluation Re Util 831104 & 840731 Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components
ML20055D6551990-07-0202 July 1990
Ack Receipt of & Check for $100,000 in Payment of Civil Penalty Imposed by NRC Order .Corrective Actions Will Be Examined During Future Insp
IR 05000302/19900051990-06-29029 June 1990
Forwards Meeting Summary & Slides from Presentation on 900523 Re SALP 50-302/90-05.No Formal Changes to SALP Rept Needed,Therefore 900511 Rept Constitutes Final Rept.W/O Encl
ML20059M9381990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20055C5981990-05-24024 May 1990
Forwards Order Imposing Civil Monetary Penalty in Amount of $100,000,per Violations Noted in Insp Rept 50-302/89-09. Penalty Proposed to Emphasize Importance of Implementing Adequate Mgt & Programmatic Controls
ML20248D7351989-09-28028 September 1989
Requests That Impell Rept 03-0920-1186,Rev 0, Pipe Rupture Analysis Criteria Outside Reactor Bldg, Be Revised & Modified to Include Listed Conditions,Per NRC Approval to Calculate High Energy Line Breaks,Per ANSI B31.1 1967
ML20248E4811989-09-25025 September 1989
Forwards Staff Position on Preoperational Testing of Upgraded Emergency Diesel Generators to Be Implemented During Refuel 7.Type Qualification Tests Not Required Provided Preoperational Test Program Successfully Completed
ML20248E7881989-09-25025 September 1989
Advises That Encl Notice of Consideration of Issuance of Amend to License & Proposed NSHC & Opportunity for Hearing on 890809 Request to Extend Surveillance Period for Diesel Generator full-load Test Sent to Ofc of Fr for Publication
ML20248B7501989-09-22022 September 1989
Confirms 890919 Telcon Re Rescheduling & Change in Topics for Enforcement Conference on 890928,per Insp Repts 50-302/89-200 & 50-302/89-24 Concerning Insp Issues & Improper Impeller Installed on Raw Water Pump
ML20248D1381989-09-22022 September 1989
Ack Receipt of 890908 Response to Violations Noted in Insp Rept 50-302/89-17
IR 05000302/19890151989-09-19019 September 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-302/89-15
ML20248C8381989-09-18018 September 1989
Forwards Insp Rept 50-302/89-24 on 890907-08.No Notice of Violations Issued for Violations Described in Rept. Enforcement Conference to Discuss Violations Scheduled for 890928
ML20247K5711989-09-18018 September 1989
Advises That Voltage Levels Discussed in LER-86-015-1 & LER-87-007 & in Util 880229 & 0902 Ltrs Considered within Design Basis of Plant.Util Should Confirm Values for 480 & 120 Voltages by Testing During Next Refueling Outage
IR 05000302/19892001989-09-18018 September 1989
Confirms 890912 Telcon Re Enforcement Conference to Be Conducted on 890928 to Discuss Issues from Insp Repts 50-302/89-200 & 50-302/89-24 & Items Reported by Plant Staff on 890907 & 08
ML20247K5911989-09-18018 September 1989
Advises That Plant PRA Considered Fair Evaluation of Most Likely Paths to Core Damage at Plant.W/Stated Exceptions, Review of PRA Did Not Uncover Any Reason Why PRA Could Not Be Used as Aid to Evaluate Plant Mods or for Decisions
ML20247L0841989-09-18018 September 1989
Forwards Amend 8 to Indemnity Agreement B-54.Amend Increases Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu
ML20247K5531989-09-15015 September 1989
Advises That If Util Revises FSAR to Account for Revised Steam Generator Tube Rupture Mitigation Emergency Operating Procedure 10CFR50.59,NRC Will Review Evaluation as Part of Periodic Review of 10CFR50.59 Changes
IR 05000302/19890091989-09-13013 September 1989
Discusses Insp Rept 50-302/89-09 on 890424-28 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.NRC Concerns Re Insp Findings Were Discussed During 890628 Enforcement Conference
ML20247H0731989-09-12012 September 1989
Confirms 890914 Conference in Region II Ofc to Discuss Plans to Resolve Electrical Issue Prior to Restart
ML20247H4451989-09-12012 September 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-302/89-16.Severity Level Reduced from IV to V,Based on Review of Response
ML20247C2251989-09-0707 September 1989
Advises That Util 890608 Response to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs, Acceptable.Acceptance Based on Implicit Assumption of Util Commitment to Perform Action of Item 2.D
1990-09-06
[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] |
See also: IR 05000302/1987041
Text
F ,.3 ,
.,'.-
'
.- . . ..
>
MAR 15 E88 4
f
Docket No. 50-302-
License No. DPR-72
Flprida Fower Corporation
(Yr. W. S. Wilgus
LVice President Nuclear Operations
ATTN: Manager, Nuclear Licensing
i- P. O. Box 219
Crystal River, FL 32629
Gentlemen:
SUBJECT: ENFORCEMENT CONFERENCE SUMMARY
(NRC INSPECTION REPORT NO. 50-302/87-41)
This letter refers to the Enforcement Conference held at our request on
February 22, 1988. This meeting concerned activities authorized for your
Crystal River facility.
The issues discussed at th's conference related to diesel generator loading and
cooling water temperatures. A sumary, list of attendees, and a' copy of your
handout are. enclosed. We are continuing our review of these issues to
determine the appropriate enforcement action.
In accordance with 'Section 2.790 of the NRC's "Rules of Practice," Part 2,
Title 10, Code of Federal Regulations, a copy of this letter and its enclosures
will be placed in the NRC Public Document Room.
Should you have any questions concerning this matter, please contact us.
Sincerely,
t
sS
J. Nelson Grace
Regional Admiriistrator
Enclosures:
1. Enforcement Conference Summary
2. List of Attendees
3. Handout
cc w/encls: (Seepage 2)
_
eso3280179
ADOCK h ho2
DCD \\
PDR
O
H e/
- - - - - - - - - - - ---- - . - - - - - - - - - - - - - - - - -
, . ~ . ~ .
. . - . . -
,. ..
. .
- - : ^
m,
.
- MAR 151988
,
Florida Power Corporation 2
1
,
eg w/encls:
W. F.- McKee, Di rector,
Nuclear Plant Operations
M . C. Simpson, Director,
Nuclear Site Support
bec w/encls: -
'
o V Lieberman, DOE
G..'R. Jenkins, EICS
LMC Resident-Inspector
'DRS Technical Assistant
Document Control Desk
State of Florida
O
RII RII
RII RI _
AHerdt b^ AGibson
li n:tj nlon
03/4/88 03/4/88
03/j/88 03/j/88
'
RII RII
RI:
t
njak LReyes Glenkfns
R 03/iT/88
03/ /88 03/ /88 03/f/8
,
. . _ _
J
r ,
.
.
,
.
ENCLOSURE 1
ENFORCEMENT CONFERENCE SUMMARY
An Enforcement Conference was held on February 22, 1988, to discuss the
potential violation described in Inspection Report No. 50-302/87-41.
The licensee did not provide any information during the enforcement conference
which would require correction to the information in the inspection report.
The licensee did, however, point out that he reported to the NRC the fact that
the 30-minute rating of the diesel generators had been exceeded during previous
18-month surveillance test and the vendor recommended special inspections had
not been performed. This information was verbally reported on September 14,
1987, and the licensee was give verbal approval to continue operation until
September 19, 1987, when the outage began.
While addressing the root cause and corrective actions for the proposed
violation, the licensee stated that he will expedite his Configuration
Management Program. The licensee proposed extensive corrective actions
directed at the broad scope of potential design errors through the Configura-
tion Management Program. The licensee suggested a meeting, at a date to be
detennined later, to discuss the details of the program, and the handling
of problems that may come to light as a result of the review process.
The adequacy of the ultimate heat sink temperature was discussed even though
this was not within the scope of Inspection Report No. 50-302/87-41. Refer to
Enclosure 3 for details.
The licensee stated that his best estimate for the load on Diesel Generator A
is 3112kw. This value was determined by calculation and testing and,
represents a blending of the two methods. A meeting is scheduled for March to
discuss options for reducing the load below the 30-minute rating range of
3001-3300kw.
-
. .
.
.
ENFORCEMENT CONFERENCE LIST OF ATTENDEES
LICENSEE: FPC DATE: 2/22/88
FACILITY: CRYSTAL RIVER IR NO:
LOCATION: ATLANTA, GA
NAME. POSITION / TITLE ORGANIZATION
Malcolm L. Ernst DRA NRC/RII
Luis A. Reyes Director, DRP NRC/RII
Herbert N. Berkow Director, PDII-2 NRC/NRR
Harley Silver PM CR-3 NRC/NR3
Tom Stetka SRI NRC
Paul Fillion Reactor Inspector NRC/RII
T. E. Conlon Chief, PSS NRC/RII
Paul R. Tanguay Mgr. Mech /Struct Engrg FPC
Donald A. Shook Mgr., Elect /I&C Eng FPC
E. C. Simpson Dir., Nuc. Ops. Engineering FPC
and Licensing
K. R. Wilson Mgr., Nuclear Licensing FPC
D. G. Green Licensing Specialist FPC
Walter S. W11gus V. P., Nuclear Ops. FPC
R. C. Widell Mgr., Nuclear Eng FPC
R. V. Crienjak Section Chief /DRP NRC/RII
Howard Wong Sr. Enforcement Specialist NRCOE
George R. Jenkins Director, EICS NRC/RII
A. R. Herdt Chief, Engineering Bra.ich NRC/RII
B. D. Wilson Chief, Projects Branch 2 NRC/RII
McKenzie Thomas Reactor Inspector NRC/RII
R. H. Bernhard Reactor Inspector NRC/RII
M. S. Lewis Reactor Inspector NRC/RII
Bruno Uryc Enforcement Coordinator NRC/RII
John D. Schiffgens PE NRC/NRR
Dominic Tondi Section Chief NRC/NRR/ DEST
-.
m,
. . ...
. , , ,- .
ENCLOSURE 3
February 22, 1988
ENFORCEMENT CONFERENCE
AGENDA
Introduction Hally N11gus
Chronology Ken Nilson
Corrective Actions Rolf Hidell
Conclusions / Mitigating Circumstances Bert Simpson
i
l
I
%
-
.
.
. .
IHDBUM SODPE
o Tectnical Wicatica required a 60 mimte duraticm test at 2
3000 kw. 'the diesel ratirq is for S 30 airutes between 3001 ard
3300 kW.
'Iherefore, Tacti Spas (ard hence p - trres) conflict with design
basis.
o 'Ihe calculated loads were haaari cn an a==unari + == A. poet-
factor of 0.8, the actual "average" power factor is apprtaciately
0.9. Parther, sczne loads were unitted.
'Iberefore, all reported diesel loads were underestinated ard the
additice of EFP-1 to the auto cuaCud loads pHM tha
i of lew11rg the EDG beycrd it's rated mpacity,
& bility
o 'Ibctnical Specificaticns limit the ultisate heat sink (W)
tyrature to 5105'F. 'Ibe design of the closed cycle safety-
related cooling systan (N, DC) ==neri a 85'F W inlet. 'Ihe
clocu3 cycle system have a 105'F limit.
'Ihe clooed cycle limit may not be able to be maintained less than
105'F with Wad real ultimte heat sink taaperatures of up to
92*F.
-
0
-
l - -. 1
.
BERE!NCY DH! EEL Q!NERMtR
Q H EDEDGY
TIMDG IESQtIPTICH
July, 1974 PSAR revised awpac+=d lead fmn 2917 kw
(PGAR) to 2915 kw (within 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> l
rating). Both PSAR and FSAR referenced
0.s power factor.
Martit, 1975 Chapter 15 'Ibtfrim1 Specifimtims
incitzled a 60 mimte tmt at 2915 kW. ;
nans=*=r, 1975 Mc arygestad a 1004 (3000 kw) test for
60 mimtes. FPC ag er e tly agreed and
'Ibcinical R=e ifications were so issued.
-
July,1979 NEREG-0578 (2.1.7.a) regLtired motor
driven AFW ptmps be autcmatirmily 1rmiart
m emnergency bus.
July, 1979 FIC testad dIanal loads to dentmstrata
mrgin availahility. Iced was 2520 kw
without mu=?dcri for is.. -midant flow
rates or conservatively armwiting for
puma 11 loads.
Msy, 1980 FPC rrummitted to arriify EPP/EDG includirg
30 mimte trip to protect 30 minute
rating. Wimim haaari cri 2520 Mr test
value and 340 At ocultributical from EPP.
Atxpst, 1980 Re-performed arrif fied test with mi=ilar
rmults and shar+rreirgs.
Jtily, 1982 FSAR updated to reflect alculated worse
case load of 3180 kw.
August, 1986 [1Irirq perfnrmnae of SP-417 the DCP was
noted to not blodc load properly (UR 86-
15).
April, 1987 Pbllow-g to UR noted potetial for
"armaalve" voltage dip. C/CI also
calmlated worse case load >3300 kw.
>
'Ihis cala11atirn was in errut.
April, 1987 FTC rgarted (UR 87-07) voltage dips
alirfitly more non-<rmervative that
desity/limansing basis. NFC/NRR folicWed
@ extensively begiming day-after red
Itama rgart.
June, 1987 Marne case load 'calculated to be 3276
vice 3180 kw.
. _ __ .. . . - - . - _ _ - - _ - -.._ _ - . - . _. . _ _ . - _ _ . -_ _ - ____ _-
-
.
I
August, 1987 91te 1&r: lear Erginearirg riotified
Licensing of potential ocmflict between
Tacti Spec and diesel ratings.
August, 1987 FIC firumli'M NTR same day lagt; before
CErrI team ====har inquired about 'IWit.
Spec. value and it's relation to
ratings. FPC brought CErrI team q>-to-
date with our own zwiaw.
Seph=har, 1987 Colt h==arited clarified ratings,
detailed recylized maintenance and
ccrmrred with cperation tmtil Refuel VI
after meeting at Cblt, etc.
Sqtr=+cr - Octr+pr, 1987 FPC in an effort to renove e_q
ccnoervatism frun calculations looked
into debila of loads, power factors,
wM<=1t scenaries, etc. FPC ideritified
,
arti both Colt any G/CI ocmfI* power
factor error.
October, 1987 IIR 87-19 reported Tecti Spec / Design
conflict.
FTC notaa mm as ". ..'Ihe ocmflict
betwecn Tat Spec acceptance criteria and
the design rating limit was never
rarrrytized or resolved...". It was
suumarized in the space limited abstract
,
as an agparent misinterpretatics of the
ratirgs early in plant life (e.g. Wum
the 'Iwis Spec was yW).
l
1
m
_- ~ __ . _ - . _ _. _ _ _ . _ _ . _ . _ . , _ . . _ , _ _ , . _ _ . , .
_m_..-_ _ . _ _- . _ . . _ _ _, . . . . _ _ , _ _ . _ - _ _ _ - _ _ . _ . _ _ . . - _ . , _ _ _ - . , , . _ _ . . _ . _ - - .
.
MITIGEING CIRCGEEDN3S
DERENCY DIESEL GNPENIT
o FTC idmtified prtblan as a result of rreself-diarlosirq
supon== tic review prmaasw==. OS'I'I team idetification as
either dcw- eid. cn E idmtificaticn or omcurret with it.
o E is swirq extensive mocdve actions directed at broad
socpe of potential design errors through Ctnfiguration Management
s w. 'Ihis effort as undermy before ED3 probles as
riisamvered.
o 'Ihe ptatial overleed sceario is very Innote (loss of offsite
power, ocncurrmt with EDG-B failure, emcurret with interwdiate
or large break IOCA) . In fact, the evmt is ncn-medanistic for
CR-3 (4-. cdanted 11cmoed Inak-Defore-Break) .
o 'Ihe p*mtlal for timply ard effective cperator intervmticn is
good. Operator, by EDP's, has always throttled HPI flow ard
manrads EDG loads,
o E took sus, and effective u.uuvdve acticns -f ated with
Epecific prtblGR.
-
Scujht and gained Colt ardKocnourrmae to ocntime
operatitz) for a fat days prior to tear down.
-
'Ibok significant actions to IMm loads to less than 3000
kw.
-
Act:epted staff foertwst to reevaluate one arrif fication (EFP-1
trip) ard revised 'Ibch Spec charge recpest to allow cperatico
in 30 mimte ratirg.
-
Prmmad exrmpticn when NFC achinistrative su --ws couldn't-
-
han11e original staff proposal.
-
Avoided cperatar turden are unwarranted decreases in safety
mrgins in resolvirg iswawi.
o E does not have a history of significant design basis errors.
o 'Ihe invalid aas-tion was reascnable ard omaistet with irdustry
ard NRC gnirknce (R.G.1.9)
,
_ - , _ - ,_ . _ . - _ _ _ _ _ _ _ _ . _ _ _ m ,
.
l
umcarna enemms
-
1
Nf 'D!MRE\'IME ;
I
.
o %.tcic action (drgping off 1 RB Cooling thit) would harve beam
effective if naadsd.
o 'Ihe potetial for -ive Sli tauperature is sanall ( M heat
lovl in RB) .
o Limited n=har of wuds affected (Sperit Fuel Rap and control
complex Q1111er).
o Analysis conservatim my yet be adegata to overazne error.
l
I
m
,
1
__ _ . __ . . . _ _ _ . _ _ _ , - . . _ _ _ _ _ _ _ _.. . _ . _ - _ _ , _ _ _ , _ _ _ _ , . _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ , _ . _ _ . _ _ .
- _ . .
.
'.
!
l
l
I
'
ULTIMATE HEAT SIhK TEMPERATURE
Licensing Basis for 3-3 - 85'F Max.
Normally Observed Peak Susumer Temp. - 92*F
Operation Justified Until RH Temperature Exceeds 85'F
i
SM/DC Design 105'F Nax.
SM/DC Calculated Max. for LOCA
Exceeds 105'F for 25 Minutes
Peak Temperature 110*F
.
RH Temperature at 95'F
3 RB Fan Coolors Operating
All Equipment for Accident Mitigation On Line
l
'
-. _ _ - . _ _ . _ . _. - _ _ - _ _ - - ._ _ _ _ -
.
.
CRYSTAL RI'/ER UN*.T 3
CCNflGURATION M ANAGEM' INT PROGRAM
-
- _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ - _ _ ______________ _________ ___ - - -
.
.
'
FRIB4 REACTIR 3 TD REACTIR
VESSEL VESSEL -
.
s m
- "
DECAY K AT
v
lI m m
~
.
.- + - -
l
PLANT *- PLANT
- HEAT -*'
HEAT -*'
'
LOADS n LOADS
, NuCtE4R StRv1CES
j q_. q_ g CLDSED CYCLE DECAY EAT _g, _,,
- CM LING PU W S
n CLDSED CYCLE
l COOLING PUWS
'
105 Deg
105 Deg
i uuctEaR SERvrCES
n
[
-
s
-
s
-
m
-
DECAY EAT
, CtDSE CYCtE
'N , E AT DCHaNGERS
_ s _
n -
' -
NUCLEAR SERVICES g , r
SEAVATER PUWS DECAY EAT ~
SEAVATER PUMPS
SEAVATER
45 Deg~ DiSCuaRGE V
r i
.
. . .
CONFIGURATION MANAGEMENT AT CR-3
o FPC HAS ALWAYS BEEN SENSITIVE TO CONFIGURATION MANAGEMENT
ORIGINAL DRAWINGS MAINTAINED BY FPC
CONTROLLED DESIGN CHANGE PROCESS
PROCEDURE CHANGE CONTROL
o PROGRAMMATIC ENHANCEMENTS
ENHANCED CONTROL OF A/E'S 1980
MODIFICATION PRDJECT MANAGEMENT JULY 1983
DESIGN BASIS DDCUMENT PROGRAM OCT. 1983 - DEC. 1987
ENHANCED MODIFICATION PROCESS AUGUST 1984
INSTRUMENT DATA SHEET / CALIBRATION SHEET SEPT. 1985 - SEPT. 1989
REALIGNMENT OF ENGINEERING ORGANIZATION 1986
ENGINEERING ASSURANCE ORGANIZATION 1986
QUALITY PROGRAMS AUDIT PROGRAM 1986
ELECTRICAL DRAWING UPGRADE 1986 - 1988
ANALYSIS BASIS DOCUMENT 1987 - 1988
SURVEILLANCE PROCEDURE VERIFICATION / VALIDATION 1987 - 1988
COMPREHENSIVE DRAWING SYSTEM REVIEW 1987
SAFETY LISTING INTERIM ENHANCEMENTS 1987
CONFIGURATION MANAGEMENT PROGRAM PLAN 1987
TAG NUMBER DATA BASE
SAFETY LISTING COMPUTERIZATION
o WEAKNESS IN DOCUMEliTATION OF ORIGINAL DESIGN DEVELOPMENT
-
r. ,
,= . . .
?
CONFIGURATION MANAGEMENT PROGRAM
o IMPROVE THE QUALITY OF CONFIGURATION DATA
DESIGN BASIS RECONSTITUTION
DESIGN BASIS DOCUM:NT
ANALYSIS BASIS DOCliMENT
PRIORITIZATION
CONSISTENCY OF THE DATA
o DEVELOP OVERALL CONTROL ELEMENTS TO ASSURE HIGH QUALITY DATA
IS MAINTAINED
IDENTIFY ALL CONFIGURATION DOCUMENTS
IDENTIFY ALL SOURCES OF CHANGE
INTEGRATE OVERALL CONFIGURATION CONTROL
o EXPAND USER CAPABILITY OF THE DATA
COMON DATA BASE
BASED ON TAG NLMER
LINK TO OTHER AUTOMATED SYSTEMS
SPARE PARTF
AUTOMATED WORK REQUEST
CHANGE STATUS
-
.,- , ~ _ - , - - - - - . - - - . _ , - - - - - - . - _ _ , . - , . . . - , . - .
.
. ..
_
.
.
.
PROGRAM PLAN
o SAFETY CLASSIFICATION LIST PROGRAM
REQUIREMENTS DEFINITION
SOFTWARE DEVELOPMENT
DATA DEVELOPMENT
DATA MANAGEMENT SYSTEM DEVELOPMENT
IMPLEMENTATION
o DATA PROGRAMS
ENGINEERING CALCS PROGRAM
ENGINEERING DRAWING PROGRAM
ENGINEERING DATA LIST PROGRAM
CORE DATA PROGRAM
SURVEILLANCE PROGRAM VERIFICATION PROGRAM
ISI REQUIREMENTS INTEGRATION PROGRAM
DOCUMENT UPGRADE PROGRAM
TAG YALIDATION PROGRAM
o PROCESS ENHANCEMENT PROGRAM
CONFIGURATION CONTROL PROCESS DEVELOPMENT
CM DATA DEVELOPMENT PROGRAM
o MAINTENANCE SYSTEM PROGRAMS
DEVELOPMENT AND IMPLEMENT MAINTENANCE SYSTEM
CM INTERFACE WITH MAINTENANCE SYSTEM
.
- - . _ . , , _ _ _ _ _ _ , . . . . _ , . . . _ _ - . _ _ . . , _ . _ _ _ _ _ _ _ . . . , , .__ __
,
_ _ _ _ _ _ _ _ _
,. . .
. .
o CMIS DESIGN
CONCEPT DEFINITION
INTEGRATED SYSTEM REQUIREMENTS
INTERFACING SYSTEM REQUIREMENTS
REQUIREMENTS FINALIZATION
o CMIS SOFTWARE DEVELOPENT PROGRAM
SAFETY CLASSIFICATION LIST SOFTWARE
CMIS INTEGRATED SOFTWARE
CMIS INTERFACING SOFTWARE
DATA DEVELOPENT SUPPORT
o IMPLEMENTATION PROGRAM
OPERATING ORGANIZATION
TRAINING
CM PROGRAM DOCUMENTATION
o PROGRAM MANAGEMENT
,
_ _ _ _ _ _ _ _ _ _ . - . _ _ . . _
c. -.,
,... r,
,
, . .
ORGANIZATION
o PROGRAM MANAGER AND KEY LEAD POSITIONS FILLED BY FPC PERSONNEL
KNOWLEDGE OF PLANT, PA0BLEMS AND SYSTEMS
CONTROL OF SCHEDULE AND BUDGET
o PROGRAM MANAGER REPORTS TO MANAGER, NUCLEAR OPERATIONS ENGINEERING
RESPONSIBLE FOR DESIGN CONTROL /CR-3 DESIGN BASIS
INTEGRAL PART OF ENGINEERING ORGANIZATION
STRONG INTERFACE WITH OTHER KEY FUNCTIONAL AREAS
o IN-HOUSE CONTRACTOR SUPPORT
o FORMALLY IN EFFECT MARCH 1988
.
%
l
l
9
-,
,.
,
- .
SCHEDULE !
o OVERALL PROGRAM 4-5 YEARS
o DESIGN BASIS RECONSTITUTION
'
EXPEDITE SCHEDULE
PRIORITY NUCLEAR OPERATIONS PROGRAM
'
BUDGET
,
o APPROXIMATELY $1.5 MILLION PER YEAR ,
-
1
!
- r
1
1
-
9
a
- , . - ~ . -,-,---------__--,,_,-y r--_, , ,,.-w,a-...m ~,..--,r.--.,-...y--, r.__y. m y,---.-.-w, , , -~, , , - , -- -,...r,.,_o-vr---%,, , - -
,
.
,. . -
.
.
!
CONCLUSION
o FPC NUCLEAR PHILOSOPHY HAS ALWAYS BEEN SENSITIVE TO THE
CONTROL OF PLANT CONFIGURATION
o FPC HAS EXPENDED CONSIDERABLE RESOURCES TO UPGRADE PROGRAM
o IDENTIFICATION OF PROBLEMS WAS NOT A SURPRISE
o PLAN FOR MAJOR REVIEW OF DESIGN BASIS IN PLACE BEFORE OSTI
o DESIGN BASIS REVIEW / RECONSTITUTION IS BEING EXPEDITED
-
