Letter Sequence Other |
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MONTHYEARML20247H2751989-07-21021 July 1989
Requests Addl Info Re Emergency Diesel Generator Upgrade Program for Plant by 890804.Items Discussed in Detail Listed,Including Components Requalified by Testing
Project stage: Other
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
Project stage: Other
1989-07-21
[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 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
ML20058Q2001990-07-31031 July 1990
Requests Supplemental Response Describing Util Corrective Actions & Date of Full Compliance,Per Insp Rept 50-302/89-18
ML20058N2901990-07-31031 July 1990
Advises That 900613 Rev 5 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable
ML20058L4241990-07-31031 July 1990
Forwards Request for Addl Info Re Spent Fuel Pool Rerack Amend.Response to Items Should Be Submitted by 900820
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
ML20055H5751990-07-10010 July 1990
Forwards Insp Rept 50-302/90-22 on 900612-16.Violations Noted But Not Cited
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
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
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
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
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
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
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
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
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
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
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
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September 25, 1989 f
" Docket No. 50-302 DISTRIBUTION (DoctitFilet ACRS(10)
HRC & LPDRs SSaba 8/D/20 PD22 Rdg File MSinkuie RII Mr. W. S. Wilgus SVarga 14/E/4 Vic2 President, Nuclear Operations Glainas 14/H/3-Florida Power Corporation HSilver ATTH: Manager, Nuclear Operations GWunder Licensing HBerkow P. O. Box 219-NA-21 OGC Crystal River, Florida 32629 EJordan MNBB-3302 BGrimes 9/A/2
Dear Mr. W11gus:
SUBJECT:
CRYSTAL RIVER UNIT 3 - PRE-0PERATIONAL TESTING OF THE UPGRADED EMERGENCY DIESEL GENERATORS (EDG) (TAC NO. 67801)
In Florida Power Corporation (FPC) letters dated April 27, August 11, and August 14, 1989 and in the nceting of August 31, 1989, information was provided on the EDS upgrade program to be implemented during Refuel 7. At the August 31, meeting, we stated that because of the significant design changes to be made on the EDG, we considered the upgraded type EDG as not being previously qualified.
Therefore, qualification and pre-operational testing would be necessary as specified in Regulatory Cuide (RG) 1.0 Rev.2. However, in consideration of the tests and analyses performed by the EDG Manufacturer, the type qualification tests (300 tests with no more than 3 failures) would not be required, provided that a successful pre-operational test program is successfully completed. Ve agreed to provide the staff position on what would constitute an acceptable test program._ That position is enclosed.
Please confirm that the test outlined in the enclosure will be performed prior to declaring the EDGs operable. Any questions on this position should be discussed with the undersigned.
Sincerely, Original signed by Harley Silver, Project Manager Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated f
See next page ccw/ enclosure:[g j pf LAiPDI~2 011-2 ,3 1CSB
/ I 2 kl DMil r HSilver:jd FRosafg/{'DHBerkow 09/ /89 09ggj89 09/n /89 09/gf/89 8910050249 890925 PDR ADOCK 05000302
to ._
hf ,
/orx .'e. 2 Mr. W. . S. -Wilgus ~ Crystal' River Unit No. 3 Nuclear g Florida Power Corporation. Generating' Plant cc: .
Mr.1X. H.'Stephens State Planning and Development
. General Counsel Clearinghouse
. . Florida Power Corporation. Office of Planning and Budget MAC'- ASD Executive Office of the Governor-P. O. Box 14042 .
The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301
~ Mr. - P. F. Mc' Ke'e, Director Chairman NuclearlPlant Operations - Board of County Commissioners Florida-Power Corporation Citrus County P. O. Box 219-NA-2C .
110 North Apopka Avenue w . Crystal River, Florida 32629 Inverness', Florida 32650 Mr._ Robert'B. Borsum Mr. Rolf C. Widell, Director i Babcock &.Wilcox ..
Nuclear Operations Site Support
. Nuclear Power Generation Division Florida Power Corporation
'1700 Rockville Pike, Suite 525 P.O. Box 219-NA-21 Rockville, Maryland 20852 Crystal River, Florida 32629 Senior. Resident. Inspector Mr. Gary L. Boldt
. Crystal River Unit: 3 Vice President, . Nuclear Production U.S. Nuclear Regulatory Commission Florida Power Corporation 15760 West Power'11ne Street' P. O. Box 219-SA-2C l , ' Crystal. River, Florida . 32629 Crystal River, Florida 32629
. Regional - Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900
~ Atlanta, Georgia 30323 Mr.. Jacob Daniel Nash Office' of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32399-0700 Administrator Department of Environmental Regulation
' Power Plant Siting Section
. State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304
y . ,e yl3 l 7' ..
1 '
14 :. ENCLOSURE 9/11/89 5 STAFF POSITION ON PRE-OPERATIONAL TESTING l OF THE UPGRADED EMERGENCY DIESEL GENERATORS AT
. CRYSTAL RIVER 3 The two Emergency Diesel Generator (EDG) at Crystal River-3 (CR-3) will be modified according to an upgra5 program detailed in Florida Power Corporation
.(FPC) letters dated April 27, 1989, August 11, 1989, and August 14, 1989, and in the meeting of August 31, 1989. The FPC letter of August 11, 1989, states that the upgraded ratings have been confirmed by the diesel manufacturer based on testing performed at his plant on a 6-cylinder engine of similar basic design (the CR-3 diesels are 12-cylinder) and supporting analysis.
The old and the upgraded ratings of the EDG are:
Old Ratings Upgraded Ratings 0 - 2750kW Continuous 0 - 2850kW 2751 - 3000kW 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> 2851 - 3000kW
200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> 3001 - 3250kW 3001 - 3300kW- 30 minutes 3251 - 3500kW It was also stated in this FPC letter that after the upgrade modification, which will be implemented during Refuel 7- (Spring 1990), the automatically connected EDG accident load will be within the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating, and that any subsequent manual loading that may be applied would not exceed the.200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> rating.
The staff considers the CR-3 upgraded EDGs as not having been previously qualified due to the significant design changes, and as such should meet the type qualification testing and site acceptance testing provisions respectively of Regulatory Guide (RG) 1.9 Rev. 2 and R.G.I.108.
With regard to type qualification, the staff concludes that this requirement has been met and no further " type qualification testing" is required provided the pre-operational (site acceptance) testing described below is successfully implemented.
This conclusion is based on consideration of the testing and analyses performed by the manufacturer cited above, and on the further confirmation of the capability
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2-f and reliability of the upgraded CR-3 EDGs which will be provided by successful
. completion of the following in-situ test program.
~
. Pre-Operational Test Program:
, 4 The following tests should be conducted in-situ on each tipgraded EDG. These tests should be. performed after completion of the testing required by FPC for acceptance of the upgrade modification. . Credit may be taken for any FPC acceptance test that is essentially identical to a test in the pre-operational test program.
1.' Start and Load-Run Test:
- a. Sta rt-Test: Demonstrate proper startup from ambient conditions and verify that the required design voltage and frequency is attained. For these tests, the diesel genera-tor can be slow started, be prelubricated, have prewarmed oil and water circulating, and should reach rated speed on a pre-specified schedule that is selected to minimize stress and wear.
- b. Load-Run Test: Demonstrate full-plant emergency load carrying capability of not less than 2800kW until temperature equilibrium has been attained, but not less than I hour. This test could be accomplished by synchronizing the generator with offsite power.
The loading and unloading of a diesel generator during this test should be gradual and based on a prescribed schedule that is selected to minimize stress and wear on the diesel generator.
- 2. Fast-Start Test: Demonstrate tnat each diesel generator unit starts from ambient conditions and verify that the diesel generator reaches stable rated voltage and frequency within the limits and time, as de-fined in the plant technical specifications.
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- 3. Conbined Safety Injection Actuation Signal (SIAS) f and Loss of Offsite Power (LOOP) Test:
Demonstrate by simulating a LOOP in conjunction with SIAS that (1) the emergency buses are deenergized and loads are shed from the emergency buses and (2) the diesel generator starts on the auto-start '
signal from its standby conditions, attains the required voltage a.d frequency within the limits and time as per the plant technical !
specifications, energizes auto-connected loads through the load sequencer, and operates while loaded with the auto-connected loads 4 for greater than or equal to 5 minutes.
- 4. Single-Load Rejection Test: Demonstrate the diesel generator's capability to reject a load equal to its largest single load (600kW) and verify that the voltage and frequency requirements are met.
- 5. Full-Load Rejection Test: Demonstrate the diesel generator's capability to reject a load equal to its expected maximum design .
load (approximately 3100kW), and verify that the voltage require-ments are met and that the unit will not trip on overspeed.
- 6. Endurance and Margin Test: Demonstrate full-load carrying capability for an interval of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, of which 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> should be at a load of 3135kW and 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at a load of 2800kW. Verify that voltage and frequency requirements are
~
maintained.
- 7. Hot Restart Test: Demonstrate hot restart functional capability at full-load temperature conditions by verifying that the diesel generator starts on a manual or auto-start signal, attains the required voltage and frequency within the limits and time as per the plant technical specifications, and operates for longer than 5 minutes.
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- 8. ' Reliability Tests: Demonstrate through a mininum of 30 valid start '-
and-load; tests per item 1 above without failure on each diesel gen--
erator unit that an' acceptable level of reliability has been ' achieved
. to place the upgraded EDG into an operational category.
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