Forwards marked-up Listing of Regulatory Info Tracking Sys for Implementation of Generic Items,Per Request.Completed marked-up Listing,W/Status of All Actions Identified,Will Be Provided by 860715ML17342A573 |
Person / Time |
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Site: |
Turkey Point ![NextEra Energy icon.png](/w/images/9/9b/NextEra_Energy_icon.png) |
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Issue date: |
06/06/1986 |
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From: |
Woody C FLORIDA POWER & LIGHT CO. |
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To: |
Mcdonald D Office of Nuclear Reactor Regulation |
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References |
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TASK-***, TASK-OR, TASK-TM GL-82-16, GL-83-43, GL-84-15, IEB-80-04, IEB-80-4, L-86-240, NUDOCS 8606120406 |
Download: ML17342A573 (24) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML20212M1601999-09-28028 September 1999 Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) ML17354B2061998-12-0909 December 1998 Informs That Request for Exemption Specified in Section II.B.3 Will Not Be Needed Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg ML17354B1981998-11-25025 November 1998 Forwards Scope & Objective for 1999 Plant Annual Emergency Preparedness Exercise.Objectives Developed in Conjunction with State & Local Govts.Exercise Scheduled for 990210 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML17348A5661990-09-14014 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. ML17348A5461990-09-0707 September 1990 Forwards 1990 Inservice Insp Refueling Outage Summary Rept of NDE Activities 900206-0404 First Refueling Outage Second Period Second Insp Interval. ML17348A5501990-09-0707 September 1990 Forwards Jul 1990 Integrated Schedule Regulatory Rept for Facilities ML17348A5521990-09-0606 September 1990 Forwards Matrix of Changes to Emergency Power Sys That Affect Revised Tech Specs Issued on 900828.Matrix Sent for Info & to Assist in NRC Review of No Significant Hazards Rept for Revised Tech Specs ML17348A5431990-08-31031 August 1990 Forwards Objectives for 901108 Emergency Plan Exercise. Exercise Will Involve Participation by Local Emergency Response Agencies & State Emergency Response Personnel & Will Not Be Evaluated by FEMA ML17348A5361990-08-27027 August 1990 Forwards Turkey Point Units 3 & 4 Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Health Physics Procedure HP-48, Process Control Program for Dewatering Radwaste Liners. ML17348A5171990-08-24024 August 1990 Forwards Ref Matl in Preparation for Operator License Exams Scheduled for Wk of 901029,per NRC 900628 Request ML17348A5041990-08-17017 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990 ML17348A5051990-08-15015 August 1990 Forwards Monthly Operating Repts for Jul 1990 for Turkey Point Units 3 & 4 & Revise Rept for June 1990 for Unit 3 ML20059B0111990-08-14014 August 1990 Requests That Encl Intervenor Motion for Extension of Time to Appeal to Docketing & Svcs Branch Re Tech Spec Replacement Hearing Be Provided.Motion Inadvertently Omitted in Svc of Request on 900813 ML17348A4971990-08-10010 August 1990 Responds to Violations Noted in Insp Repts 50-250/90-18 & 50-251/90-18.Corrective Actions:Unit Stabilized in Mode 3, Operating Surveillance Procedures 3/4-OSP-089 Revised & Event Response Team Formed ML17348A4701990-07-27027 July 1990 Forwards Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per Unsatisfactory Performance Testing L-90-282, Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790)1990-07-25025 July 1990 Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790) ML17348A4281990-07-25025 July 1990 Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b) ML17348A4691990-07-23023 July 1990 Forwards Addl Info on Emergency Power Sys Enhancement Project Re Load Sequencer,Programmable Logic Controllers & Implementation of Sys in Plant,Per NRC 900705 Request ML17348A4191990-07-20020 July 1990 Advises That Comments on NRC Safety Evaluation Re Implementation of Station Blackout Rule Will Be Provided by 900921 ML17348A4201990-07-20020 July 1990 Forwards Revised No Significant Hazards Determination for Proposed Tech Specs 1.17 & 3.0.5 & Bases,Per 890605 Ltr ML17348A4141990-07-20020 July 1990 Responds to Violations Noted in Insp Repts 50-250/90-14 & 50-251/90-14.Corrective Actions:Breakers Closed,Returning Monitoring Sys to Operable Level & Briefings Held to Explain Rvlms Sys Theory to Operations Control Room Personnel ML17348A4171990-07-19019 July 1990 Forwards May 1990 Integrated Schedule Regulatory Rept for Plant ML17348A4121990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML17348A4251990-07-17017 July 1990 Withdraws 900207 & 0424 Proposed Changes to Tech Specs Re Util Nuclear Review Board Composition IR 05000250/19900131990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML20055G8641990-07-16016 July 1990 Informs ASLB That Petitioners Ref to Several Telephone Contacts Between J Butler & M Gutman,Of ATI Career Training Inst Is Inadvertent Misstatement & Should Be Changed to Telephone Contact. W/Certificate of Svc ML17348A4161990-07-16016 July 1990 Responds to Commitment Re Reverse Testing of Containment Isolation Valves Per Insp Repts 50-250/90-13 & 50-251/90-13. Corrective Action Plan Addresses Penetrations 16 & 53 for Unit 3 Only & Penetrations 11,47,54A & 54B for Both Units ML17348A4151990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML17348A4041990-07-12012 July 1990 Forwards Addl Info Re Responses to NRC Questions on Piping Codes Used for Emergency Power Sys Enhancement Project ML17348A3921990-07-12012 July 1990 Summarizes Facility Performance Since Last SALP Evaluation Period Which Ended 890731.Util Pursued Aggressive self- Assessment Program,Including Significant Internal or Outside Assessments in Areas of Operator Performance & EOPs L-90-261, Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld1990-07-11011 July 1990 Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld L-90-259, Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3))1990-07-11011 July 1990 Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3)) ML17348A4321990-07-11011 July 1990 Forwards Rev 8 to Updated FSAR for Turkey Point Units 3 & 4. Rev Includes Activities Completed Between 890123 & 900122. Rept of Changes for Jul 1989 Through June 1990 Will Be Provided by 900901 ML17348A3941990-07-0909 July 1990 Forwards Requested Addl Info Re Emergency Power Sys Enhancement Project.Specific Detailed Changes Will Be Made to Procedures to Address Mods Affecting Equipment Relied Upon for Safe Shutdown ML17348A3881990-07-0505 July 1990 Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs ML17348A4311990-07-0505 July 1990 Documents Written & Verbal Request of Region II Personnel for Temporary Waiver of Compliance of Tech Spec 3.4.2.b.1 Re Allowable Out of Svc Time for One Emergency Containment Cooler from 24 H to 72 Hr W/Addl Reasons ML17348A3851990-07-0303 July 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-250/90-08 & 50-251/90-08.Corrective Actions:Training Dept Increased Emphasis on Radiological Postings in Radiation Worker Training ML17348A3711990-07-0303 July 1990 Responds to NRC 900524 Request for Addl Info on Emergency Power Sys Enhancement Project ML17348A3671990-07-0303 July 1990 Confirms Util Intentions Not to Operate Beyond Refueling Outage That Represents Last Outage Re NRC Bulletin 89-001 ML17348A3841990-06-29029 June 1990 Forwards LER 90-11 on 900609 Re hi-hi Steam Generator Water Level Turbine Trip & Subsequent Reactor Trip Due to Failure of Switch in Feedwater Valve Controller Hand/Auto Station. W/O Encl ML17348A3601990-06-29029 June 1990 Responds to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. Test Procedures Developed & Under Mgt Review Reflecting Revised Inservice Testing Program ML17348A3621990-06-28028 June 1990 Notifies That Senior Operator License SOP-20177-2 Will Be Terminated,Effective 900731 ML17348A3651990-06-28028 June 1990 Advises That Completion of safety-related motor-operated Valve Testing & Surveillance Will Be Completed by June 1990, Per Generic Ltr 89-10 Requirements ML17348A3591990-06-27027 June 1990 Responds to Violations Noted in Insp Repts 50-250/90-09 & 50-251/90-09.Corrective Actions:Specialist Counselled on Importance of Stopping Procedure When Steps Conflict W/ Condition of Plant & Procedure Use Guidelines Reviewed ML17348A3641990-06-27027 June 1990 Responds to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions. ML17348A3861990-06-27027 June 1990 Advises That New Date for Submittal of Response to Insp Repts 50-250/90-09 & 50-251/90-09 Is 900702 ML17348A3551990-06-21021 June 1990 Responds to NRC Bulletin 88-010, Nonconforming Molded Case Circuit Breakers. Five Untraceable Circuit Breakers Installed in Unit 3 safety-related Sys.All Five Breakers Replaced W/Traceable Breakers ML20055D9201990-06-20020 June 1990 Advises That Sp Frantz Will Represent Licensee in Argument Scheduled for 900710.Certificate of Svc Encl ML17348A3181990-06-19019 June 1990 Forwards Final Rept of Inservice Insp NDE of Unisolable Piping Sys & Components for Potential Thermal Stress Effects for Turkey Point Nuclear Power Plant, Per NRC Bulletin 88-008 ML17348A2981990-06-12012 June 1990 Forwards Rev 16 to Topical QA Rept. ML17348A2871990-06-0808 June 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Model S350W Swing Check Valves or Valves of Similar Design. Bolt Replacement Performed ML17348A2861990-06-0808 June 1990 Advises That Info Re Operating History of Select Fuel Assemblies Sent to ORNL Between 900419 & 26,per 900510 Request ML17348A2781990-06-0404 June 1990 Forwards Emergency Power Sys Enhancement Project Repts, Reflecting Current Design Info 1990-09-07
[Table view] |
Text
REGULATORY XNFOR>>ATION DISTR 1BUTI ON -SYSTE>> (R IDS>
ACCESSION NBR: 8606120406 DOC. DATE: 86/06/06 NOTAR X ZED: NO DOCKET ¹ FACIL: 50-,250 Turkey Point Planti Unit 3i Flov'ida Potoer and Light C 05000250 50-251 Turkey Point Planti Unit 4i Flori da Potoer and Light C 05000251 AUTH. NA>>E AUTHOR AFFILIATION WOODY C. O. Flov ida Power 8c Light Co.
RECIP. NA>>E REC IP I ENT AFF I L I ATION
>>CDONALD, D. Q. PWR Pv object Div'ectorate 2
SUBJECT:
Forwards marked-up listing of regulatov g inFo tvacking sos For implementation oF generic items~ per request. Completed mav ked-up listing> e/status of all actions identifiedi will be pv ovided bg 860715.
DI BTRIBUTION CODE: A001D COP XES RECEIVED: LTR ENCL SI ZE:
TITLE: OR, Submittal: Qeneral Distribution NOTES:
I REC P IENT COPXEB RECIPIENT COPIES ID CODE/NA>>E LTTR ENCL ID CODE/NA>>E LTTR ENCL PNR-A EB 1 1 PWR-A EICSB 2 2
'NR-A FOB 1 PWR-A PD2 LA 0 PWR-A PD2 PD 01 5 5 >>c DONALD> D 1 PNR-A PSB 1 PNR-A RSB 1 INTERNAL: AD>>/LF>>B 1 0 ELD/HDB4 1 0 NRR/DHFT/TSCB 1 NRR/GRAS 0 04 1 RQN2 1 EXTERNAL 24X 1 1 EQhQ BRUSKEi B 1 1 LPDR 03 1 NRC PDR 02 1 1.
NBXC 05 1 1 TOTAL NU>>BER OF COPIES REQUIRED: LTTR 24 ENCL 20
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P. X 14000, JUNO BEACH, FL 33408 i~Vifii FLORIDA POWER & LIGHT COMPANY EI 1988 L-86-240 Office of Nuclear Reactor Regulation Attention: Mr. D. G. McDonald, Project Manager PWR Project Directorate f72 Division of PWR Licensing -'
U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. McDonald:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-25 I Im lementation of Generic Items Attached is the marked up generic item listing you requested. As discussed with you, a status was not provided where additional information is required to define the specific licensing action or where additional NRC action is pending following the FPL submittal.
Your request requires a careful review of all correspondence in our licensing files to determine the status of each generic item, and completion or projected completion dates. This is not a minor effort and could not be completed in the time you requested (approximately one month).
Accordingly, we consider the markup provided you to be a working document until our review can be completed. We will submit a completed marked up listing, with the status of all actions identified, to you by July I5, l986. Any changes to the attached listing will be noted in that final submittal. In the meantime, we intend to work with you to resolve any questions regarding the status of the open items.
If you have any questions, please call us.
Very truly yours, C.O.Wo d Group VI e President Nuclear Energy COW/TCG/gp (0D Attachment Sb0612040b SbObO PDR ADQCK 05000250, P PDg TCG5/006/ I PEOPLE... SERVING PEOPLE
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'-1 2087 31-001 REGULATORY INFORMATION TRACKING SYSTEN PAGE NO.s FACILITY IMPLEMENTATION 50!'3/31/8s ACILITYs TURKEY POINT 3 LANT LOCATIONs 25 NI S OF NIANIp FLA LICENSED POWERs 2200 NWT PROJECT NANAGERs D. HCDONALD iOCKET NUNBERs 050-00250 DESIGN POWERs 0693 HWE BRANCH CHIEF: L. RUBENSTEIN RCH/ENGINEERs BECH NSSS VENDORs WEST LIC. ASSISTANTs . VACANT E INSPECTORs T. PEEBLES LIC ACT LICENSEE
~OKEIE QIh3MU 108326 A-01 10 CFR 50.55 A(G) ISI 04/26/83C K 25'mple I Cgm~lel l(gS Q~( l ss3)'I'7
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'07412 A-02 A-03 APPENDIX ALARA SECURITY REVIEWS-NODIFIED ANENDNENT PLANS 04/23/84C 02/27/79C ~pie@ 1'I ~~ 44(5
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.08779 A-04 APPENDIX J - CONTAINNENT LEAK TESTING 11/04/81C C ~le~ Sl
=08790 A-06 RESPIRATORY PROTECTION SYSTEM 02/'15/79C C~tl~a 1 r 0~4 4S[gS 11373 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 02/27/80C I1 0392 A-1 0 CONTINGENCY PLANNING 11/28/80C Cov ply+ SO Q~g g((~~
10396 A-11 GUARD TRAINING PLANS 09/04/81C 04/12/82C
~Pie M 5S 5~/ g2J@g, AK. h(ko s10394 A-12 VITAL AREA ANALYSIS l47084 A-16 QUALIFICATIONS OF EXAMINATIONS INSPECTIONS TESTING 1 1/02/81 C Co Pl+ f Sl &i 6i -Oi l51 363 A-17 INSTRUHENTATION TO FOLLOW THE COURSE OF AN ACCIDEN 01/31/86 c~-~4. 5(sw 50.73 (GL 83-43) 01/31/86 ggC Gt.he Qv ds 155752 A-18 TECH SPECS AFFECTED BY 50.72 AND g A-20 50.62 OPERATING REACTOR REVIEWS 07/31/87 gK lkKon. ~ d~g l59153 10 CFR
!59992 i06614 A-21 B-02 10 CFR 50.61 i FIRE PROTECTION PRESSURIZED THERNAL SHOCK RULE 01/30/87 03/21/79C NP( O(tm>>
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'.08405 B-03 PWR NODERATOR DILUTION 02/21/79C 106717 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 03/1 4/80C 107434 B-07 STEAN GENERATOR FEEDWATER FLOW INSTABILITY 02/04/80C
)07963 B-11 FLOOD OF EQUIPHENT IMPORTANT TO SAFETY 09/04/79C 11 0404 B-13 FUEL ROD BOW 01/31/80C I
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-1208731-001 REGULATORY INFORMATION TRACKING SYSTEM PAGE NO.i 506 FACILITY IMPLEMENTATION 03/31/86
)RKEY POINT 3 (CONTINUATION)
MERCY LIC ACT LICENSEE R(5KKK 28Zf.
08796 B-14 CEA GUIDE TUBE HEAR 07/07/80C Cow )le.k.
12152 B-16 EMERGENCY PLANNING AND REVISIONS 04/01/81C 78786 B-17 TECH SPEC SUR)EILLANCE'FOR HYDRAULIC SNUBBERS 05/1 4/81 C Ss O.~k 'i>[rro 10276 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIPRATION 01/28/81 C a ~gism e ~
,I0340 B-21 LOSS OF 125-V DC BUS VOLTAGE WITH LOSS OF ANNUNCIA 02/28/82C
- ) 8784 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 10/14/83C c,i( <
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I0057 B-23 DEGRADED GRID VOLTAGE 08/1 4/84C O.wctu Q le</~
12564 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL POH 03/30/83C 10202 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL PON 12/08/80C ~le.4.
I0237 B-26 INADVERTANT SAFETY INJECTION DURING COOLDOHN 12/28/79C Co~qle 4 l'l 77126 B-30 STEAM GENERATOR REPLACEMENT PROGRAM 01/29/79C bv tie.+
07437 B"32 BLOCKED SI SIGNAL DURING COOLDOHN 04/01/82C Ceo p~
49415 08686 B-32 B-39 BLOCKED SI SIGNAL PHR PRESSURE DURING COOLDOHN TEMPERATURE LIMIT TECH SPECS 04/13/84C 01/29/81C C~~ A( $ 4 9 we,& (oz/q (p 48552 B-41 'IRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 03/27/84C Pop~ q @r.
11081 B-41 FIRE PROTECTION FINAL TECH SPECS (INCLUDES SER S 04/26/81C r r~y&0 g(8r Mi~cg 43849 43807'-41 B-41 FIRE PROTECTION FINAL TECH SPECS (INCLUDES SER FIRE PROTECTION FINAL TECH SPECS (INCLUDES SER S
S 04/16/84C 05/10/82C P g~q f4jec 4q S(ar
'rl86 S,<MAL 5~4~ ~
13124 B-42 TMI FOLLOW UP - ALL PLANTS 07/07/80C 11716 B-42 TMI FOLLOH UP ALL PLANTS 04/0'I/8'IC 11780 B-43 PHR FEEDHATER LINE CRACKS 02/22/80C 43156 PHR FEEDHATER LINE CRACKS 05/25/82C 30390 LESSONS LEARNED IMPLEMENTATION 04/07/80C I
'.-1208731-001 REGULATORY I NFORHATION TRACKING SYSTEH PAGE NO. > 507 FACILITY IMPLEMENTATION 03/31/86
'URKEY POINT 3 (CONTINUATION)
LIC ACT LICENSEE
~<L 55LR MKLEIE ~~U J+7g
'30391 B"I4 LESSONS LEARNED IMPLEMENTATION 04/07/SOC t30392 LESSONS LEARNED IHPLEHENTATION '04/07/80C I30393 B-46 LESSONS LEAR/ED IMPLEMENTATION 0 II/07/8 0C 04/07/SOC 3038'-II%
30382 LESSONS LEARNED IMPLEMENTATION 30383 LESSONS LEARNED IMPLEMENTATION 04/07/SOC LESSONS LEARNED IHPLEHENTATION Oci/07/SOC 30385 B-01 LESSONS LEARNED IMPLEMENTATION OI4/07/SOC 30386 B-I1 LESSONS LEARNED IMPLEMENTATION 04/07/SOC 30387 B-I4 LESSONS LEARNED IMPLEMENTATION 04/07/SOC 30388 B-III LESSONS LEARNED IMPLEMENTATION OII/07/SOC 30389 B-I6 LESSONS LEARNED IMPLEMENTATION 0%/07/SOC 12940 B-05 NASH 1400 EVENT Vp "PRIMARY COOLANT SYSTEM PRESSUR OII/20/81C 1257% B-A6 ANALYSIS OF TURBINE DISC CRACKS 08/21/81 C Co~(le& &(
12690 B-67 ECCSJ CLAD SHELLING AND RUPTURE 09/1 2/SOC CO~ 4.4. so 12960 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 12/17/82C 13036 B-49 PHR CONTROL ROD MISALIGNMENT 05/06/81C 11881 B-52 REVIEH OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 10/21/SOC II2322 B-53 LESSONS LEARNED CATEGORY B (ITEMS) 10/31/80C
%2103 B-57 DHR CAPABILITY 07/30/82C 42869 B-59 MASONRY HALL. DESIGN 01/OII/85C CI2070 B-60 ENVIRONMENTAL QUALIFICATION 10/25/SIIC III2712 B-61 'OSS OF NON CLASS IE I&C POHER 07/28/82C l6 2784 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 05/12/82C
1208731-001 REGULATORY INFORMATION TRACKING SYSTEM PAGE NO. ~ 508 FACILITY IMPLEMENTATION 03/31/86 URKEY POINT 3 (CONTINUATION)
LIC ACT LICENSEE
~A~0 CI~ Jg QXh~U 25IK 43913 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 04/26/82C 471 54 B-66 NATURAL CIRCULATION COOLDOHN 07/28/83C 46866 B-69 IEB 80"4 MAI+TEAM LINE BREAK HITH CONTINUED FEEDH 10/20/82C 46640 B"70 FATIGUE TRANSIENT LIMIT TS 05/25/82C 49766 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 08/27/84C Co~llle 4 Io(84. G~ Io(Ioa 49611 B-73 PLANS FOR PREVENTING EXCEEDING PTS SCREENING CRITE 11/17/83C Ce~) Ic. 4 Z(S> NIIC. K' 52810 B-76 ITEM 1.1 POST TRIP REVIEH2 PROGRAM DESCRIPTION & 06/25/85C ~(e.M t (eS 52891 B-77 ITEM 2.1 EQUIPMENT CLASSIFICATION & VENDOR INTER 09/30/86 g~ Od ce g4}~
3.1.2 4c. Octo ~wg 52972 53053 B-78 B-79 ITEMS ITEM 3.1.1 3.1.3 -
& -POST MAINTENANCE TEST PROCEDU POST MAINTENANCE TESTING CHANGES TO 01/15/86 11/14/85C 'u pl~M It/gQ 53107 B-80 ITEM 4.1 REACTOR TRIP SYSTEM RELIABILITY VENDO 01/15/86 Qpw pe+
53160 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 04/29/85C Ce~ te-4 s(ss 53202 B-82 ITEM 4.3 AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 12/03/84C co~le< ~(ss 54576 B"83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 10/17/84C Cev yt~ IZ(M- 5~6/ Il%o4 (acr gVmS M) 53643 B"85 SALEM ATHS 1.2 DATA CAPABILITY 11/27/85C 53726 B-86 SALEM ATHS 2.2 S"R COMPONENTS 01/01/87 Ngc (4k~
53809 B"87 SALEM ATHS'3.2.1 & 3.2.2 S-R COMPONENTS 12/31/86 ITIC. Ouho 53892 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 1 1/1 4/85C Gc~((~ tl(SS 53947 B-89 SALEM ATHS 4.2.3.& 4.2.4 LIFE COMPONENTS 11/28/86 ggg C2+~ Qvdl Q
55384 54119 B"90 B"92 SALEM ATHS 4.3 H AND B&H T.S.
SALEM ATHS 4 ~ 5 ~ 1 DIVERSE TRIP FEATURES 02/28/86 11/01/86
@co f(.~ S(eI. aW~4, g<z ad ~f4a~
54036 B-93 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 04/30/87 9k'. Gc4'~
08255 C"01 PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREME 10/30/81C I
-1208731-001 REGULATORY INFORMATION TRACKING SYSTEM PAGE NO.~, 50'.
FACILITY IMPLEMENTATION 03/31/8~
URKEY POINT 3 (CONTINUATION)
LIC ACT LICENSEE KJHL HHZlEIK 08651 C-03 QUALIFICATIONS OF RADIATION PROTECTION MANAGER 02r15r79C ~le~ l9 R~f 45 W 03963 C-04 FILTER TECH SPECS 03/23/82C Ce~le.& 6~
08793 C-06 PUMP SUPPORT-I,AMELLAR TEARING 12/14/82C C ~l < s(sW 5 ~leW 1'I t
08798 C-07 FUEL HANDLING., ACCIDENT INSIDE CONTAINMENT 05/30/79C 08088 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 11/01/83C Ce~pte& Ss 13041 C-13 LOSS OF OFFSITE POHER 05/06/80C 43649 C-14 AUXILIARY FEEDHATER SEISMIC QUALIFICATION 08/25/83C C-15 CONTROL OF HEAVY LOADS PHASE II (FOLLOHUP 06/28/85C Co~I~
52281 58098 C-16 UTILITY RESPONSES OF MPA TO STAFF RECOMMENDATIONS CONCERN 01r22r86C Cs) ~\~-
M 78
<($ 4 07878 D-02 ECCS ZIRC.CLAD MODEL ERROR"COMPLIANCE HITH 10 CFR- 09/22/78C Co~()~
07859'-03 PRESSURIZER HEATUP RATE ERROR 10/25/78C ~s 0.~4 4o/Sz 08782 D-10 ASYMMETRIC LOCA LOADS 02/06/84C 10002 D-11 FISSION GAS RELEASE 02/22/80C 08800 D-14 REACTOR VESSEL HELD HIRE DEFICIENCY 02/13/79C 12280 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 02/02/84C 43013 D-17 DEFINITION OF OPERABLE 05/12/81C ~w pie h Qt 5.~Q 4b]sg 55915 D-19 DIESEL GENERATOR RELIABILITYTECH SPECS (GL 84-15) 03/31/86 (4~+ g )[san VMMlg ~
44062 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 01/08/82C Ccn~4.~ 6W 44133 F-02 I.A.1.3 SHIFT MANNING 06/30/83C 44204 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 10/25/82C 44275 44345 F-04 F-05 I.C.1.2/3 A EMERGENCY OPERATING PROCEDURES I.C.1.2/3.B PROCEDURES GENERATION PACKAGES GENERIC (NUREG 06/07/84C 11/30/86 QRt'- 5 Sot) m<h Ja~ P~~
S(S 47259 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 10/20/81C
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'.-1 208731-001 REGULATORY INFORMATION TRACKING SYSTEM PAGE NO.> 51 FAC I L ITY'MP L EMENTATI ON 03/31/8 URKEY POINT 3 (CONTINUATION)
LIC ACT LICENSEE HHZlfIK ~~U l47 331 l51213 F-07 F-08 I.C.6 I.D.1.1 CORRECT PERFORMANCE OF OPERATING ACTIVITI 10/20/81C 01/16/84C ~(
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~+~ ~ AEOe 151293 F-09 I. D.2 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA SAFETY PARAMETER DISPLAY SYSTEM 03/04/85C 4 ~'l~ iZ.(e<
i l44413 F-10 II.B.1 RCS HIGH POINT VENTS 09/02/83C 0 p4A-e I47982 F-11 II.B.2 PLANT SHIELDING 06/30/83C 4.4 83 5s'c)~)
I44483 F-12 II.B.3 POST ACCIDENT SAMPLING 11/08/83C S(e 4-l44554 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 10/25/82C (~~ eZ l44626 F-14 Il.D.1 RV AND SV T1tAXRBtG V~wrMQ- 09/30/86 I42324 F-1 5 I I . E. 1 . 1 AFW SYSTEM EVALUATION 11/04/82C l44697 F-16 ZI.E.1.2.1 AFW SYSTEM INITIATION 09/15/82C l44736 F-17 II.E.1.2.2 AFW SYSTEM FLOW INDICATION 09/15/82C I44822 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 03/25/82C l44893 F-19 Il.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 11/1 2/82C l44964 F-20 II . F. 1 .1 NOBLE GAS MONITOR 09/30/81C 145035 F-21 ZI.F.1.2. IODZNE/PARTICULATE SAMPLING 09/30/81 C 1451 06 F-22 Il.F.1 .3 CONTAINMENT HIGH RANGE MONITOR 02/08/82C l47643 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 05/02/83C ~wq4 Q g l47714 F-24 ZI.F.1.5 CONTAINMENT WATER LEVEL INSTRUMENT 05/02/83C Go~yf+4 l47785 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 05/02/83C Co~p(t + gg l45176 F-26 II.F.2 I I.K.2. 13 INSTRUMENTS FOR DETECTION ON INADEQUATE 01/26/85C Preying 4
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i&I l46910 l47824 F-30 F-33 ZI.K.2.17 THERMAL-MECHANICAL REPORT POTENTIAL FOR VOIDING IN RCS 06/06/84C 01/06/84C t'we Co~p4 C i(aa 145254 F-36 II .K. 3 ~ 1 AUTO PORV ISOLATION 09/16/83C Co~l~k 63 l
'.-1 208731-001 REGULATORY INFORMATION TRACKING SYST EM PAGE NO, i 51 FACILITY IMPLEMENTATION 03/3)/8i URKEY POINT 3 (CONTINUATION)
LIC ACT LICENSEE
~OLDIE ~~US l45300 F-37 II.K.3.2 . REPORT ON PORV FAILURES 09/16/83C Co~luk-l45386 F-38 'II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 06/24/82C Y45417 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C Q( Q(g 0 ~4.M II.K.3.9 t
l45466 F-40 PID CONTROLLER 08/20/81C l45496 l45526 l45673 F"41 F-42 F-47 II.K.3.1 0 II.K.3.12 I I.K. 3. 17 ANTICIPATORY TRIP MODIFICATIONS ANTICIPATORY TRIP ECCS OUTAGES ON TURBINE TRIP 08/20/81C 08/20/81C 08/26/83C
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.48437 F-53 II.K.3.25 POWER ON PUMP SEALS 06/24/82C ez F"57 II.K.3.30 05r29r85C 5~ ~,,>>,Z ~N~a~~
l45869 SB LOCA METHODS Qg4
'48210 F-58 II.K.3.31 COMPLIANCE WITH 10 CFR 50.46 - 12/31/86 l 'gg( Ik+o<<kv keg l45988 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 06/30/86 NG O.d(o P l46060 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 06/30/86 HK. Grk~ A~
III.A.1.2 gQ Rdl. Q l46132 l46204 F-65 F-66 II I .A. . 2 1
EMERGENCY OPERATIONS NUCLEAR DATA LINK FACILITY 06/30/86 07/30/82C Cp~4 4~4 4 5>
~ 83 146276 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/13/83C l46347 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 06/30/86 146418 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 02/09/82C p~
l46487 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 11/25/83C P,~P izlss w Pl~<<~h ~~~4
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156177 YI9678 F-71 G-01 I.D.1.2 DETAILED CONTROL REACTOR COOLANT PUMP TRIP ROOM REVIEW (FOLLOWUP TO (D660 II.K.3.5) 05r21/85C 04/20/86 Co Ng.( adc I ~
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591514 A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS 07/31/87 0t'C 5&>
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'-1208731-001 REGULATORY INFORNATION TRACKING SYSTEH PAGE NO. g. '513 FACILITY INPLEHENTATION 03/31/86 URKEY POINT 4 (CONTINUATION)
LIC ACT LICENSEE HHZlfIK '~U l08797 B-14 CEA GUIDE TUBE NEAR 07/07/80C i 2153 08787 110277 B-16 B-17 B-20 EMERGENCY PLANNING AND REVISIONS TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS CONTAINHENT LEAKAGE DUE TO SEAL DETERIORATION 04/01/81 01/28/81 C
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!42565 B-24,VENTING AND PURGING CONTAINHENTS HHILE AT FULL PON 03/30/83C
!10201 B-24 VENTING AND PURGING CONTAINNENTS HHILE AT FULL POH 12/08/80C Ce~t t 4 Zo l1 0238 B-26 INADVERTANT SAFETY INJECTION DURING COOLDONN 12/28/79C Gov (hi~ 19 i11990 B-30 STEAN GENERATOR REPLACENENT PROGRAN 06/23/81C Co )(4 sw 82 i08809 l08792 B-30 B-32 STEAN GENERATOR REPLACENENT PROGRAH BLOCKED SI SIGNAL DURING COOLDOHN 06/29/79C 04/01/82C Co~ d(s4 ~+ !ogpu 149416 B-32 BLOCKED SI SIGNAL DURING COOLDOHN 04/13/84C I08687 B-39 PHR PRESSURE TEl!iPERATURE LIHIT TECH SPECS 01/26/81C l43808 I48 553 B-41 B-41 FIRE PROTECTION FINAL TECH SPECS (INCLUDES SER FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S
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l11717 B-42 TNI FOLLOH UP ALL PLANTS 04/01/81 C l13125 B-42 THI FOLLOH UP ALL PLANTS 07/07/80C 143157 B-43 PHR FEEDWATER LINE CRACKS 05/25/82C 111781 PHR FEEDHATER LINE CRACKS 02/22/80C I
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LIC ACT LICENSEE
~OlPLJUf ~X% 25IK l30394 LESSONS LEARNED IHPLEHENTATION 04/07/80C
'30395 B-44 LESSONS LEARNED IHPL EHENTATION 04/07/80C l30 396 LESSONS LEARNED IHPLEHENTATION 04/07/80C I30397 LESSONS LEARNED IHPLEHENTATION 04/07/80C l30398 LESSONS LEARNED IHPLEHENTATION 04/07/80C
'30399 B-44 LESSONS LEARNED IHPLEHENTATION 04/07/80C l30400 B-44 LESSONS LEARNED IHPLEHENTATION 04/07/80C l30401 B-44 LESSONS LEARNED IHPLEHENTATION 04/07/80C l30402 B-44 LESSONS LEARNED IHP L EHENTATION 04/07/80C I30403 B-44 LESSONS LEARNED IHPLEHENTATION 04/07/80C
!30404 B-44 LESSONS LEARNED IHPLEHENTATION 04/07/80C l30405 B-44 LESSONS LEARNED IHPLEHENTATION 04/07/80C 30406 B-44 LESSONS LEARNED IHPLEHENTATION 04/07/80C I30407 B-44 LESSONS LEARNED IHPLEHENTATION 04/07/80C l12941 B-45 HASH 1400 EVENT'> "PRIHARY COOLANT SYSTEH PRESSUR 04/20/81C l12575 l12691 l1 2965
'" B-46 47 ANALYSIS OF TURBINE DISC CRACKS ECCSj CLAD SHELLING AND RUPTURE ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 08/21/81 09/12/80C 12/17/82C C b +K st sp ~,
113037 B-49 PHR CONTROL ROD HISALIGNHENT 05/06/81C 5p~~ &i 0.~< 4siSq l1 1882 B-52 REVIEW OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 10r21r80C o 42323 B-53 LESSONS LEARNED CATEGORY B (ITEHS) 10/3'1/80C 143424 B-54 LESSONS CATEGORY A TECH SPEC 07/06/81C l42104 B-57 'HR CAPABILITY 07/30/82C 1
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208731-001'URKEY FACILITY IMPLEMENTATION 51'3/31'/&
i POINT 4 (CONTINUATION)
LIC ACT LICENSEE QK EL EKED% ~02lEXE ~EM 25TE
%2870 B-59 MASONRY HALL DESIGN 01/00/85C Siew N2CI71 B-60 ENVIRONMENTAL QUALIFICATION 10/25/86C N2713 $ -61 . LOSS'F NON CLASS IE I&C POHER 07/28/82C 162785 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 05/12/82C i%3914 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 06/26/82C N7155 B-66 NATURAL CIRCULATION COOLDOHN 07/28/83C 107550 B-67 THERMAL SHOCK 02/09/83C 1%7028 B-67 THERMAL SHOCK 01/21/82C 116867 B-69 IEB 80"4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 1 0/20/82C YI66C01 B-70 FATIGUE TRANSIENT LIMIT TS 05/25/82C N9767 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 10/01/84C Co~4.~ lo (64- ll~~ iG4[(80 1CI9612 B-73 PLANS FOR PREVENTING EXCEEDING PTS SCREENING CRITE 11/17/8 3C Jaw~ 2Lcs gtzc 152811 B-76 ITEM 1.1 - POST TRIP REVIEHJ PROGRAM DESCRIPTION & 06/25/85C >(t& sK'e~p4Ae-152892 '-77 ITEM 2.1 EQUIPMENT CLASSIFICATION & VENDOR INTER 09/30/86 gg AC4c Qvd g 152973 B-78 ITEMS 3 ~ 1'1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 01/15/86 Asc Ak~
153054 B-79 ITEM 3.1.3 POST MAINTENANCE TESTING CHANGES TO 11/14/85C p 4-4 il (fS 153108 B-80 ITEM c5.1 - REACTOR TRIP SYSTEM RELIABILITY VENDO 01r15/86 co pl + s(gg 153161 B-81 ITEMS 4.2.1 &. 1.2.2 -PREVENTATIVE MAINT PROG FOR R 06/29/85C Cs~t <b 5 (Ss 153203 B-82 ITEM 0.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 12/03/84C Pnpukk 7(sb 150577 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 10/17/8CIC ~@4% R(+tgorp4~ Awe /no(io4
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FACILITY IMPLEMENTATION 3.2.3 T.S- S-R COMPONENTS 4.2.3 & 4.2.4 LIFE COMPONENTS 4.3 W AND B&W T.S.
4.'5.1 DIVERSE TRIP 4.5.2 PWR SECONDARY WATER
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.ECCS ZIRC CLAD II (FOLLOWUP OF MPA TO STAFF RECOMMENDATIONS CONCERN MODEL ERROR-COMPLIANCE WITH 10 CFR-LIC ACT QHKUZK 11/14/85C 11/28/86 02/28/86 11/01/86 04r30r87 10/30/81C 02/15/79C 03/23/82C 12/14/82C 05/30/79C 11/01/83C 05/06/80C 08/25/83C 06/28/85C 01/24/86C 09/22/78C
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F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 11/12/82C c<< sw F-20 II.F.1.1 09/30/81C M~p4 4 44965 45036 F-21 II.F.1.2 NOBLE GAS MONITOR IODINE/PARTICULATE SAMPLING 09/30/81C co~~ ~Is~
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-1208731-001 REGULATORY INFORMATION TRACKING SYSTEH PAGE NO. i ~ 518 FACILITY IHPLEMENTATION 03/31/86 URKEY POINT 4 (CONTINUATION)
LIC ACT LICENSEE HHELUf 47715 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 05/02/83C Cc AM 55 47786 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 05/02/83C s~.
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45177 F-26 II.F.2 INSTRUMENTS.FOR DETECTION ON INADEQUATE 01/26/85C 46911 47825 45255 F-30 F-33 F-36 II.K.2.13 II.K.2.17 II.K.3.1 THERMAL-MECHANICAL REPORT POTENTIAL FOR VOIDING IN RCS AUTO PORV ISOLATION 06/06/84C 01r06/84C 09/1 6/83C Cow Co Mv-~4
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'6/24/82C Ce~ phd-4 BZ 45387 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 45418 F"39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C Qgz ~o~Q~d~g 45467 15497 45527 F-40 F"41 F-42 II.K.3.9 II.K.3.10 II.K.3.12 PID CONTROLLER ANTICIPATORY TRIP MODIFICATIONS ANTICIPATORY TRIP ON TURBINE TRIP 08/20/81C 08/20/81C 08/20/81C
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%6061 F-64 III.A.1:2 OPERATIONAL SUPPORT CENTER 06/30/86 gg. ~mP~p pQg 'h~ p~~Q 46133 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 06r30/86 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C 46205 46277 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/13/83C pLd'cc Acro 46348 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 06/30/86 46419 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 02/09/82C Co~~ Q~
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