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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 ML17241A5001999-10-21021 October 1999 Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C ML17309A9981999-10-19019 October 1999 Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points ML20217F6171999-10-0808 October 1999 Forwards Insp Repts 50-335/99-11 & 50-389/99-11 on 990827 & 990907-09.No Violations Identified.Matl Encl Contained Safeguards Info as Defined by 10CFR73.21 & Disclosed to Unauthorized Individuals Prohibited by Section 147 of AEA 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 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 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 ML17241A4811999-10-0101 October 1999 Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a 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 ML17241A4701999-09-25025 September 1999 Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant ML17241A4721999-09-24024 September 1999 Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999 ML17241A4681999-09-22022 September 1999 Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6) 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 ML17241A4671999-09-20020 September 1999 Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. ML17241A4581999-09-13013 September 1999 Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program 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 ML17241A4521999-08-31031 August 1999 Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval ML17241A4531999-08-31031 August 1999 Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006 ML17241A4501999-08-26026 August 1999 Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached 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 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 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. 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 ML17241A4371999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d) ML17241A4461999-08-11011 August 1999 Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999 Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3) ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17309A9911999-07-26026 July 1999 Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified ML17241A4151999-07-22022 July 1999 Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2 ML17241A4221999-07-22022 July 1999 Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. ML17241A4471999-07-22022 July 1999 Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure ML17241A4101999-07-16016 July 1999 Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants 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 ML17309A9881999-07-0707 July 1999 Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager ML20209F1541999-07-0606 July 1999 Informs That NRC in Process of Conducting Operational Safeguards Response Evaluations at Nuclear Power Reactors. Plant Chosen for Such Review Scheduled for Wk of 990823-26 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 ML17241A3971999-06-30030 June 1999 Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr ML17241A4011999-06-30030 June 1999 Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604 ML17241A3951999-06-29029 June 1999 Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl 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. ML17241A3731999-06-17017 June 1999 Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16) ML17241A3641999-06-14014 June 1999 Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139 ML20195F3871999-06-11011 June 1999 Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5) 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARIR 05000250/19900351990-10-30030 October 1990 Forwards Insp Repts 50-250/90-35 & 50-251/90-35 on 901001-05.No Violations or Deviations Noted.Repts Withheld (Ref 10CFR73.21) ML20062A2151990-10-11011 October 1990 Advises That 900926 Rev 7 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion in Plan ML20062A2091990-10-11011 October 1990 Advises That 900926 Rev 27 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable.Plan Withheld (Ref 10CFR73.21) ML20058N2041990-08-10010 August 1990 Advises That 900725 Rev 23 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20055J2431990-07-24024 July 1990 Advises That 900711 Rev 22 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable.Plan Withheld (Ref 10CFR73.21) ML20059M9461990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C5941990-05-16016 May 1990 Advises That 900305 & 0416 Revs 20 & 21 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20248J0421989-09-29029 September 1989 Forwards Partially Withheld Insp Repts 50-250/89-42 & 50-251/89-42 on 890828-0901 (Ref 10CFR2.790(d) & 73.21).No Violations or Deviations Noted ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20247H8191989-09-13013 September 1989 Advises That 890823 Rev 22 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20247K2231989-09-11011 September 1989 Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe ML20247E3371989-09-0707 September 1989 Forwards Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Records Retention for Radiological Effluent Monitoring & ODCM ML20246Q0121989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted IR 05000029/19890141989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246J5881989-08-29029 August 1989 Notifies That plant-specific Review of Vital Area Validation Issue for Plant Terminated.Issue Will Be Resolved on Generic Basis ML20246C3941989-08-15015 August 1989 Forwards Safeguards Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14.No Violations Noted ML20246C8211989-08-11011 August 1989 Confirms 890808 Telcon Re Util Participation in NRC Regulatory Impact Survey on 891023 in Berlin,Ct.Schedule & General Discussion Groups Shown in Encl ML20246B0901989-08-0909 August 1989 Forwards Insp Repts 50-250/89-33 & 50-251/89-33 on 890717-21.No Violations or Deviations Noted ML20248D6921989-08-0404 August 1989 Advises That Rev 6b to Generating Stations Emergency Plan Transmitted by Util 890710 Form Acceptable & Does Not Decrease Effectiveness of Plan ML20248C0561989-08-0303 August 1989 Forwards Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants.Nrc Requested to Be Notified Upon Completion of Human Factors Review ML20245H5331989-08-0202 August 1989 Advises That 890519 Changes to QA Program Described in CPC-2A Acceptable.Issues Addressed Listed ML20248B7491989-07-31031 July 1989 Advises That 890711 Rev 5 to Guard Training & Qualification Plan Consistent w/10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20248B7571989-07-31031 July 1989 Advises That 890711 Rev 6 to Guard Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20248A1321989-07-28028 July 1989 Advises That 890711 Rev 21 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20248B6481989-07-28028 July 1989 Forwards Insp Repts 50-250/89-30 & 50-251/89-30 on 890614- 16.No Violations or Deviations Noted ML20247H6891989-07-25025 July 1989 Requests Proposed Design Change to Containment Hydrogen Monitoring Sys,W/Schedule for Implementing Change or Justification for Existing Configuration ML20247R9141989-07-24024 July 1989 Advises That 890711 Rev 17 to Plant Physical Security Plan Consistent w/10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20246J5121989-07-12012 July 1989 Forwards Safeguards Insp Repts 50-250/89-21 & 50-251/89-21 on 890424-28 & Notice of Violation.Advises That Penalty Unwarranted to Further Emphasize Need for Improvement in Security Program.Notice Withheld (Ref 10CFR2.790 & 73.21) ML20246A2951989-06-29029 June 1989 Forwards Request for Addl Info Re NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20246L2211989-06-26026 June 1989 Forwards Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Revise Tech Specs by Removing Tech Spec Figures 6.2-1 & 6.2-2 Re Organizations Functional Requirements ML20245J3301989-06-22022 June 1989 Provides Background Info on Regulatory Analysis Supplementing NRC Proposed Backfit,Per 890413 Request.Util Expected to Provide Schedule for Implementation of Required Improvements ML20245F2691989-06-16016 June 1989 Forwards SER Accepting Licensee 850612 Response to Generic Ltr 83-28,Item 4.5.3 Re Trip Reliability & on-line Functional Testing of Trip Sys ML20245K0881989-06-16016 June 1989 Advises That 890327 Rev 16 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20245H1491989-06-15015 June 1989 Submits Correction/Clarificaton to Util 890508 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Program on Critical Air Demand Equipment Is in Addition to Investigations Performed ML20245B1731989-06-15015 June 1989 Ack Receipt of Rev 55 to QA Topical Rept CE-1-A.Program Satisfies Requirements of 10CFR50,App B & Acceptable ML20244C2941989-06-0909 June 1989 Advises Tht Util 890329 Request for Approval to Use Fuses for Electrical Isolation of non-Class 1E Dc Power Sys Acceptable Provided That Circuit Breaker in Parallel to Two Fuses Locked Open ML20244C5091989-06-0101 June 1989 Advises That Bunker Ramo Penetration Assemblies Environmentally Qualified to Perform Intended Functions for Plants,Per 890224 Rept & .Concerns Expressed in Re Byron Unit 2 Satisfied ML20248C2671989-05-31031 May 1989 Forwards Insp Repts 50-321/88-37,50-366/88-37 & 50-424/88-53 on 881102-890106 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790(d) & 73.21) ML20247M7731989-05-26026 May 1989 Forwards Director'S Decision Re Ohio Citizens for Responsible Energy 10CFR2.206 Petition Re 880309 Power Oscillation Event at Lasalle,Unit 2 IR 05000250/19890091989-05-24024 May 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-250/89-09 & 50-251/89-09 ML20247H3511989-05-19019 May 1989 Advises That Licensee Response to Generic Ltr 82-33 Re post-accident Monitoring Instrumentation,Per Rev 3 to Reg Guide 1.97,acceptable,except for Four Items Listed in Technical Evaluation Rept ML20247J7801989-05-19019 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, Mutually Agreed Upon Between NRC & Westinghouse During 890411 Meeting ML20247C1521989-05-18018 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Understands That Westinghouse Will Provide Util W/Generic Bounding Analysis Re Seismic Loadings ML20247G5241989-05-18018 May 1989 Responds to Re Util Position on Dealing W/Dc Grounds After Discussion W/Nrc in 890301 Meeting.Continued Plant Operation Will Be Allowed Only So Long as Applicable Limiting Conditions/Or Action Statements Met ML20247B2411989-05-17017 May 1989 Comments on Expeditious Actions & Notice of Audit on Generic Ltr 88-17 Re Potential Loss of Dhr.Requests Addl Info Re Training Packages,Administrative Controls for Containment Closure & RCS Level Indications ML20246Q1511989-05-16016 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, Per 890411 Meeting W/Westinghouse Owners Group.Proposed Schedule for Analysis Must Be Accelerated ML20246P8141989-05-15015 May 1989 Requests Addl Info Re 881130 Application for Amends to Licenses Per Generic Ltr 87-09.Affirmation Should Be Provided That Procedures,Mgt Directives & Onsite Reviews Limit Use of Spec 3.0.4 Exceptions ML20246L2741989-05-11011 May 1989 Forwards Anl Draft Rept Re Main Steam Line Breaks in Plants Ice Condenser,Per Util 880613,0907 & 1012 Ltrs & WCAP-10988 & WCAP-10986P,for Review & Comments within 60 Days.W/O Encl 1990-08-10
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F6171999-10-0808 October 1999 Forwards Insp Repts 50-335/99-11 & 50-389/99-11 on 990827 & 990907-09.No Violations Identified.Matl Encl Contained Safeguards Info as Defined by 10CFR73.21 & Disclosed to Unauthorized Individuals Prohibited by Section 147 of AEA 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 ML20209F1541999-07-0606 July 1999 Informs That NRC in Process of Conducting Operational Safeguards Response Evaluations at Nuclear Power Reactors. Plant Chosen for Such Review Scheduled for Wk of 990823-26 IA-99-247, Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)1999-06-11011 June 1999 Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5) ML20195F3871999-06-11011 June 1999 Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5) ML20207C7531999-05-17017 May 1999 Discusses Issue Identified by FPL in Feb 1998 Involving Potential for Fire to Cause Breach of Rc Sys High/Low Pressure Interface Boundary & NRC Decision for Exercise of Enforcement Discretion ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML20205C3701999-03-29029 March 1999 Final Response to FOIA Request for Documents.App a Documents Encl & Available in Pdr.App B Records Being Completely Withheld (Ref FOIA Exemption 5) DD-98-10, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-98-10 Has Expired.Decision Became Final on 981116.With Certificate of Svc.Served on 9811201998-11-19019 November 1998 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-98-10 Has Expired.Decision Became Final on 981116.With Certificate of Svc.Served on 981120 ML20154B2531998-09-17017 September 1998 Responds to Stating Intention to Pursue License Renewal Application for Turkey Point,Units 3 & 4.Info Shared by Util Will Be Useful for NRC Resource Planning ML20237D0471998-08-14014 August 1998 Summarizes 980804 Meeting W/Util in Atlanta,Ga to Discuss Corrective Action Status for Fpfi Conducted in March & April 1998.List of Attendees & Handouts Encl ML20236S7521998-07-20020 July 1998 Ltr Contract:Task Order 15, Turkey Point Safety Sys Enginering Insp, Under Contract NRC-03-98-021 ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20247H9561998-05-19019 May 1998 Ack Receipt of Ltr & Electronic Fund Transfer of $88,000 in Payment for Civil Penalty Proposed by NRC in Ltr .Corrective Actions Will Be Examined During Future Insp ML20247P8331998-05-19019 May 1998 Ltr Contract:Task Order 002, St Luci Engineering & Technical Support Insp, Under Contract NRC-03-98-021 ML20216C5511998-05-0808 May 1998 First Partial Response to FOIA Request for Documents.App a Records Partially Withheld (Ref Exemptions 5 & 7c).App B Records Totally Withheld (Ref Exemption 5) ML20217B4041998-04-21021 April 1998 Responds to Submitted as Petition Under 10CFR2.206 Seeking Certain Action by NRC W/Respect to Fp&L. Request Will Not Be Reviewed,Per 10CFR2.206,due to Listed Reasons ML20217B7801998-04-17017 April 1998 Final Response to FOIA Request for Documents.Forwards Records in App H,Being Withheld in Part (Ref FOIA Exemption 7) IA-97-484, Final Response to FOIA Request for Documents.Forwards Records in App H,Being Withheld in Part (Ref FOIA Exemption 7)1998-04-17017 April 1998 Final Response to FOIA Request for Documents.Forwards Records in App H,Being Withheld in Part (Ref FOIA Exemption 7) IR 05000335/19970161998-03-25025 March 1998 Discusses Insp Repts 50-335/97-16 & 50-389/97-16 on 971103- 980109 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $88,000 ML20203K5641998-02-23023 February 1998 Ack Receipt of to President Ofc of Professional Responsibility,Which Requested Investigation of Nrc.Staff Inappropriately Released Info to Licensee That Could Have Resulted in Identifying Individual Referred to in Ltr ML20202D9521998-02-12012 February 1998 Final Response to FOIA Request for Records.App a Records Partially Withheld (Ref Exemptions 7A & 7C) ML20202D8101998-01-28028 January 1998 Fourth Partial Response to FOIA Request for Documents. Documents Listed in App E,Being Released in Entirety. Documents Listed in App F,Being Released in Part (Ref FOIA Exemption 7C) ML20202D8171998-01-23023 January 1998 Third Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Withheld in Part.App D Records Being Withheld in Entirety (Ref FOIA Exemption 7) ML20202D8701998-01-23023 January 1998 Second Partial Response to FOIA Request for Documents. Records in App B Being Withheld in Part (Ref FOIA Exemption 7) ML20202D9681998-01-21021 January 1998 First Partial Response to FOIA Request for Documents.Records in App a Encl & Being Released in Entirety ML20202D9991997-11-25025 November 1997 Responds to 971120 FOIA Request.Informs That Request Has Been Forwarded to NRC Headquarters DD-97-20, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision DD-97-20 Has Expired.Commission Declined Any Review.Decision Became Final on 971003.W/Certificate of Svc.Served on 9710071997-10-0707 October 1997 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision DD-97-20 Has Expired.Commission Declined Any Review.Decision Became Final on 971003.W/Certificate of Svc.Served on 971007 ML20217E5571997-09-26026 September 1997 Forwards Insp Repts 50-250/97-09 & 50-251/97-09 on 970826.No Violations or Deviations Noted ML20149H8551997-07-23023 July 1997 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in Pdr.App B Records Being Made Available in PDR ML20149E5281997-07-11011 July 1997 Final Response to FOIA Request for Documents.Forwards Documents Listed in App a Being Withheld in Part (Ref Exemptions 5 & 7C) ML20149E8491997-07-10010 July 1997 Forwards Operational Safeguards Response Evaluation Review Held on 970520-21.Evaluation Resulted from Feb 97 Insp That Indicated Changes in Site Protection Strategy or Capability Should Be Validated.Encl Withheld ML20202D9261997-06-0606 June 1997 Partially Deleted Ltr Forwarding Allegation Evaluation Repts RII-1997-A-0053 & RII-1997-A-0054 Re Excessive Overtime Worked for Reactor Operators at Plant & Improper Securing of LPCI Pump ML20202D9591997-05-30030 May 1997 Partially Deleted Ltr Re Allegation Rept RII-97-A-0027 Related to Concerns Over Control of on-site Hazardous Matl, Maint Mgt Practices & Industrial Safety Conditions at Plant ML20140A4431997-05-23023 May 1997 Forty-first Partial Response to FOIA Request for Documents. App Aaaa Record Being Withheld in Part (Ref FOIA Exemptions 5 & 7C) ML20148E8811997-05-21021 May 1997 Fortieth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App Zzz.Documents Will Be Withheld in Part (Ref FOIA Exemption 6) ML20141J0741997-05-19019 May 1997 Fifth Partial Response to FOIA Request for Documents.App E Records Being Withheld in Part (Ref FOIA Exemption 7) ML20141C6011997-05-14014 May 1997 Thirty-sixth Partial Response to FOIA Request for Documents. App Ttt Records Being Withheld in Part (Ref FOIA Exemption 6) ML20148C3561997-05-12012 May 1997 Thirty-fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App Rrr Being Made Available in Pdr.App SSS Records Being Withheld in Part (Ref FOIA Exemption 6) ML20138F6321997-04-25025 April 1997 Thirty-first Partial Response to FOIA Request for Documents. Records in App Lll Encl & Will Be Available in Pdr.App Mmm Records Withheld in Part (Ref FOIA Exemptions 2 & 6) ML20140E4971997-04-23023 April 1997 Thirtieth Partial Response to FOIA Request for Documents. Forwards App Kkk Records Being Made Available in PDR ML20137Y9371997-04-21021 April 1997 Discusses Corrective Actions in Response to GL 96-06 Concerns for Plant,Units 1 & 2 ML20137Y0011997-04-17017 April 1997 Twenty-eighth Partial Response to FOIA Request for Documents.Records in App III Encl & Being Withheld in Part (Ref FOIA Exemptions 2 & 6) ML20202E0611997-04-0808 April 1997 Partially Deleted Ltr Forwarding Allegation Evaluation Rept RII-97-A-0015 Re Female Visitors Not Being Informed About Monitoring of Embryo/Fetus Prior to Gaining Access to Radiologically Controlled Area ML20137P2261997-04-0707 April 1997 Twenty-fifth Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App Eee ML20137R1061997-04-0404 April 1997 Twenty-fourth Partial Response to FOIA Request for Documents.Forwards Documents Listed in App Ddd.Documents Being Released in Entirety.Copyright Documents Withheld ML20137K8161997-04-0202 April 1997 Twenty-second Partial Response to FOIA Request for Documents.Records in App Bbb Encl & Will Be Available in PDR ML20137M0891997-04-0101 April 1997 Twenty First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App GG Throuth Aaa Being Made Available in PDR ML20137N1591997-03-31031 March 1997 Informs That Licensee Facility Scheduled to Administer NRC GFE on 970409.Sonalsts,Inc Authorized Under Contract to Support NRC Administration of GFE Activities ML20137R2791997-03-27027 March 1997 Twentieth Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App FF 1999-09-28
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.t1AR 2 71986 F}orida Power and Light Company iATTN: Mr. C. O. Woody Group Vice President Nuclear Energy Department P. O. Box 14000 Juno Beach, FL 33408
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Gentlemen:
SUBJECT:
SITE VISIT FOR THE EMERGENCY RESPONSE DATA SYSTEM This letter is to inform you of an emergency communications capability that the NRC is considering establishing with licensed nuclear power facilities and an upcoming site visit by an NRC contractor to obtain information on how such a system would interface with your Emergency Operations Facility.
The emergency communications capability being considered is called the Emergency Response Data Systerc (ERDS). The EROS concept has been determined by the NRC to be a design which best addresses the requirements of the NRC with minimal impact on the licensee. The development of the ERDS concept began with.an assessment of the NRC's role in an emergency at a licensed nuclear facility. The Commission determined that the NRC's primary role is one of monitoring the licensee to assure that appropriate recommendations are made with respect to offsite
. protective actions. To fulfill this role, the NRC requires accurate, timely data on four types of parameters: (1) core and coolant system conditions must be known well enough to assess the extent or likelihood of core damage; (2) conditions inside the containment must be known well enough to assess the likelihood of its failure; (3) radioactivity release rates must be available promptly to assess the immediacy and degree of public danger; and (4) the data from the plant's meteorological tower is necessary to assess the distribution of potential or actual impact on the public. A list.of the particular parameters considered necessary to these assessments is included as Enclosure 1.
Experience with the voice-only emergency ccmunications link, currently utilized for data transmission, has demonstrated that excessive amounts of time are needed for the routine transmission of data and for verification or correction of data that appear questionable. Error rates have been excessive; initiations have been slow; frequency of upd;tes has been unreliable. In addition, the current system creates an excessive drain on the time of valuable experts at the NRC and at the facility. When errors occur, they frequently create false issues which, at best, divert experts from the real problems for seriously long periods of time. At worst, incorrect data may cause the NRC to respond to offsite officials with inaccurate or outdated advice that results in the implementation of inappropriate protective actions.
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Florida Power and Light Company 2 Several options were considered for upgrading the data acquisition capabilities at the Operations Center. The options included various means of acquiring the data: manually, automatically using existing systems, or automatically using new systems. Appropriate options for transmitting the data to the Operations Center were considered: electronically formatted data, image facsimile, or by voice through specially qualified communicators.
The criteria used to compare these options involve accuracy, reliability, timeliness, completeness, cost (in dollars and expert personnel), and backfitting requirements. The NRC determined that' automatic transmission of selected parameters from licensees' existing electronic data systems is most capable of providing acceptably complete and reliable data on a timely basis at reasonable cost with the minimum potential for burdening the licensee in an emergency. Most licensees either already have developed or are developing electronic data systems for their . emergency response facilities (ERFs). Because the role of the licenseas' ERFs is similar to the role of the NRC during emergencies, the licensees' data systems already include most of the parameters desired by NRC.
Those few parameters which are not included in any particular licensee's system can be communicated by voice over the Emergency Notification System (ENS), thus avoiding backfitting requirements on the licensee to include additional parameters on their electronic data systems. Data would be accepted in whatever format the licensee uses and reformatted at the Operations Center, as necessary.
Because of the diversity of data systems utilized by the licensees, the best means for extracting the NRC's parameters from each system would be determined on a case-by-case basis. The licensees would have control over transmission and would use the system only during emergencies. This option is the Emergency Response Data System. The design concept for the ERDS is outlined in Enclosure 2.
Previous discussions with several licensees and two tests of the ERDS concept which were conducted with Duke Power and Commonwealth Edison have indicated that the ERDS . concept has the potential to significantly improve the NRC's incident response function and its response relationship with licensees. Therefore, to determine more specifically the factors that would affect' implementation of an ERDS, we have initiated an effort to survey the equipment and facilities at licensees' sites and determine the hardware and software requirements of such a system. You should expect to be contacted in the near future by a member of this Regional Office to arrange a site visit by an NRC Headquarters staff member accompanied by an NRC contractor to speak with you on this subject. The visit is an information gathering process. It is oriented toward determination of:
The availability of a particular set of PWR or BWR parameters in digital form.
The verification and validation method, if any.
, Characterization of the available data feed point (s).
Access will be needed to documentation and knowledgeable individuals typically from Instrumentation and Centrol, technical, telecommunications, and computer systems cadres within the plant staff._ Please contact Mr. Bill Sartor with the
Florida Power and Light Company 3 Region II Emergency Preparedness Section at (404) 331-6152 and provide him with a licensee contact to assist in the scheduling of site visits. NRC Headquarters has indicated that site visits will. be initiated during early 1986 and should be completed within four months.
1 Should you have questions regarding the site visits, please contact Mr. Sartor.
Should you have any questions on. the ERDS concept in general, please contact Mr. Ken Perkins with the Incident Response Branch at NRC Headquarters, telephone (301) 492-7361.
Sincerely,
- Original Signed by Roger D. Walker Roger D. Walker., Director Division of Reactor Projects
Enclosures:
- 1. PWR and BWR Parameters
- 2. ERDS Design Concept
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i ENCLOSURE 1 PWR PARAMETER LISTS Primary Coolant System Pressure Temperatures - hot leg Temperatures - cold leg Temperatures - core exit thermocouples Subcooling margin Pressurizer level RCS charging / makeup flow Reactor vessel level (when available)
Reactor coolant flow Neutron flux - startup range
-Secondary Coolant System Steam generator levels Main feedwater flows Auxiliary / Emergency feedwater flows Safety Injection High pressure safety injection flows Low pressure safety injection flows Safety injection flows (Westinghouse)
Borated water storage tank level Containment Containment pressure Containment. temperatures Hydrog'n e concentration Containment sump levels Radiation Monitoring System Reactor coolant radioactivity Containment radiation level Condenser air removal radiation level j Effluent radiation monitors Process radiation monitor levels Meteorological Wind speed Wind direction Atmospheric stability BWR PARAMETER LISTS Reactor Coolant System Reactor Pressure Reactor vessel level Feedwater flow Neutron flux-startup range i
Enclosure 1 2 Safety Infection RCIC flow HPCI/HPCS flow Core spray flow LPCI flow Condensate storage tank level Containment Drywell pressure Drywell temperature Hydrogen & 0xygen Concentration Drywell sump level Suppression pool temperature Suppression pool level Radiation Monitoring System Reactor coolant radioactivity level Primary containment radiation level Ccndenser off gas radiation levels Effluent radiation monitor Process radiation levels Meteorological Wind speed Wind direction Atmospheric stability
ENCLOSURE 2 EMERGENCY RESPONSE DATA SYSTEM (ERDS)
DESIGN CONCEPT Data Acquisition Parameter inputs to ERDS would be obtained from an existing computer system (e.g., SPDS, plant computer, EOF data systems, etc.) at the plant.
Data Transmission Data will be transmitted to the NRC Operations Center by modem to cor.mercial telephone line or a dedicated line maintained by NRC (e.g., ENS).
Data Collection A processing system maintained by the NRC will receive the data stream by modem. The system will be . designed to receive all varied data streams and to reformat the data into a consistent format. The reformatted data will be output to CRTs and printer.
Parameter List The parameter list would ~ include those parameters necessary to ensure that appropriate protective action is being taken with respect to offsite recommendations. The list would be limited to those parameters involving plant status,_ radiological and meteorological conditions.
Licensees will not be required to backfit their systems to include additional parameters to provide data on NRC's parameter list. Data that is not available from the electronic data stream can be provided by voice over existing phone lines.
Transmission Frequency The updating frequency of the licensees' system will determine transmission frequency to NRC. If more frequent updates are required than those provided electronically by a particular licensee, the increased frequency will be accomplished (for a very limited subset of parameters) by voice over existing telephone lines.
Control The licensee will have complete control over data transmission. ERDS would be " switched on" by the licensee in the early stage of a declared emergency.