|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML17241A5001999-10-21021 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 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) 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 ML17241A4531999-08-31031 August 1999 Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006 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 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 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) 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 ML17241A4471999-07-22022 July 1999 Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure 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. ML17241A4151999-07-22022 July 1999 Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2 ML17241A4101999-07-16016 July 1999 Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants 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 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 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 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 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 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) 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) L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999 Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3) ML17241A3561999-06-0707 June 1999 Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209 ML17241A3601999-06-0707 June 1999 Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998 ML20195F3941999-05-27027 May 1999 FOIA Request That Memo from J Calvo to Fl Lebdon Re TIA - St Lucie,Unit 1 Environ Qualification of Woodward Governor Controls Be Placed in PDR ML17241A3461999-05-24024 May 1999 Forwards Revised Relief Request 22 to Clarify Several Areas of Relief.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage ML17241A3391999-05-20020 May 1999 Forwards Notification of Change to Small Break LOCA ECCS Evaluation Model Used for St Lucie Unit 1.Anomaly Was Discovered & Corrected That Resulted in Reducing Calculated PCT for Limiting SBLOCA by More than 50 F ML17241A3371999-05-20020 May 1999 Forwards Util Suppl to GL 95-07 Response Re pressure-locking & Thermal Binding of safety-related power-operated Gate Valves,In Response to NRC Second RAI Dtd 990225 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 ML17241A3301999-05-17017 May 1999 Forwards LER 99-004-00 Re as Found Cycle 10 Psv Setpoints Outside TS Limits,Which Occurred on 990415.Root Cause Determination Not Yet Complete.Suppl to Include Root Cause & Corrective Actions Will Be Submitted ML17309A9821999-05-10010 May 1999 Forwards Rev 36 to St Lucie Emergency Plan, Per 10CFR50.54(q).Executive Summary & Summary of Changes Incorporated by Rev,Encl IR 05000335/19980141999-04-29029 April 1999 Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated ML17241A3221999-04-29029 April 1999 Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated ML17229B1071999-04-28028 April 1999 Forwards 1998 Annual Environ Operating Rept for St Lucie Unit 2. Rept Includes Discussions of 5-inch Barrier Net Maint & Taprogge Condenser Tube Cleaning Sys Ball Loss,As Agreed at First Biennial Sea Turtle Meeting Held on 980120 ML17229B1051999-04-22022 April 1999 Requests That Listed Individuals Be Placed on Official Serve List for Nuclear Matl Safety & Safeguards Info Notices ML17229B1061999-04-21021 April 1999 Notifies NRC of Change in Medical Status of Licensed Operator Pf Farnsworth (Docket 55-21285,license SOP-21094). NRC Form 3996, Medical Exam Certification, Encl.Encl Withheld Per 10CFR2.790(a)(6) ML17309A9851999-04-15015 April 1999 Requests That NRC Review Denial of Appeal from Assessment of Fees Assessed in 981101 Invoice RS0062-99 & Assessment of Fees in Invoice RS0182-99 Which Was Also Denied in 990305 Ltr.Both Invoices Are for Fees Re Inspector GG Warnick ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML17229B0951999-04-0808 April 1999 Requests Approval of Encl Revised Relief Request 6,in Response to 990322 Telcon with NRC & 10CFR55.55a(a)(3). Request States That Visual VT-3 Exams Will Be Conducted IAW IWA-2213 & Repairs Will Be IAW Util ASME Section IX Program ML17229B0821999-04-0707 April 1999 Requests Approval of Interim Relief Request 26 Re Repair Requirements for Class 2 ECCS Piping,Per 10CFR50.55a(a)(3) & 50.55a(g)(iii).Alternative Actions Apply Guidance of GLs 91-18 & 90-05 & ASME Code Case N-513.Evaluation,encl 1999-09-28
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062A2091990-10-11011 October 1990 Advises That 900926 Rev 27 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable.Plan Withheld (Ref 10CFR73.21) 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 ML20059M9461990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20247H8191989-09-13013 September 1989 Advises That 890823 Rev 22 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable 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 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 ML20248A1321989-07-28028 July 1989 Advises That 890711 Rev 21 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20245F7471989-04-25025 April 1989 Advises That 890327 Rev 20 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20248H7051989-03-29029 March 1989 Advises That 881213 & 890224 Revs 18 & 19 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20196D2161988-11-23023 November 1988 Advises That 880921 Rev 5 to Safeguards Contingency Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable IR 05000335/19880201988-11-0303 November 1988 Discusses Insp Repts 50-335/88-20 & 50-389/88-20 on 880803 & Forwards Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790 & 10CFR73.21) ML20206E6251988-11-0202 November 1988 Forwards Insp Repts 50-335/88-23 & 50-389/88-23 on 880925-30.No Violations or Deviations Noted ML20205Q0861988-10-31031 October 1988 Advises That 880921 Rev 17 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Changes Requiring Further Clarification Withheld ML20206E7491988-10-31031 October 1988 Advises That Most Changes in Rev 17 to Physical Security Plan,Transmitted by Consistent W/Provisions of 10CFR50.54(p) & Acceptable.Changes Requiring Clarification Delineated in Encl.Encl Withheld (Ref 10CFR73.21) ML20155J3501988-10-19019 October 1988 Advises That 880912 Rev 4 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable IR 05000335/19880101988-10-10010 October 1988 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-335/88-10 ML20154R5091988-09-21021 September 1988 Advises That 880917 Rev 16 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20154E6871988-09-0909 September 1988 Confirms 880906 Enforcement Conference Re Inattentiveness of Guard Posted to Control Access to Vital Area.List of Attendees,Summary & Handout Encl.Encls Withheld (Ref 10CFR2.790(d) & 10CFR73.21) ML20151Y6791988-08-19019 August 1988 Forwards Insp Repts 50-335/88-20 & 50-389/88-20 on 880803. Violations Noted in Rept Under Consideration for Escalated Enforcement Action.Enforcement Conference Scheduled for 880906 ML20151C1721988-07-0707 July 1988 Advises That 880623 Rev 15 to Physical Security Plan Meets Requirements of 10CFR50.54(p) & Acceptable ML20151C1991988-07-0707 July 1988 Advises That Revised Page to Rev 13 to Physical Security Plan Transmitted by Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20195E2131988-06-15015 June 1988 Forwards Request for Addl Info Re Util 880214 Request to Use Instrumented Insp Technique.Response Requested within 45 Days of Ltr Date.Full Response Schedule within 30 Days of Ltr Date Requested If Unable to Provide Full Response ML20196A8091988-06-14014 June 1988 Forwards Insp Repts 50-335/88-11 & 50-389/88-11 on 880523-26.No Violations or Deviations Noted ML20195C6191988-06-10010 June 1988 Forwards Insp Repts 50-335/88-12 & 50-389/88-12 on 880516-20.No Violations or Deviations Noted IR 05000335/19880021988-05-10010 May 1988 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-335/88-02 & 50-389/88-02.Corrective Actions Will Be Examined During Future Insps ML20153F4461988-05-0404 May 1988 Advises That 880411 Rev 14 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20151V8251988-04-27027 April 1988 Advises That 880307 Rev 13 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable.Encl Withheld Per 10CFR73.21.Corrected Plan Pages Re Intake Canal Intrusion Detection Sys Requested,Per 880310 Conference ML20196G9391988-02-29029 February 1988 Advises That 880127 Rev 11-07 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Page Submitted W/Rev Also Addressed Rev 11-1 Re Compensatory Measures at Intake Canal.Rev Not Received in Region ML20237D1351987-12-16016 December 1987 Advises That 871123 Submittal of Rept Describing Change to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20237D5701987-12-12012 December 1987 Forwards Safety Evaluation Granting Util 861029 & 870121 Requests for Relief from Various Exam Requirements of ASME Boiler & Pressure Vessel Code,Section XI IR 05000335/19870191987-11-19019 November 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-335/87-19 & 50-389/87-18.Response Meets Requirements of Radiological Emergency Plan & Implementing Procedures ML20235J2441987-09-25025 September 1987 Forwards Insp Repts 50-335/87-19 & 50-389/87-18 on 870825-0904.No Violations or Deviations Noted.Response Stating Actions Planned or Taken to Correct Exercise Weaknesses Requested within 45 Days of Ltr Date ML20235A9941987-09-0909 September 1987 Advises That Change to Physical Security Plan,Transmitted on 870526 Unacceptable Under Provisions of 10CFR50.54(p). Change Downgrades Vital Equipment & Decreases Effectiveness of Plan.Application for Amend Required to Pursue Matter ML20235Y1871987-07-21021 July 1987 Requests Addl Info Re Util 860515,1013 & 31 Responses to IE Bulletin 85-003, Motor Operated Valve Common Mode Failures During Plant Transient Due to Improper Switch Settings. Response Requested within 30 Days of Ltr Date ML20234E6981987-06-25025 June 1987 Confirms Arrangements for Operator & Senior Operator Licensing Requalification Exams Scheduled for Wk of 870928. Encl Ref Matl Requested by 870724 in Order to Meet Scheduled Exam Date ML20216C4461987-06-24024 June 1987 Ack Receipt of Transmitting 870325 Rev to Physical Security Plan,Deleting Certain Plant Equipment from Vital Equipment List Currently Under Review by NRC ML20215K8661987-06-22022 June 1987 Forwards Exam Rept 50-335/OL-87-01 of Exams Administered on 870420-22 ML20214M1261987-05-21021 May 1987 Forwards SER Supporting Util 831110 & 850618 Responses to Generic Ltr 83-28,Item 2.1 (Part 2) Re Establishment of Interface W/Either NSSS or Vendors of Each Component of Reactor Trip Sys.Contractor Evaluation Rept Also Encl ML20206E2921987-04-0303 April 1987 Requests Cooperation in Region II Participation in Upcoming Emergency Exercise,Including Full Response by Base Team & Partial Participation of Site Team in Test of Incident Response Plan.Approx 16 Regional Personnel Will Participate ML20205P4881987-03-25025 March 1987 Advises That 850915 Rev 16 to Radiological Emergency Plan Consistent W/Provisions of 10CFR50.47(b) & App E to 10CFR50 & Acceptable ML20205B9321987-03-20020 March 1987 Forwards Insp Repts 50-335/87-02 & 50-389/87-02 on 870217- 26.No Violations or Deviations Noted ML20207T7721987-02-27027 February 1987 Forwards Insp Repts 50-335/87-01 & 50-389/87-01 on 870113- 0207.No Violations or Deviations Noted ML20211H2211987-02-17017 February 1987 Forwards Exam Rept 50-335/OL-86-02 on 861117 & Util 861203 Comments on Exam ML20211G4031987-02-14014 February 1987 Forwards Safety Evaluation & EGG-NTA-7463, Reactor Trip Sys Reliability..., Supporting Response to Generic Ltr 83-28,Item 4.5.2 Re Periodic on-line Testing of Reactor Trip Sys.Plant Designed to Permit on-line Testing IR 05000335/19860251987-01-27027 January 1987 Forwards Info Re Contractor Employee Concerns of Alleged Poor Procedure for Welder Certification & Discriminatory Release from Plant,Documented in Insp Repts 50-335/86-25 & 50-389/86-24.Statement Withheld (Ref 10CFR2.790) ML20210E0231987-01-26026 January 1987 Forwards Insp Repts 50-335/86-27 & 50-389/86-26 on 861216- 870112.No Violations or Deviations Noted ML20210D5141987-01-26026 January 1987 Advises That Written & Oral Operator Licensing Exams Scheduled for Wk of 870420,per Telcon Between J Spodick & B Dean.Requests Selected Ref Matl from Encl List by 870220 to Avoid Delay in Administering Exams ML20213A3791987-01-21021 January 1987 Advises That 861211 Rev 11 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable IR 05000335/19860211987-01-20020 January 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-335/86-21 & 50-389/86-20.Violation Re 10CFR50.59 Annual Reporting Requirements for 820721 & 860327 FSAR Updates Withdrawn ML20213A1191987-01-16016 January 1987 Extends Invitation to Participate in 870218 Incident Investigation Program Workshop in Atlanta,Ga.Workshop Will Provide Understanding of Process by Which NRC Investigates Potential Significant Incidents.Agenda Encl.W/O Procedures 1990-06-13
[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 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 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) ML20247P8331998-05-19019 May 1998 Ltr Contract:Task Order 002, St Luci Engineering & Technical Support Insp, Under Contract NRC-03-98-021 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 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 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) 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) 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) 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) 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) 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 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 ML20137K4711997-03-25025 March 1997 Nineteenth Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App DD & Ee ML20137B8371997-03-12012 March 1997 Sixteenth Partial Response to FOIA Request for Documents. Records Subj to Request Identified in App Z & Encl ML20136C4211997-03-0606 March 1997 Fifteenth Partial Response to FOIA Request for Records. App Y Records Encl & Available in PDR ML20136A7521997-03-0505 March 1997 Forteenth Partial Response to FOIA Request for Documents. Records in App W Encl & Available in Pdr.App X Records Withheld in Part (Ref FOIA Exemption 6) ML20135E4221997-03-0505 March 1997 Ack Receipt of & Check for $100,00 in Payment for Civil Penalties Proposed by NRC in .Corrective Actions to Be Examined During Future Insps ML20136A6181997-02-28028 February 1997 Twelfth Partial Response for FOIA Request for Documents.App U Records Being Withheld in Part (Ref FOIA Exemptions 4,5 & 6) 1999-09-28
[Table view] |
Text
_. - _ _. - _ _ _ . . . _
May 9, 1985
~ Docket Nos.-50-335 DISTRIBUTION:
and 50-389 tM Gray File NRC PDR L PDR 4 Mr. J. W. Williams, Jr. HThompson OELD LVicePresident. EJordan Nuclear Energy Department Florida Power & Light Company BGrimes JPartlow P. O. Box 14000 Juno Beach, Florida 33408 DESells PMKreutzer
Dear Mr. Williams:
ACRS +10
SUBJECT:
. DRAFT TECHNICAL EVALUATION REPORT (TER) FOR SALEM ATWS ITEM I.2 (GENERIC LETTER 83-28)
Re: St. Lucie Plant, Unit Nos. 182 The staff .has completed a preliminary ' review to assess the completeness and
- adequacy of licensee responses to Generic Letter 83-28 Item 1.2. For the
' St. .Lucie Plant, Unit Nos.1 & 2, your response was found to be incomplete in four of the areas evaluated.
1
- .The enclosed TER provides a technical evaluation representing the staff's
-initial judgment of the areas evaluated. Pen and ink changes have been made to the TER by your. project manager to make the wording consistent with our approach.
In order to preserve our present review schedule, .we would appreciate your
!- cooperation in obtaining additional information that will permit us to complete our review. It would appear.that the needed information on your facility could be obtained by telephone conference within one week of your
. receipt of the DRAFT TER. Your project manager'will.be working with you to arrange an acceptable time to conduct the necessary conference calls. OMB clearance is not required since th information needs for each plant vary.
l
, James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
DRAFT TER on Salem ATWS Item 1.2 l
i cc w/ enclosure
- See next page l '
- ORB #3
- L ORB #3:DL C :DL
- er DESp11s:dd Miller
/g /85 5/}/85 /c /85 mw sus p PDR
.o SAIC-85/f525-10 REVIEW OF LICENSEE AND APPLICANT RESPONSES TO NRC GENERIC LETTER 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events). Item 1.2
" POST-TRIP REVIEW: DATA AND INFORMATION CAPABILITIES" FOR
, ST. LUCIE PLANT, UNITS 1 & 2 (50-335, 50-389)
Technical Evaluation Report Prepared.by Science Applications International Corporation 1710 Goodridge Drive McLean, Virginia 22102 Prepared for U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Contract No. NRC-03-82-096 1
I J
l 2
-- ,- , , ,,., - -a- . - - ---a,- -- --- - - -- -- - , -. -,,-.--,- . +, , - - , -, ,
~
~
FOREWORD This report contains the technical evaluation of the St. Lucie Plant, Units 1&2 response to Generic Letter 83-28 (Required Actions Based on Generic Implications of Salem AT JS Events). Item 1.2 " Post Trip Review:
Data and Information Capabilities."
For the purposes of this evaluation.. the review criteria, presented in part 2 of this report, were divided into five separate categories. These are:
- 1. The parameters monitored by the sequence of events and the time history recorders,
. 2. The performance characteristics of the sequence of events recorders,
- 3. The performance characteristics of the time history recorders, '
- 4. The data output fomat, and
- 5. The long-term data retention capability for post-trip review material.
All available responses to Generic Letter 83-28 were evaluated. The plant for which this report is applicable was found to have adequately responded to, and met, category 2.
MvwdC 44 The report describes the specific methods used to determine he cate-gorization of the responses to Generic Letter 83-28. Since this valuation report was intended to apply to more than one nuclear power plan specifics regarding how each plant met (or failed to meet) the --- '----" are not presented. Instead, the evaluation presents a categorization of the responses according to which categories of -- ,Mc;. : .t: are satisfied and which are not. The evaluations are based on specific criteria (Section 2) derived from the requirements as stated in the generic letter.
i I
TABLE OF CONTENTS Section Page Introduction. . . . . . . . . . . . . . . . . . . . . . . . . I 1.- Background. . . . . . . . . . . . . . . . . . . . . . . . . . 2
- 2. Review Criteria . . . ................... 3
- 3. Evaluation. . . . . . . . . . . . . . . . . . . . . . . . . 8
- 4. Conclusion. . . . . . . . . . . . . . . . . . . . . . . . . . 9 5.- References. . . . . . . . . . . . . . . . . . . . . . . . . . 10
- 4. ~ S u//d4M d oc, time.eist F a(. Tel e un . - - - 13 d
e
l INTRODUCTION M.- y l
SAIC has reviewed the g submittals prepared in response to Generic Letter !
83-28, item 1.2 " Post-Trip Review: Data and Information Capability", .
The sube ittals (see references) contained sufficient information to determine that the data and information capabilities at this plant are acceptable in the following area.
e The sequence-of-events recorder (s) performance charac-teristics.
However, the d.*.ta and information capabilities, as described in the submittal, either fail to meet the review criteria or provide insufficient information to allow determination of the adequacy of the data and information capabilities in the following areas, e The parameters monitored by both the sequence-of-events and time history recorders, e The time history recorder (s) performance characteris-tics.
e The output format of the recorded data.
e The long-term data retention, record keeping, capa-bility, i
1
- 1. Backcround On February 25, 1984, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal from the reactor protection system. This incident occurred during the plant startup and the reactor was tripped manually by the operator about 30 seconds after the initiation of the automatic trip signal. The failure of the circuit breakers has been determined to be related to the sticking of the under voltage trip attachment. Prior to this incident; on February 22, 1983; at Unit 1 of the Salem Nuclear Power Plant an automatic trip signal was generated based on steam generator low-low level during plant startup.
In this case the reactor was tripped manually by the operator almost coinci-dentally with the automatic trip. At that time, because the utility did not have a requirement for the systematic evaluation of the reactor trip, no investigation was performed to determine whether the reactor was tripped automatically as expected or manually. The utilities' written procedures .
required only that the cause of the trip be determined and identified the I
responsible personnel that could authorize a restart if the cause of the trip is known. Following the second trip which clearly indicated the problem with the trip breakers, the question was raised on whether the circuit breakers had functioned properly during the earlier incident. The most useful source of information in this case, namely the sequence of events printout which would have indicated whether the reactor was tripped automatically or manually during the February 22 incident, was not retained after the incident. Thus, no ju.dgment on the proper functioning of the trip system during the earlier incident could be made.
Following these incidents; on February 28, 1983; the NRC Executive
. Director for Operations (E00), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Sale'm Nuclear Power Plant.' The results of the staf f's inquiry into the generic implications of the Salem Unit incidents is reported in NUREG-1000, " Generic Implications of ATWS Events at the Salem Nuclear Power Plant." Based on the
)
4 results of this study, a set of required actions were developed and included in Generic Letter 83-28 which was issued on July 8,1983 and sent to all licensees of operating reacters, applicants for operating license, and construction permit holders. The required actions in this generic letter consist of four categories. These are: (1) Post-Trip Review. (2) Equipment 2
1
l Classification and Vender Interface. -(3) Post Maintenance Testing, and (4)
Reactor Trip System Reliability Improvements.
The first required action of the generic letter, Post-Trip Review, is the subject of this TER and consists of action item 1.1 " Program Description and Procedure" and action item 1.2 " Data and Information Capability." In the next section the review critgria used to assess the adequacy of the '
utilities responses to the requirements of action item 1.2 will be discussed.
l
- 2. Review Criteria l The intent of the Post Trip Review requirements of Generic Letter 83-28 is to ensure that the licensee has adequa e procedures and data and in' formation sources to understand the caus , nd progression of a reactor trip. This understanding should go beyond a simple identification of the course of the event. It should include the capability to determine the root '
cause of the reactor trip and to determine whether safety limits have been exceeded and if so to what extent. Sufficient information about the reactor trip event should be available so that a decision on the acceptability of a reactor restart can be made.
The following are the review criteria developed for the requirements of Generic Letter 83-28, action item 1.1:
The equipment that provides the digital sequence of events (SOE) record and the analog time history records of an unscheduled shutdown should pro-vide a reliable source of the necessary information to be used in the post trip review. Each plant variable which is necessary to determine the
- cause(s) and progression of the event (s) following a plant trip should be monitored by at least one recorder Quch as a sequence-of-events recorder or l a plant process computer for digital parameters; and strip charts, a plant j
l process computer or analog recorder for analog (time history) variables}
Each device used to record an analog or digital plant variable should be described in sufficient detail so that a determination can be made as to whether the following performance characteristics are met:
i l
t 3 i
f
.m., . + - - - - - - . - , , . . , - , , , . . . , - , - - , , . - - - - - - - . - . - - - - - - - - - - - - - - - - _ - - - _ _ , - - - _ _ _ _ _ - - - - _
e Each sequence-of-events recorder should be capable of detecting and. recording the sequence of events with a sufficient time discrimination capability to ensure that the time responses asso-ciated with each monitored safety-related system can be ascer-tained, and that a determination can be made as to whether the time response is within acceptable limits based on FSAR Chapter 15 Accident Analyses. The recommended guideline for the SOE time discrimination is approxi-mately 100 msec. If current SOE recorders do not have this time discrimination capability the licensee or applicant should show that the current time discrimination capability is sufficient for-an adequate reconstruction of the course of the reactor trip. As a minimum thirshould include the ability to adequately recon-struct the accident scenarios presented in Chapter 15 of the plant FSAR.
- Each analog time history data recorder should have a sample inter- '
val small enough so that the incident can be accurately reconstructed following a reactor trip. As a minimum, the licensee or applicant should be able to reconstruct the course of the accident sequences evaluated in the accident analysis of the plant FSAR (Chapter 15). The recommended guideline for the sample interval is 10 sec. If the time history equipment does not meet this guideline, the licensee or applicant should show that the current time history capability is sufficient to accurately recon-struct the accident sequences presented in Chapter 15 of the FSAR.
e To support the post trip analysis of the cause of the trip and the proper functioning of involved safety related equipment, each analog time history data recorder should be capable,of updating .
and retaining information from approximately five minutes prior to the trip until at least ten minutes after the trip, a The information gathered by the sequence-of-events and time history data collectors should be stored in a manner that will allow for retrieval and analysis. The data may be retained in either hardcopy (computer printout, strip chart output, etc.)
or in an accessible memory (magnetic disc or tape). This 4
information should be presented in a readable and meaningful format, taking into consideration good human factors practices !
(such as those outlined in NUREG-0700). .
s All equipment used to record sequence of events and time history information should be powered from a reliabl6 and non-interruptible power source. The power source used need not be safety related. i l
The sequence of events and time history recording equipment should monitor sufficient digital and analog parameters, respectively, to assure that the course of the reactor trip can be reconstructed. The parameters
. monitored should provide sufficient information to determine the root cause of the reactor trip, the progression of the reactor trip, and the response of'the plant parameters and systems to the reactor trip. Specifically, all input parameters associated with reactor trips, safety injections and other safety-related systems as well as output parameters sufficient to record the proper functioning of these systems should be recorded for use in the post trip review. The parameters deemed necessary, as a minimum, to perform a post-trip review (one$that would determine if the plant remained within its design envelope) are presented on Tabits 1.2-1 and 1.2-2. If the appli-cants' or licensees' SOE recorders and time history recorders do not monitor all of the parameters suggested in these tables the applicant or licensee should show that the existing set of monitored parameters are sufficient to establish that the plant remained within the design envelope for the appro-priate accident conditions; such as those analyzed in Chapter 15 of the plant Safety Analysis Report.
Information gathered during the post trip review is required input for "
future post trip reviews. Data from all unscheduled shutdowns provides a valuable reference source for the determination of the acceptability of the plant vital parameter and equipment response to future unscheduled shut-downs. It is therefore necessary that information gathered during all post trip reviews be maintained in an accessible manner for the life of the plant.
5
- - - . - - - . . , - . - - ,- -.-.,,,-.,-.,-n-.,. -- - . - . . _ . , - - - . , . - - - , - , . , .- ,, , ,,
Table 1.2-1. PWR Parameter List SOE Time History '
Recorder Reco'r der Parameter / Sicial
.(,1\'x 4eactor Trip (1) x Safety Injection x
Containment Isolation (1) x Turbfne Trip x Control Rod Position (1) x x Neutron Flux, Power x 5 Containment Pressure (2) Containment Radiation x Containment Sump Level
, (1) x x Primary System Pressure (1) x x Primary System Temperature .
(1) x Pressurizer Level (1) x Reactor Coolant Pump Status (1) x x Primary System Flow (3) Safety Inj.; Flow. Pump / Valve Status x MSIY Position x x Steam Generator Pressure (1) x x Steam Generator Level (1) x x Feedwater Flow (1) x x . Steam Flow (3) Auxiliary Feedwater System; Flow.
Pump /Value Status x AC and DC System Status (Bus Voltage) .
x Diesel Generator Status (Start /Stop, On/Off) x PORY Position (1): Trip parameters (2): Parameter may be monitored by either an SOE or time history recorder.
(3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
6
Table 1.2-2. BWR Parameter List 50E Time History
Jafety Injection x Containment Isolation x Turbine Trip x Control Rod Position x (1) x Neutron Flux, Power x (1) Main Steam Radiation (2) Containment (Dry Well) Radiation
, x (1) x Drywell Pressure (Containment Pressure)
(2) Suppression Pool Temperature x (1) x Primary System Pressure ,
x (1) x Primary System Level x MSIY Position x (1) Turbine Stop Valve / Control Valve Position x Turbine. Bypass Vs1ve Position x Feedwater Flow x Steam Flow (3) Recirculation; Flow, Pump Status x (1) Scram Discharge Level x (1) ,
Condenser Yacuum x AC and DC System Status (Bus Voltage)
(3)(4) Safety Injection; Flow. Pump / Valve Status x Diesel Generator Status (On/Off, Start /Stop)
(1): Trip parameters.
(2): Parameter may be recorded by either an SOE or time history recorder.
(3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
(4): Includes recording of parameters for all applicable systems from the following: HPCI, LPCI, LPCS, IC, RCIC.
7
- 3. Evaluation i
The parameters identified in part 2 of this report as a part'of the review criteria are those deemed necessary to perform an adequate post-trip
- review. The recording of these parameters on equipment that meets the guidelines of the review criteria will result in a source of information that can be used to determine the cause of the reactor trip and the plant response to the trip, including the responses of important plant systems.
The parameters identified in this submittal as being recorded by the sequence of events and time history recorders do not correspond to the parameters specified in part 2 of this report.
1 The review criteria require that the equipment being used to record the i
se'quence of events and time history data required for a post-trip review ,
meet certain performance characteristics. These characteristics are intended to ensure that, if the proper parameters are recorded, the record -
ing equipment will provide an edequate source of information for an effec-
- tive post-trip review. The information provided in this submittal does not indicate that the time history equipment used would meet the intent of the performance criteria outlined in part 2 of this report. Information supplied in the submittal does indicate that the SOE equipment meets the performance criteria specified in part 2 of this report.
The data and information recorded for use in the post-trip review should be output in a format that allows for ease of identification and use of the data to meet the review criterion that calls for information in a
, readable and meaningful format. The information contained in this submittal does not indicate that this requirement is met, ut4 The data and information used during a post-trip evie'w should b'e retained as part of the plant files. This information uld prove useful during future post-trip reviews. Therefore, one Jr;;' ::::t- is that infor-mation used during a post-trip review be maintained in an accessible manner for the life of the plant. The information contained within this submittal does not indicate that this criterion will be met.
i i
8
- 4. Conclusion The information supplied in response to Generic Letter 83-28 indicates that the current post-trip review data and information capabilities are adequate in the following area:
- 1. the sequence of events recorders meet the minimum performance requirements.
The information supplied in response -to Generic Letter 83-28 does not indicate that the post-trip review data and information capabilities are adequate in the following areas.
- 1. Based upon the information contained in the submittal, all of the parameters specified in part 2 of this report that should be recorded for use in a post-trip review are not recorded. '
- 2. Time history recorders, as described in the submittal, do not meet
, the minimum performance characteristics.
- 3. As described in the submittal, the recorded data may not be output in a readable and meaningful format.
- 4. The data retention procedures, as described in the submittal, do not ladicate that the information recorded for the post-trip review is maintained in an accessible manner for the life of the plant.
It is possible that the current data and information capabil{t th nuclear power plant are adequate to meet the intent of these ?:;90=.3, but were not completely described. Under these circumstances, the licensee should provide an updated, more complete, description to show in more detail the data and information capabilities at this nuclear power plant. If the information provided accurately represents all current data and information capabilties, then the licensee should either show that the data and informa-
' tion capabilities meet the intent of the criteria in part 2 of this report. l or detail future niodifications that would enable the licensee to meet the !
j intent of the evaluation criteria.
s 9
I REFERENCES -
NRC Generic Letter 83-28. " Letter to all licensees of operating reactors, applicants for operating license, and holders of construction permits regarding Required Actions Based on Generic Implications of Salem ATWS Events." July 8, 1983.
NUREG-1000, ~ Generic Implications of ATWS Events at the Salem Nuclear Power Plant, April 1983.
Letter from J.W. Williams, Jr., Florida Power and Light, to D.G.
Eisenhut, NRC, dated November 8,1984. Accession Number 8311110156 in-response to Generic Letter 83-28 of July 8,1983, with attachment.
4 0
99 10
SUPPORTING DOCUMENT FOR TELECON St. Lucie 1 and 2
- 1. Parameters recorded: Unsatisfactory See attached. table for discre'pancies.
- 2. SOE recorders performance characteristics: Satisfactory 7 Unit I sequence of events recorder: 2msee time discrimination with a non-interruptible power supply Unit 2 sequence of events recorder: Imsee time discrimination with a non-interruptible power supple
- 3. Time history recorders performance characteristics: Unsatisfactory SAS (TEC Co s, computer): sample interval of between 1 and 60 secs for the period 'm 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after the trip with non-inter- ile power supply Strip charts: 1"/hr rate, continuous monitoring and non-interruptible power
- 4. Data output format: Unsatisfactory SOE output includes time of event, sensor ID, and an event descriptor.
Time history output includes time, parameter name and value for the strip charts; the TEC computer output is not specified.
- 5. Data retention capability: Unsatisfactory Strip chart data is retained sometimes for life of plant, sometimes not at all.
11 l
, \
l
Required PWR Parameters for Post Trip Review (circled parameters are not recorded)
SOE Time History
Recorder Recorder Parameter / Signal
, -x Reactor Trip (1) x -
Safety Injection x Containment Isolation (1) x Turbine Trip x Control Rod Position (1) x x Neutron Flux, Power
,x Containment Pressure (2) Containment Radiation
@ Containment Sump Level (1)(3) Primary Syste.fi Pressure (Vessel Pressure, Pressurizer Pressure)
(1) x x Primary System Temperature (1) x Pressurizer Level (1) x Reactor Coolant Pump Status (1) x @ Primary System Flow (4) Safety Inj.; Flow, Pump / Valve Status x MSIV Position x x Steam Generator Pressure (1)x x Steam Generator Level (1)x x Feedwater Flow (1) x x Steam Flors (4) Auxiliary Feedwater System; Flow, Pump /Value Status x AC and DC System Status
- x Diesel Generator Status x PORY Position (1): Trip parameters; pressurizer or primary pressure is a trip parameter (depending on plant).
(2): Parameter may be monitored by either an SOE or time history recorder.
(3): Acceptable recorder options are: (a) reactor vessel pressure recorded on both an SOE and time history recorder, or (b) pressurizer pressure recorded on both an SOE and time history recorder.
(4): Act epteble recorder options are: (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
we- w -vw--w ww - ----,, y -- -, w w,,