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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:INCOMING CORRESPONDENCE
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 ML17241A4811999-10-0101 October 1999 Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a 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 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 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 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 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) 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 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 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 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 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 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 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 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 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 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 ML17229B0851999-04-0505 April 1999 Requests Approval of Encl Relief Request 25 Which Proposes to Use Alternative Requirements of ASME Code Case N-613 in Lieu of Requirements of ASME Section XI Figures IWB-2500-7(a) & IWB-2500-7(b).Action Requested by Aug 1999 ML17309A9791999-03-31031 March 1999 Forwards Revised EPIPs Including Rev 2 to EPIP-00,rev 2 to EPIP-09,rev 2 to EPIP-10 & Rev 10 to HP-207.Summary of Revs Listed ML17309A9761999-03-23023 March 1999 Forwards Revised Epips,Including Rev 4 to EPIP-03, Er Organization Notification/Staff Augmentation, Rev 3 to EPIP-05, Activation & Operation of OSC & Rev 14 to HP-200, HP Emergency Organization. Changes to Epips,Discussed ML17229B0691999-03-19019 March 1999 Transmits TS Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity,Per Soluble Boron Credit ML17229B0721999-03-16016 March 1999 Requests Approval of Enclosed Relief Requests 23 & 24 Re ISI Plan for Second ten-year Interval.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML17229B0481999-03-10010 March 1999 Informs That Util Delivered Matls Requested in Encl 1 of NRC Ltr by Hand on 990308,as Requested by NRC Ltr Dtd 990218 1999-09-25
[Table view] Category:UTILITY TO NRC
MONTHYEARML17223A9401990-09-13013 September 1990 Forwards Evaluation of Potential Safety Impact of Failed Control Element Assemblies on Limiting Transients for Facility ML17223A9341990-09-10010 September 1990 Forwards Addl Info Re Generic Implications & Resolution of Control Element Assembly (CEA) Failure at Facility,Per NRC Request.Description of Testing Program for Old Style CEAs in Unit 1 Core Encl L-90-315, Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 81990-08-30030 August 1990 Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 8 ML17223A9201990-08-28028 August 1990 Forwards Forms NIS-1 & NIS-2, Owners Rept for Inservice Insps as Required by Provisions of ASME Code Rules, Per 900725 Ltr ML17223A8911990-08-20020 August 1990 Forwards Corrected Monthly Operating Repts for Jul 1990 for St Lucie Units 1 & 2 & Summary of Operating Experience ML17348A5041990-08-17017 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990 L-90-301, Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant1990-08-16016 August 1990 Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant ML17223A8751990-08-0909 August 1990 Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor IR 05000335/19900141990-08-0909 August 1990 Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor ML17348A4701990-07-27027 July 1990 Forwards Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per Unsatisfactory Performance Testing ML17223A8621990-07-25025 July 1990 Advises That NIS-1 & NIS-2 Forms,As Part of Inservice Insp Rept,Will Be Submitted by 900831 ML17348A4281990-07-25025 July 1990 Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b) ML17223A8631990-07-25025 July 1990 Submits Addl Info Re Implementation of Programmed Enhancements Per Generic Ltr 88-17, Loss of Dhr. All Mods for Unit 1 Completed & Operational.Mods for Unit 2 Schedule for Upcoming Refueling Outage L-90-271, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders1990-07-20020 July 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders ML17223A8581990-07-19019 July 1990 Forwards Implementation Status of 10CFR50.62 Mod at Facility Re Requirements for Reduction of Risk from ATWS Events for Light Water Cooled Nuclear Power Plants ML17223A8491990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Transmitters Models 1153 Series B,1153 Series D & 1154 Mfg Prior to 890711 Supplied by Different Vendor ML17223A8521990-07-17017 July 1990 Forwards Addl Info Requested Re Generic Implications & Resolution of Control Element Assembly Failure at Plant.Encl Confirms Util Intent to Follow C-E Regulatory Response Group Action Program IR 05000335/19900131990-07-0909 July 1990 Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements ML17223A8421990-07-0909 July 1990 Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements ML17348A3881990-07-0505 July 1990 Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs ML17223A8391990-07-0303 July 1990 Forwards Results of Beach Survey Procedure & Reduction of Field Survey Data,Per Tech Spec 4.7.6.1.1.Unit 1 Updated Fsar,Section 2.4.2.2,concluded That Dune Condition Acceptable Per Tech Spec 5.1.3 ML17223A8381990-07-0202 July 1990 Requests Termination of Operator License for s Lavelle.Util Also Requests That Ltr Be Withheld (Ref 10CFR2.790) L-90-239, Forwards Rev 6 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990 Forwards Rev 6 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21) ML17223A8371990-06-27027 June 1990 Provides Details of Implementation Plan Re Recommendations & Schedular Requirements in Generic Ltr 89-10,per 891228 Ltr.Design Basis Review of safety-related motor-operated Valves & Determination of Switch Settings in Progress ML17308A4981990-06-27027 June 1990 Responds to Generic Ltr 90-04 Re Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML17223A8341990-06-19019 June 1990 Forwards Corrected Proposed Tech Spec Figure 3.4-2 Per 900207 Application for Amend to License NPF-16,incorporating Revised Pressure/Temp Limits & Results of Revised Low Temp Overpressure Protection Analysis Into Tech Specs ML17223A8241990-06-18018 June 1990 Forwards Revised Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1988. ML17223A8271990-06-18018 June 1990 Forwards Ma Smith 900601 Ltr to WR Cunningham of EPA Requesting Mod to Plant NPDES Permit to Permit Cleaning of Facility & to Establish Discharge Limits for Chemical Cleaning Wastes ML17348A2981990-06-12012 June 1990 Forwards Rev 16 to Topical QA Rept. ML17223A6761990-05-31031 May 1990 Advises That Air Operated safety-related Components Will Perform All Design Basis Events,Per 881227 Ltr.All Actions Required by Generic Ltr 88-14 Complete for Plant ML17348A2651990-05-29029 May 1990 Submits Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per 10CFR26,App A.2.8(e)(4) ML17223A6741990-05-22022 May 1990 Forwards Info Re Status of 10CFR50.62 Mods to Meet ATWS Requirements as of 900515.Plant Change/Mod Package Necessary for Installing ATWS Will Be Issued by 900630.Hardware Procurement for Diverse Scram Sys Approx 90% Complete ML17223A6361990-05-0808 May 1990 Forwards Final Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. One Untraceable Circuit Breaker Installed in Unit 2 Qualified SPDS & Replaced W/Traceable Breaker ML17223A6281990-04-21021 April 1990 Forwards St Lucie Unit 2 Annual Environ Operating Rept, Vol 1 1989. ML17223A6081990-04-13013 April 1990 Responds to Violations Noted in Insp Repts 50-335/90-02 & 50-389/90-02.Corrective Actions:Nuclear Plant Supervisor Required to Remain in Control Room During Significant Changes in Power Operation & Preventive Maint Upgraded ML17223A6071990-04-0505 April 1990 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. Removal & Replacement of Cold Leg Side Plugs of Heat Number 3513 for Unit 1 Completed During Refueling Outage ML17308A4911990-04-0202 April 1990 Forwards Description & Summary of Safety Evaluations of Plant Changes/Mods Reportable Per 10CFR50.59.Repair &/Or Replacement of Protective Coatings on Surfaces Inside Bldg Pose No Unreviewed Safety Question ML17223A5931990-03-30030 March 1990 Forwards Status of 10CFR50.62, Requirements for Reduction of Risk from ATWS Mods at Plant as of 900315.Diverse Scram Sys Module Prototype Fabrication in Progress ML17223A5921990-03-27027 March 1990 Forwards Addl Info on Proposed License Amend Re Increased Max Allowable Resistance Temp Detector Delay Time,Per 891219 Telcon & Advises That Util Request to Increase Plant Resistance Temp Detector Response Time Remain Unchanged ML17223A5831990-03-19019 March 1990 Forwards Response to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implications of Control Sys in LWR Nuclear Power Plants,' Per 10CFR50.54(f) ML17347B6191990-03-13013 March 1990 Provides Listing of Property Insurance Programs ML17223A5531990-03-0909 March 1990 Submits Results of Investigation of Error Detected in Dose Assessment During 900124 NRC Evaluated Exercise at Plant. Operator Error Caused Keyboard Hangup Requiring Computer Restart ML17223A5451990-03-0808 March 1990 Forwards Revised Tech Specs Re Steam Generator Tube Repairs, Per 890602 Telcon & Subsequent Discussions W/Nrc ML17308A4871990-03-0707 March 1990 Forwards Response to Eight Audit Questions & Licensing Bases Criteria to Resolve Station Blackout Issue.Util Currently Has Procedures to Mitigate Effects of Hurricanes & Tornados Which Meet or Exceed NUMARC 87-00 Guidelines ML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML17347B6031990-02-27027 February 1990 Requests Approval to Use Code Case N-468 at Plants ML17223A5321990-02-26026 February 1990 Forwards CEN-396 (L)-NP, Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2. ML20012A0011990-02-26026 February 1990 Notifies That Followup Actions Completed on Schedule & Incorporated Into Rev 25 to Plant Physical Security Plan,Per NRC 890605 Request ML17223A5411990-02-26026 February 1990 Provides Addl Info Re Proposed License Amends Re Moderator Temp Coefficient Surveillance Requirements,Per 891026 & 900109 Telcons IR 05000335/19890241990-02-22022 February 1990 Responds to Violations Noted in Insp Repts 50-335/89-24 & 50-389/89-24.Corrective Actions:Applicable Procedures Changed to Clarify Which Spaces & Blocks Required to Be Completed on Plant Work Order & QC Supervisor Counseled 1990-09-13
[Table view] |
Text
REGULATOR r INFORMATION'ISTR'IBUTION b STE<<l. (RIDS)
ACCESSIOVi NBR:8110280126'OC,DATE(: 81/10/22 NOTARIZED:: NO DOCKE(T FACIL(:50 389 St<+ Lucie Plantg Unit 2~. Florida Power L Liight Co,, 0'5000389 AUTH(. NAME( AUTHOR AFFIL'IAT(ION UHRI 9 g R, E'; Flor<ida Power (( Light Co.
REC IP ~ VARE( RECiIPZENT AFFIL<IATIO<V EiISE<VHUTrr DiG,, Divisi on of Li censing
SUBJECT:
- Forwards response to C'or e Per f ormance( Branch request>> fori addi info re( instrumentation< to detect" conditions of inadequate core< cooling.Updated< info in responsei to 811019 teilconi encl, DISTRIBUTION CODE(: 80016 COPIES RECEa VED:LiTR ENCL( SIZE~:
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FLORIDA POWER & LIGHT COMPANY October 22, 1981 L-81-463 Office of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 eE
/(() ,
Dear Mr. Eisenhut:
Re: St. Lucie Unit 2 Docket No. 50-389 Requests for Additional Information Inade uate Core Coolin Instrumentation Attached is Florida Power 8 Light Company's .'response to a Core Performance Branch request for additional information concerning instrumentation to detect conditions of inadequate core cooling. Also attached is additional and updated information on the same. subject requested by the NRC staff during a telephone conversation on October 19, 1981 between J. Westhoven (C-E), R. Gritz (FPL), V. Nerses (NRC), and T. Huang (NRC). The attached information should close out this item for St. Lucie Unit 2. Should you have any additional questions, please call us.
'ery truly yours, ert E. Uhrig Vice President Advanced Systems 8 Technology REU/TCG/ah Attachments cc: J. P. O'Reilly, Director, Region II (w/o attachments)
Harold F. Reis, Esquire (w/o attachments) goo I Bii0280i2h Sii0 2t~
PDR ADQCK 0500 89)
A DR/
PEOPLE... SERVING PEOPLE
PT~C~NT Response to NRC Questions on Inadequate Core Cooling Instrumentation
ATTACHMENT A Res onse to NRC estions on Inade uate Core Coolin Instrumentation (1'-13) Responses to questions (1-13) were responded to on a generic basis by 'the C-E Owners Group. These responses were provided in CEN-181-P, "Generic Responses to NRC Questions on. the C-E Inadequate Core Cooling Instrumentation", which was transmitted in a letter from K. P. Baskin (Chair-man C-E Owners Group 1 to D.M. Crutchfield dated September 15, 1981. That letter also transmitted CEN-185, Documentation of Inadequate Core Cooling Instrumentation for Combustion Engineering Nuclear. Steam Supply Systems",
which is applicable to the St. Lucie-2 ICC .instrumentation.
4 Question 14: Describe how the processor tests operate to'etermine that the.
sensor outputs are within range. How are the ranges selectedf Response: Analog signals are converted to digital form through a 12 bit resolution A/D converter. The input electrical ranges are preprogrammed to 0-10V, 1-5V, 4-20 ma, 10-50 ma, and a range suitable for Type K thermocouples.
Functionally, the analog signals are first converted into volts, then scaled to engineering units. The input variable is then compared to upper and lower out of range values to detect out of range inputs. If the variable is out of range, the display will clearly identify the variable as out of range. The out of range variables will be eliminated from algorithms.
Question 15: Describe the display measurement units.
Response: The primary ICC display will be in the Critical Function Monitoring System. However, the QSPDS display will present the measured variables in engineering units. The engineering units will be in units most directly describiqg the process. For the ICC detection variables, the following units will be used:
FUNCTION UNITS
- 1. Saturation/Subcooled Margin - 'F of PSIA (subcooled or superheat)
Inputs 'F or PSIA
- 2. Reactor Vessel Level Above % height above the core and the Core discrete level displays Inputs oF
- 3. Core Exit Thermocouple oF Temperature
Question 16: Describe which parameter or parameters would need to be calculated from the sensor inputs. The description of the QSODS implies that such a calculation might or might not be required. When would it be required'hen would it not be requiredl Response: The following ICC detection parameters or variables require calculation from sensor inputs:
- 1. Saturation or subcooled margin The maximum of the temperature inputs and the minimum of the pressure inputs are compared to the saturation temperature or'ressure to determine the temperature and pressure margin to saturation. Superheat will.
be calculated up to the difference between the range of the inputs and the saturation temperature.
- 2. Reactor vessel level above the core The HJTC sensor dif-ferential temperature and the unheated temperature are compared to,setpoints to determine if a liquid covered or uncovered con-dition exists at each sensor location. The corresponding level output is directly related to the number of sensors that detect liquid or an uncovered state.
- 3. Representative core ex'it". thermocouple temperature A tem-perature will be calculated to represent the number of core exit thermocouple temperatures across the core. This calcula-tion has not been determined yet. It is anticipated to be an average calculation such as the averaging of the five highest temperatures.
Question 17: Specifically, describe the automatic on-line surveillance tests.
Response: The following on-line surveillance tests are performed in the QSPDS:
- 1. The temperature inside the QSPDS cabinet with a cooling system alarm on high temperature.
- 2. Power failure to the processor with alarm on failure.
- 3. Bad sensors and broken communication links with indication on the display.
- 4. CPU memory'heck and data communication checks with alarm and indication on the plasma display and digital panel meter on the cabinet. (These checks are performed periodically.)
- 5. Alalog input offset voltage with compensation performed automatically.
- 6. Inputs out of range with alarm (see Question 14).
- 7. Low HJTCS differential temperature with alarm.
Question 18: Describe the manual on-line diagnostic capability and procedures.
Response: The automatic on-line surveillance tests replace the need for a manual initiated on-line or off-line diagnostic test to be per-for'med by the, computer. A page displaying the status of the automatic surveillance tests will be provided to aid operator diagnostics.
Additionally, the following manual test capabilities are included in the design:
- 1. Calibration of the A/D'boards (with automatic offset voltage compensation).
- 2. Reset of the system.
Question 19: Discuss the predetermined setpoint for the heated junction ther-mocouple signals and how it will be selected.
Response: A setpoint on each of two inputs determines the presence or absence of liquid at each HJTC senor location:
- 1. Differential temperature between the unheated and heated HJTC junctions, and
- 2. Unheated HJTC junction temperature.
When either of these two input temperatures exceeds the setpoint for the respective input temperature, the logic indicates that the li'quid level has dropped to a level lower than the sensor location.
The setpoint values are predetermined and are installed as part of the level logic software. The differential temperature setpoint is calculated (based on tests) to be low enough to obtain a good response time but high enough to assure liquid is not present.
The unheated junction temperature setpoint is calculated to assure that liquid is not present at the sensor position.
ATTACHMENT ."B" Draft Responses to Appendix 1.9B
Section 3.1.1 Replacement 3.1.1 SATURATION MARGIN Saturation Margin Monitoring (SMM) provides information to the reactor operator on (1) the approach to and existence of saturation and (2) existence o'f core uncovery.
The SMM includes inputs from RCS cold and hot leg temperatures measured by" RTDs, the temperature of the maximum of the top three Unheated Junction Thermocouples (UHJTC), representative core exit temperature, and pressurizer pressure sensors. The UHJTC input comes from the output of the HJTCS pro-cessing units. In summary,'he sensor inputs are'as follows:
~1n nt ~Ren e Pressurizer Pressure 0-3000 p5ia Cold Leg Temperature 0-710'F Hot Leg Temperature 0-710'F Maximum UHJTC Temperature of top three 200-2300'F sensors (from HJTC processing)
Representative CET Temperature 200-2300'F
3.2 DESCRIPTION
OF ICC PROCESSING The following sections provide a preliminary description of the processing control and display functions associated with each of the ICC detection instru-ments in the AMS. The sensor inputs for the major ICC parameters; satura-tion margin, reactor vessel inventory/temperature above the core, and core exit temperature are processed in the two channel QSPDS and transmitted to the Safety'ssessment System for primary display and trending.
3.2.1 SATURATION MARGIN The QSPDS processing equipment will perform the following saturation margin monitoring functions:
- 1. Calculate the saturation margin The saturation temperature is calculated from the minimum pressure input. The temperature subcooled or superheat margin is the difference between saturation temperature and the sensor temperature input. Three temperatures subcooled or superheat margin presentations will be avail-able. These are as follows:
- a. RCS saturation margin the temperature saturation margin based
,on the difference between the saturation temperature and the maximum temperature from the RTDs in the hot and cold legs.
- b. Upper head saturation margin temperature saturation margin based on the difference between the saturation temperature and the UHJTC temperature (based on the maximum of the top three
, UHJTC).
Cs CET saturation margin temperature saturation margin based the difference between the saturation temperature and the representa-tion core exit, temperature calculated from the CETs (Section 2.2.3).
- 2. Process sensor outputs for determination of temperature saturation margin.
- 3. Provide an alarm output for an. annunciator when temperature saturation margin reaches a preslected setpoint (expected to be within O'F to subcool'ed) for RCS or upper head saturation margin. CET satura- '0'F tion margin is not alarmed to avoid possible spurious alarms.
3 2' HEATED JUNCTION THEMOCOUPLE The gSPDS processing equipment performs the following functions for the HJTC:
r
- 1. Determine collapsed liquid level above core.
The heated and unheated thermocouples in the HJTC are connected in such a way that absolute and differential temperature signals are available. This is shown in Figure 2-6. When liquid ~ater surrounds the thermocouples, their temperature and voltage outputs are approxi-mately equal. The voltage V(A C), on Figure 2-6 is therefore, approxi-mately zero. ln the absence of liquid, the thermocouple temperatures".and output voltage become unequal, causing VgACq to:rise. When V of the individual HJTC rises above a predetermined setpoint, liquid inventory does not exist at this HJTC position.
- 2. Determine the maximum upper plenum/head fluid temperature of the top three unheated thermocouples for use as an output to the SMM calcula-.
tion. (The temperature processing range is from 100'F to 2300'F).
- 3. Process input signals to display collapsed liquid level and unheated junction thermocouple temperatures.
- 4. Provide an alarm output 'when any of the HJTC detects the absence of liquid level.
- 5. Provide control of heater power for proper HJTC output signal level.
Figure 2-7 shows the design for one of the two channels which includes the heater controller power supplies.
3.2.3 CORE EXIT THERMOCOUPLE SYSTEM The QSPDS performs the following CET processing functions:
- 1. Process core exit: thermocouple inputs for display.
- 2. Calculate a representative core exit temperature. .Although not final-ized, this temperature will be either the maximum valid core exit temperature or the average of. the five highest valid core exit tem-peratures.
- 3. Provide an alarm output when temperature reaches a preselected value.
I
- 4. Process CETs for display of CET temperature and superheat.
These functions are intended to meet the design requirements of NUREG-0737, II.F.2. Attachment l.
3.3 SYSTEM DISPLAY, The ICC detection instrumentation displays in both the SAS (primary displays) and the QSPDS (backup displays) have an ICC summary page as part of the core.
heat removal control critical function supported by more detailed display pages for each of the ICC variable categories.
The summary page will include:
- 1. RCS/Upper Head saturation margin the maximum of the RCS and Upp'er Head saturation margin.
- 2. Reactor vessel .level above the core.
- 3. Representative coie exit temperature.
I Since the SAS has more display capabilities than the QSPDS such as col,or-graphics, trending, and a larger format, additional information may be added and with a better presentation than is available with the QSPDS. These variables are incorporated in other SAS system displays.
Since the SAS receives both QSPDS channels of ICC input, the SAS displays both channels of ICC information. The QSPDS displays only one channel of ICC information for each video display unit.
. Although all inputs are accessible for trending and historical recall, the SAS has a dedicated ICC trend page for RCS/upper head saturation margin, reactor vessel level, and representative core exit temperature and core exit saturation margin. These are also available as analog outputs from the QSPDS cabinet. t Each QSPDS safety grade backup display also has available the most reliable basic information for each of the ICC instruments. These displays are human engineered to give. the operator clear'nambiguous indications. The backup displays are designed:
- 1. To give instrument indications in the remote chance that the primary becomes inoperable. 'isplay
- 2. To provide confirmatory indications. to the primary display.
- 3. To aid in 'surveillance tests and diagnostics.
The following sections describe displays as presently conceived for each of the ICC instrument systems. Both primary and backup displays are in-tended to be designed consistent with the criteria in II.F.2 Attachment 1 and Appendix B.
3.3.1 .
SATURATION MARGIN DISPLAY The following information- is presented on the primary SAS and backup (QSPDS) displays:
Temperature and pressure saturation margins for RCS, Upper Head, Core Exit Temperature.
- 2. Temperatures and pressure inputs.
3.3.2 HEATED JUNCTION THERMOCOUPLE SYSTEM DISPLAY The following information is displayed on the CFMS and QSPDS displays:
Liuqid inventory level above the fuel alignment plate derived from the eight discrete HJTC positions.
- 2. 8 discrete HJTC positions indicating liquid inventory above the fuel alignment plate.
- 3. ,Inputs from the HJTCS:
- a. Unheated )unction temperature at the 8 positions.
- b. Heated )unction temperature at the 8 positions.
- c. Differential junction temperature at the 8 positions.
2.3.4. CORE EXIT THERMOCOUPLE'DISPLAY The following information is displayed on the SAS display:
A spatially oriented core map indicating the temperature at each of the CET's.
- 2. A selective re'ading of CET temperatures.
- 3. The representative core exit temperature.
The following information is displayed on the QSPDS display:
Representative. core exit temperature. ~
- 2. A selective reading of the CET temperatures (two highest tempera-tures in each quadrant)
- 3. A listing of all core exit temperatures.
Replacement Section 5.0 . SYSTEM UALIFICATION The qualification program for St. Lucie-2 ICC. instrumentation will be based on the following three categories of ICC instruments:
- 1. Sensor instrumentation within the pressure vessel.
- 2. Instrumentation components and systems which extend from the primary pressure boundary up to and including the primary display isolator and including the backup displays.
- 3. Instrumentation systems which comprise the primary display
~
equipment.
The in-vessel sensors represent the best equip'ment available consistent with qualification 'and schedular: requirements (as per NUREG-0737, Appendix B). Design of the equipment will be consistent with current in-dustry practices in 'this area. Specifically, instrumentation will be designed such that they meet appropriate stress criteria when subjected to normal and design basis accident loadings. Seismic qualification to safe shutdown conditions will verify function after being subjected to the seismic loadings.
The out-of-vessel instrumentation system, up to and including the primary display isolator, and the backup displays will be environmentally qualified in accordance with IEEE-323-1974. Plant-specific containment temperature and pressure design profiles will be used where appropriate in these tests.
This equipment will also be seismically qualifed according to IEEE-STD-344-1975. CEN-99(S), "Seismic Qualification of NSSS Supplied Instrumentation
Equipment, Combustion Engineering, Inc." (August 1978) describes the methods used to meet the criteria of this document.
FPSL is evaluating what is required to augment the out-. of-vessel Class 1E instrumentation equipment qualification program to NUREG-0588. Consistent with Appendix.B of NUREG-0737, the out-of-vessel equipment under. procurement is the best available equipment. FPL expects to complete this evaluation by the end of the first quarter of 1982.
Revision to Section 6.2 PROTOTYPE TESTING The Phase 3 test program will consist of high temperature and pressure test-ing of the manufactuied prototype system HJTC probe assembly and processing electronics. Verification of, the HJTC system prototype will be the goal of this test program. The Phase 3 test program is expected, to be completed by the end of the first charter of 1982.
Revision to Setion 9.0 SCHEDULE FOR'ICC INSTRUMENTATION"INSTALLATION
'E Flordia Power and Light is actively pursuing, procuring and expediting equipment necessary.to implement requirements for THI item II.F.2, "Instrumentation for Inadequate Core Cooling". However, this commitment is predicated upon manufacturers and.vendors meeting their scheduled delivery promises. When firmschedules are developed FPL will inform NRC of the most probable implementation date.
APPENDIX 1.9B Section 10 Will Be Deleted Replacement Table I.9B-2 TABLE'1.9B-2 EVALUATION OF ICC'DETECTION INSTRUMENTATION TO DOCUMENTATION RE UIREMENTS OF NUREG-0737 ITEM II.F.2 ITEM- RESPONSE 1 oa ~ Description of the ICC Detection Instrumentation is provided in Section 3.0. The instrumentation to be added includes'.the modified SMM, the HJTC Probe Assemblies, and Improved ICI (CET) Detector Assemblies.
/
l.b. The instrumentation described in Section 2.0'ill be the ICC detection instrumentation design for FPL.
lac ~ The planned modifications to the existing Unit 2 instrumentation will be made prior to fuel load. Modifications include changes to the SMM, design, procurement and installation of the HJTC probe assemblies, and improved ICI Detector Assemblies (which necessitate installation of improved ICI Nozzle Flanges). The final ICC Detection Instrumentation. willbe as described in Sec-tion 3.0.
- 2. The design analysis and evaluation of the ICC Detection Instru-mentation is discussed in Sections 2.0 and 4.0. and Appendix A.
Testing is discussed in .Section 6.0.
- 3. The HJTCS has one remaining test phase. The Phase 3 test program will consist of high temperature and pressure testing of a manufactured production prototype system HJTC probe as-sembly and processing electronics. The Phase 3 test program will be executed at the C-E test facility used for the Phaseof 2 test and is expected to be completed by the first quarter 1982.
No special verification or experimental tests are planned for the hot leg and cold leg RTD sensors, the pressurizer pressure sensors, or the Type K (chromel-alumel) core exit thermocouples since they are standard high quality nuclear instruments with well known responses.
For qualification testing, all out-of-vessel sensors and equip-ment, including the QSPDS up to and including the isolation to the SAS, will be environmentally qualified to IEE Std. 323-1974 as interpreted to CENPD-255 Rev. Ol, "Qualification of C-E Instru-
" ments", as interpreted by CENPD-182, and seismically, qualified to IEEE STd. 344-1975, "Seismic Qualification of C-E Instrumen-tation Equipment". The qualification to NUREG-0588 is being addressed by the C-E Owners'roup (See the response to item 1 in Table 3 for more information).
Table 1.9B-2 Continued Necessary augmenting of out of vessel class 1E instrumentation to NUREG-0588 requirements will be addressed by the FPL evala-tion to be completed by the end of the first quarter of 1982.
4~ This table evaluates the ICC Detection Instrumentation's con-formance to the NUREG-0737, Item II.F.2 documentation require-ments. Table 1.9B-3 evaluated conformance to Attachement 1 of Item II.F.2 Table 1.9B-4 evaluates conformance to Appendix B of NUREG-0737.
- 5. The ICC detection instrumentation processing and display con-sists of two computer systems; the 2 redundant channel safety grade microcomputer based QSPDS, and the SAS. The ICC inputs are acquired and processed by the safety grade QSPDS and isolated and transmitted to the. primary display in the SAS. The QSPDS also has the seismically qualified backup displays for the ICC detection instruments. The software functions for processing are listed in Section 3.2, the functions for display are listed in Section 3.3.
The software for the QSPDS is being designed consistent to the recommendations of the draft standard, IEEE std. P742/ANS 4.3.2, "Criteria for the Application of Programmable Digital Computer Systems in the Safety Systems of Nuclear Power Gener-ating Stations". This design procedure verifies and validates that the QSPDS software is properly implemented and integrated with the system hardware to meet the system's functional require-ments. This procedure is quality assured by means of the C-E QADP; Since C-E has designed the only licensed safety grade digital computer system in the nuclear industry, C-E has the facilities and experience to design reliable computer systems.
The QSPDS hardware is designed as a redundant safety grade qualified computer system which is designed to the unava'il-ability goal of 0.01 with the appropriate spare parts and main-tenance support.
- 6. Section 9.0 discusses the schedule for installation and imple-mentation of the complete ICC Detection Instrumentation.
- 7. Guidelines for use of the ICC Detection Instrumentation "are discussed in Section 7.0.
A future amendment will discuss key operator actions in the current emergency procedures for ICC. The ammendment will be submitted prior to fuel load. Section 7.0 discusses the emer-gency procedures to be implemented upon incorporation of the complete ICC Detection System,
Table 1.9B-2 Continued
- 9. The following describes additional submittals that will be provided to support the acceptability of the final ICC Detec-tion Instrumentation.
- 1) Environmental 'and Seismic Qualification of the instru-mentation equipment. Additional evaluation to NUREG-
~
0588 will be provided by June 1982.
- 2) Modifications to emergency procedures (prior to fuel load)
- 3) , Changes to Technical Specifications (prior to fuel load)
TABLE '.'B-3 EVALUATION OF ICC'DETECTION INSTRUMENTATION TO ATTACHMENT 1 of II.F.2 ITEM RESPONSE St. Lucie 2 has 56 core exit thermocouples (CETs) distributed uniformly over the top of the core, Section 3.1.3 has a dis-cription of the CET sensors, Figure 1.9B-7 depicts the locations of the CETs.
2." ,The SAS meets the primary display requirements for CET tem-peiatures.
2 ~ 'a ~ A spatial CET temperature map is available on demand.
2.b. A selective representative CET temperature will be displayed continuously on demand. Although not finalized, this tempera-ture will be either the maximum CET temperature or the average of the five highest CET temperatures.
2 ~ c ~, The SAS provides direct readout of CET temperature with a de-dicated display page. The line printer provides the hardcopy.
capability 'for recording CET temperatures.
A 2.d. The SAS has an extensive trend and historical data storage and retrieval system. The historical data storage and retrieval system functionallows all ICC inputs to be recorded, stored, and recalled by the operator. The:operator (and other user stations) can 'graphically trend any CET value on the display screen. A dedicated ICC trend page which includes the representative CET temperature and representative CET saturation margin will be accessible to the users.
2~e~ The SAS has alarm capabilities and visually displayed value alarms on the system level pages.
2.f. The SAS is. an extensively human-factor designed display system which allows quick access to requested displays.
3~ ICC instrumentation QSPDS design incorporates a minimum of one backup display with the capability of selective reading of a minimum of 16 operable Thermocouples, 4 from each quadrant.
All CET temperatures can be displayed within 5 minutes.
- 4. The types and locations of displays and alarms are determined for, the primary display by performing a human-factors analysis.
The QSPDS also incorporates human factors engineering. The use of these display systems will be addressed in operating proce-dures, emergency procedures, and op'erator training.
5~ The ICC instrumentation was evaluated for conformance to Appendix B of NUREG-0737 (see Table 1.9B-4).
Table 1.9B-3 Continued
- 6. The QSPDS channels are Class lE, electrically independent, energized from independent station Class lE power sources and physically. separated in accordance with Regulatory Guide 1..75 "Physical Independence of Electric Systems" January 1975 (Rl) up to and including the isolation devices.
7~ ICC instrumentation shall be environmentally qualified pursuant to C-E owners group qualification program. The isolation de-vices in the QSPDS are accessible for maintenance following an accident.
- 8. Primary and backup display channels are designed to provide the highest availability possible. The QSPDS.is designed to provide 99% availability. The availability of the QSPDS will be addressed in the Technical S'pecifications.
- 9. The quality assurance provisions of Appendix B, Item 5, will be applied to the ICC detection instruments as described in the Appendix B evaluation in Table 1.9B-4.
Revision to Table 1-9B-4 ITEM RESPONSE
- 5. 1.144 "Auditing of Quality Assurance Programs for Nuclear Power Plants"..
- 6. The ICC detection instrumentation outputs are continuously avail-able on the QSPDS displays through manual callup of displays. through manual callup of 'displays. Additionally, one channel of analog trend
,,;recording will continuously indicate the ICC summary variables.
~
- 7. The ICC instrumentation is designed to provide readout display and trending information to the opeartor through the SAS and analog trend recording of the ICC summary variables.
(See Section 3.3);
- 8. The inadequate. core cooling instrumentation is specifically and singularly identified so that the operator can easily discern their use during an accident condition.
- 9. Transmission of signals from instruments of associated sensors between redundant IE channels or between 1E and non-1E instru-ment channels are isolated with isolation devices qualified to the provisions of Appendix B.
- 10. The QSPDS consists of two redundant channels to avoid inter-ruptions of display due to a single failure. If in the remote chance that one complete QSPDS channel fails, the operator has:
- 1) Additional channels of ICC sensor inputs for cold leg temperature, hot leg temperature, and pressuizer pres-sure on the control board separate from the QSPDS.
'2) The HJTCS and CET have multiple sensors in each channel for the operator to correlate and check inputs.
- 3) The HJTCS sensor output may be tested by the operator reading the temperature of the unheated thermocouple and comparing to other temperature indications.
- 4) Other variables are available to the operator on the Main Control Board for verifying the ICC parameter.
Servicing, testing and calibrating programs shall be consis-tent -with operating technical specifications.
- 12. The ICC instrumentation, including the QSPDS, are not intended to be removed or bypassed during operation. Administrative control will be necessary to remove power, from a channel.
- 13. The system design is su'ch as to facilitate administrative control
'of access to all setpoints adjustments, calibration adjustments and test points.
Revision to Table 1.9B-4 Continued
- 14. The QSPDS is designed to minimize anomalous indications to the operator (see section 3.3).
- 15. Instrumentation is designed to facilitate replacement of com-ponents or modules. The i'nstrumentation design is such that malfunctioning components can be identifed easily.
- 16. The design incorporates this requirement to the extent prac-tical.
- 17. The design incorporates this requirement to the extent prac-tical.
- 18. The system is designed to be capable of periodic testing of instrument channels.