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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 rINFORMATION'ISTR'IBUTION bSTE<<l.(RIDS)ACCESSIOVi NBR:8110280126'OC,DATE(:
81/10/22NOTARIZED::
NOFACIL(:50 389St<+LuciePlantgUnit2~.FloridaPowerLLiightCo,,AUTH(.NAME(AUTHORAFFIL'IAT(ION UHRI9gR,E';Flor<idaPower((LightCo.RECIP~VARE(RECiIPZENT AFFIL<IATIO<V EiISE<VHUTrr DiG,,DivisionofLicensing
SUBJECT:
ForwardsresponsetoC'orePerformance(Branchrequest>>foriaddiinfore(instrumentation<
todetect"conditions ofinadequate core<cooling.Updated<
infoinresponsei to811019teilconiencl,DISTRIBUTION CODE(:80016COPIESRECEaVED:LiTRENCL(SIZE~:
T(ITLE(:..
-PSAR'/FSAR AMDT6andRe,latedCorre'spondence
<VOTES':".DOCKE(T0'5000389 RECIPEKNT'OrCODE/t<(AMKI ACTION::A/DrLiICEVSNG L<IC(BRi(r3LAINTERNAL(:'-ELO(HUR(FACiT'NG40,ILCISYSBR16'E'/EPDS(
35i*L<IC(GUIDBR"33iNATLE'VG,BR'7MPAlNRR</DE'/EQB 13iNRR'/DSI</ASB27iVRR'/OSIS'CSB 09OPLIC8Ri34PROC/TST'EV 20.ESSBR22'.REG<IL'4<VGBR'25<EXTERNALi:
ACR641>>FE('lAREPDIV39NRC(PDRI02!NT'ISCOPIESL<TTREiVCLr1010101111111111103II311111111111111161611111RECIPIENT IDCODE/NAME L(ICBR03BC<VERSESrV.
01GEOSCIENCES 28HYD'/GEOBR30I8Ei06'E'/EPLB,36'iIC'UALr BR32'ECH'<VG BR18NRR/DE/CEB, 11=NRR/DSIi/AEB26NRR/DSI/CPB 10iVRR/DSI"/ET<8812'OWERSYSBR19QA.BR21=-REAC<SYSBR23SIT<ANAL(BR2'4BiVL(AMD'TSONLY)LPDR<03VSIC05COPIEBLq'<TR(ENCL(10.122'2'3<33<11111111111111111111111VOV01SgJ>TO<TAL<VU4lBER(
OFCOPIES'EQUIRED!:
LiTTR63ENCL(58 ePI P.o.BOX529100MIAMI,FL33152kiA~4%FLORIDAPOWER&LIGHTCOMPANYOctober22,1981L-81-463OfficeofNuclearReactorRegulation Attention:
Mr.DarrellG.Eisenhut, DirectorDivisionofLicensing U.S.NuclearRegulatory Commission Washington, D.C.20555
DearMr.Eisenhut:
eE/((),Re:St.LucieUnit2DocketNo.50-389RequestsforAdditional Information InadeuateCoreCoolinInstrumentation AttachedisFloridaPower8LightCompany's
.'response toaCorePerformance Branchrequestforadditional information concerning instrumentation todetectconditions ofinadequate corecooling.Alsoattachedisadditional andupdatedinformation onthesame.subjectrequested bytheNRCstaffduringatelephone conversation onOctober19,1981betweenJ.Westhoven (C-E),R.Gritz(FPL),V.Nerses(NRC),andT.Huang(NRC).Theattachedinformation shouldcloseoutthisitemforSt.LucieUnit2.Shouldyouhaveanyadditional questions, pleasecallus.'erytrulyyours,ertE.UhrigVicePresident AdvancedSystems8Technology REU/TCG/ah Attachments cc:J.P.O'Reilly,
- Director, RegionII(w/oattachments)
HaroldF.Reis,Esquire(w/oattachments) gooIBii0280i2h Sii02t~PDRADQCK050089)ADR/PEOPLE...
SERVINGPEOPLE PT~C~NTResponsetoNRCQuestions onInadequate CoreCoolingInstrumentation ATTACHMENT AResonsetoNRCestionsonInadeuateCoreCoolinInstrumentation (1'-13)Responses toquestions (1-13)wereresponded toonagenericbasisby'theC-EOwnersGroup.Theseresponses wereprovidedinCEN-181-P, "GenericResponses toNRCQuestions on.theC-EInadequate CoreCoolingInstrumentation",
whichwastransmitted inaletterfromK.P.Baskin(Chair-manC-EOwnersGroup1toD.M.Crutchfield datedSeptember 15,1981.Thatletteralsotransmitted CEN-185,Documentation ofInadequate CoreCoolingInstrumentation forCombustion Engineering Nuclear.SteamSupplySystems",
whichisapplicable totheSt.Lucie-2ICC.instrumentation.
Question14:4Describehowtheprocessor testsoperateto'etermine thatthe.sensoroutputsarewithinrange.Howaretherangesselectedf
Response
Analogsignalsareconverted todigitalformthrougha12bitresolution A/Dconverter.
Theinputelectrical rangesarepreprogrammed to0-10V,1-5V,4-20ma,10-50ma,andarangesuitableforTypeKthermocouples.
Functionally, theanalogsignalsarefirstconverted intovolts,thenscaledtoengineering units.Theinputvariableisthencomparedtoupperandloweroutofrangevaluestodetectoutofrangeinputs.Ifthevariableisoutofrange,thedisplaywillclearlyidentifythevariableasoutofrange.Theoutofrangevariables willbeeliminated fromalgorithms.
Question15:Describethedisplaymeasurement units.Response:
TheprimaryICCdisplaywillbeintheCriticalFunctionMonitoring System.However,theQSPDSdisplaywillpresentthemeasuredvariables inengineering units.Theengineering unitswillbeinunitsmostdirectlydescribiqg theprocess.FortheICCdetection variables, thefollowing unitswillbeused:FUNCTION1.Saturation/Subcooled MarginInputsUNITS-'FofPSIA(subcooled orsuperheat)
-'ForPSIA2.ReactorVesselLevelAbovetheCoreInputs-%heightabovethecoreanddiscreteleveldisplaysoF3.CoreExitThermocouple Temperature oF Question16:Describewhichparameter orparameters wouldneedtobecalculated fromthesensorinputs.Thedescription oftheQSODSimpliesthatsuchacalculation mightormightnotberequired.
Whenwoulditberequired'hen woulditnotberequiredl
Response
Thefollowing ICCdetection parameters orvariables requirecalculation fromsensorinputs:1.Saturation orsubcooled margin-Themaximumofthetemperature inputsandtheminimumofthepressureinputsarecomparedtothesaturation temperature or'ressure todetermine thetemperature andpressuremargintosaturation.
Superheat will.becalculated uptothedifference betweentherangeoftheinputsandthesaturation temperature.
2.Reactorvessellevelabovethecore-TheHJTCsensordif-ferential temperature andtheunheatedtemperature arecomparedto,setpoints todetermine ifaliquidcoveredoruncovered con-ditionexistsateachsensorlocation.
Thecorresponding leveloutputisdirectlyrelatedtothenumberofsensorsthatdetectliquidoranuncovered state.3.Representative coreex'it".thermocouple temperature
-Atem-peraturewillbecalculated torepresent thenumberofcoreexitthermocouple temperatures acrossthecore.Thiscalcula-tionhasnotbeendetermined yet.Itisanticipated tobeanaveragecalculation suchastheaveraging ofthefivehighesttemperatures.
Question17:Response:
Specifically, describetheautomatic on-linesurveillance tests.Thefollowing on-linesurveillance testsareperformed intheQSPDS:1.Thetemperature insidetheQSPDScabinetwithacoolingsystemalarmonhightemperature.
2.Powerfailuretotheprocessor withalarmonfailure.3.Badsensorsandbrokencommunication linkswithindication onthedisplay.4.CPUmemory'heck anddatacommunication checkswithalarmandindication ontheplasmadisplayanddigitalpanelmeteronthecabinet.(Thesechecksareperformed periodically.)
5.Alaloginputoffsetvoltagewithcompensation performed automatically.
6.Inputsoutofrangewithalarm(seeQuestion14).7.LowHJTCSdifferential temperature withalarm.
Question18:Describethemanualon-linediagnostic capability andprocedures.
Response
Theautomatic on-linesurveillance testsreplacetheneedforamanualinitiated on-lineoroff-linediagnostic testtobeper-for'medbythe,computer.
Apagedisplaying thestatusoftheautomatic surveillance testswillbeprovidedtoaidoperatordiagnostics.
Additionally, thefollowing manualtestcapabilities areincludedinthedesign:1.Calibration oftheA/D'boards (withautomatic offsetvoltagecompensation).
2.Resetofthesystem.Question19:Discussthepredetermined setpointfortheheatedjunctionther-mocouplesignalsandhowitwillbeselected.
Response
Asetpointoneachoftwoinputsdetermines thepresenceorabsenceofliquidateachHJTCsenorlocation:
1.Differential temperature betweentheunheatedandheatedHJTCjunctions, and2.UnheatedHJTCjunctiontemperature.
Wheneitherofthesetwoinputtemperatures exceedsthesetpointfortherespective inputtemperature, thelogicindicates thattheli'quidlevelhasdroppedtoalevellowerthanthesensorlocation.
Thesetpointvaluesarepredetermined andareinstalled aspartofthelevellogicsoftware.
Thedifferential temperature setpointiscalculated (basedontests)tobelowenoughtoobtainagoodresponsetimebuthighenoughtoassureliquidisnotpresent.Theunheatedjunctiontemperature setpointiscalculated toassurethatliquidisnotpresentatthesensorposition.
ATTACHMENT
."B"DraftResponses toAppendix1.9B Section3.1.1Replacement 3.1.1SATURATION MARGINSaturation MarginMonitoring (SMM)providesinformation tothereactoroperatoron(1)theapproachtoandexistence ofsaturation and(2)existence o'fcoreuncovery.
TheSMMincludesinputsfromRCScoldandhotlegtemperatures measuredby"RTDs,thetemperature ofthemaximumofthetopthreeUnheatedJunctionThermocouples (UHJTC),representative coreexittemperature, andpressurizer pressuresensors.TheUHJTCinputcomesfromtheoutputoftheHJTCSpro-cessingunits.Insummary,'he sensorinputsare'asfollows:~1nnt~RenePressurizer PressureColdLegTemperature HotLegTemperature MaximumUHJTCTemperature oftopthreesensors(fromHJTCprocessing) 0-3000p5ia0-710'F0-710'F200-2300'F Representative CETTemperature 200-2300'F 3.2DESCRIPTION OFICCPROCESSING Thefollowing sectionsprovideapreliminary description oftheprocessing controlanddisplayfunctions associated witheachoftheICCdetection instru-mentsintheAMS.ThesensorinputsforthemajorICCparameters; satura-tionmargin,reactorvesselinventory/temperature abovethecore,andcoreexittemperature areprocessed inthetwochannelQSPDSandtransmitted totheSafety'ssessment Systemforprimarydisplayandtrending.
3.2.1SATURATION MARGINTheQSPDSprocessing equipment willperformthefollowing saturation marginmonitoring functions:
1.Calculate thesaturation marginThesaturation temperature iscalculated fromtheminimumpressureinput.Thetemperature subcooled orsuperheat marginisthedifference betweensaturation temperature andthesensortemperature input.Threetemperatures subcooled orsuperheat marginpresentations willbeavail-able.Theseareasfollows:
a.RCSsaturation margin-thetemperature saturation marginbased,onthedifference betweenthesaturation temperature andthemaximumtemperature fromtheRTDsinthehotandcoldlegs.b.Upperheadsaturation margin-temperature saturation marginbasedonthedifference betweenthesaturation temperature andtheUHJTCtemperature (basedonthemaximumofthetopthree,UHJTC).CsCETsaturation margin-temperature saturation marginbasedthedifference betweenthesaturation temperature andtherepresenta-tioncoreexit,temperature calculated fromtheCETs(Section2.2.3).2.Processsensoroutputsfordetermination oftemperature saturation margin.3.Provideanalarmoutputforan.annunciator whentemperature saturation marginreachesapreslected setpoint(expected tobewithinO'Fto'0'Fsubcool'ed) forRCSorupperheadsaturation margin.CETsatura-tionmarginisnotalarmedtoavoidpossiblespuriousalarms.32'HEATEDJUNCTIONTHEMOCOUPLE ThegSPDSprocessing equipment performsthefollowing functions fortheHJTC:r1.Determine collapsed liquidlevelabovecore.Theheatedandunheatedthermocouples intheHJTCareconnected insuchawaythatabsoluteanddifferential temperature signalsareavailable.
ThisisshowninFigure2-6.Whenliquid~atersurrounds thethermocouples, theirtemperature andvoltageoutputsareapproxi-matelyequal.ThevoltageV(AC),onFigure2-6istherefore, approxi-matelyzero.lntheabsenceofliquid,thethermocouple temperatures".and outputvoltagebecomeunequal,causingVgACqto:rise.WhenVoftheindividual HJTCrisesaboveapredetermined
- setpoint, liquidinventory doesnotexistatthisHJTCposition.
2.Determine themaximumupperplenum/head fluidtemperature ofthetopthreeunheatedthermocouples foruseasanoutputtotheSMMcalcula-.
tion.(Thetemperature processing rangeisfrom100'Fto2300'F).3.Processinputsignalstodisplaycollapsed liquidlevelandunheatedjunctionthermocouple temperatures.
4.Provideanalarmoutput'whenanyoftheHJTCdetectstheabsenceofliquidlevel.
5.ProvidecontrolofheaterpowerforproperHJTCoutputsignallevel.Figure2-7showsthedesignforoneofthetwochannelswhichincludestheheatercontroller powersupplies.
3.2.3COREEXITTHERMOCOUPLE SYSTEMTheQSPDSperformsthefollowing CETprocessing functions:
1.Processcoreexit:thermocouple inputsfordisplay.2.Calculate arepresentative coreexittemperature.
.Although notfinal-ized,thistemperature willbeeitherthemaximumvalidcoreexittemperature ortheaverageof.thefivehighestvalidcoreexittem-peratures.
3.Provideanalarmoutputwhentemperature reachesapreselected value.I4.ProcessCETsfordisplayofCETtemperature andsuperheat.
Thesefunctions areintendedtomeetthedesignrequirements ofNUREG-0737, II.F.2.Attachment l.3.3SYSTEMDISPLAY,TheICCdetection instrumentation displaysinboththeSAS(primarydisplays) andtheQSPDS(backupdisplays) haveanICCsummarypageaspartofthecore.heatremovalcontrolcriticalfunctionsupported bymoredetaileddisplaypagesforeachoftheICCvariablecategories.
Thesummarypagewillinclude:1.RCS/Upper Headsaturation margin-themaximumoftheRCSandUpp'erHeadsaturation margin.2.Reactorvessel.levelabovethecore.3.Representative coieexittemperature.
ISincetheSAShasmoredisplaycapabilities thantheQSPDSsuchascol,or-graphics,
- trending, andalargerformat,additional information maybeaddedandwithabetterpresentation thanisavailable withtheQSPDS.Thesevariables areincorporated inotherSASsystemdisplays.
SincetheSASreceivesbothQSPDSchannelsofICCinput,theSASdisplaysbothchannelsofICCinformation.
TheQSPDSdisplaysonlyonechannelofICCinformation foreachvideodisplayunit.
.Althoughallinputsareaccessible fortrendingandhistorical recall,theSAShasadedicated ICCtrendpageforRCS/upper headsaturation margin,reactorvessellevel,andrepresentative coreexittemperature andcoreexitsaturation margin.Thesearealsoavailable asanalogoutputsfromtheQSPDScabinet.tEachQSPDSsafetygradebackupdisplayalsohasavailable themostreliablebasicinformation foreachoftheICCinstruments.
Thesedisplaysarehumanengineered togive.theoperatorclear'nambiguous indications.
Thebackupdisplaysaredesigned:
1.Togiveinstrument indications intheremotechancethattheprimary'isplaybecomesinoperable.
2.Toprovideconfirmatory indications.
totheprimarydisplay.3.Toaidin'surveillance testsanddiagnostics.
Thefollowing sectionsdescribedisplaysaspresently conceived foreachoftheICCinstrument systems.Bothprimaryandbackupdisplaysarein-tendedtobedesignedconsistent withthecriteriainII.F.2Attachment 1andAppendixB.3.3.1.*SATURATION MARGINDISPLAYThefollowing information-ispresented ontheprimarySASandbackup(QSPDS)displays:
Temperature andpressuresaturation marginsforRCS,UpperHead,CoreExitTemperature.
2.Temperatures andpressureinputs.3.3.2HEATEDJUNCTIONTHERMOCOUPLE SYSTEMDISPLAYThefollowing information isdisplayed ontheCFMSandQSPDSdisplays:
Liuqidinventory levelabovethefuelalignment platederivedfromtheeightdiscreteHJTCpositions.
2.8discreteHJTCpositions indicating liquidinventory abovethefuelalignment plate.3.,InputsfromtheHJTCS:a.Unheated)unctiontemperature atthe8positions.
b.Heated)unctiontemperature atthe8positions.
c.Differential junctiontemperature atthe8positions.
2.3.4.COREEXITTHERMOCOUPLE'DISPLAY Thefollowing information isdisplayed ontheSASdisplay:Aspatially orientedcoremapindicating thetemperature ateachoftheCET's.2.Aselective re'adingofCETtemperatures.
3.Therepresentative coreexittemperature.
Thefollowing information isdisplayed ontheQSPDSdisplay:2.Representative.
coreexittemperature.
~Aselective readingoftheCETtemperatures (twohighesttempera-turesineachquadrant) 3.Alistingofallcoreexittemperatures.
Replacement Section5.0.SYSTEMUALIFICATION Thequalification programforSt.Lucie-2ICC.instrumentation willbebasedonthefollowing threecategories ofICCinstruments:
1.Sensorinstrumentation withinthepressurevessel.2.Instrumentation components andsystemswhichextendfromtheprimarypressureboundaryuptoandincluding theprimarydisplayisolatorandincluding thebackupdisplays.
3.Instrumentation systemswhichcomprisetheprimarydisplay~equipment.
Thein-vessel sensorsrepresent thebestequip'ment available consistent withqualification
'andschedular:
requirements (asperNUREG-0737, AppendixB).Designoftheequipment willbeconsistent withcurrentin-dustrypractices in'thisarea.Specifically, instrumentation willbedesignedsuchthattheymeetappropriate stresscriteriawhensubjected tonormalanddesignbasisaccidentloadings.
Seismicqualification tosafeshutdownconditions willverifyfunctionafterbeingsubjected totheseismicloadings.
Theout-of-vessel instrumentation system,uptoandincluding theprimarydisplayisolator, andthebackupdisplayswillbeenvironmentally qualified inaccordance withIEEE-323-1974.
Plant-specific containment temperature andpressuredesignprofileswillbeusedwhereappropriate inthesetests.Thisequipment willalsobeseismically qualifedaccording toIEEE-STD-344-1975.CEN-99(S),
"SeismicQualification ofNSSSSuppliedInstrumentation Equipment, Combustion Engineering, Inc."(August1978)describes themethodsusedtomeetthecriteriaofthisdocument.
FPSLisevaluating whatisrequiredtoaugmenttheout-.of-vessel Class1Einstrumentation equipment qualification programtoNUREG-0588.
Consistent withAppendix.B ofNUREG-0737, theout-of-vessel equipment under.procurement isthebestavailable equipment.
FPLexpectstocompletethisevaluation bytheendofthefirstquarterof1982.RevisiontoSection6.2PROTOTYPE TESTINGThePhase3testprogramwillconsistofhightemperature andpressuretest-ingofthemanufactuied prototype systemHJTCprobeassemblyandprocessing electronics.
Verification of,theHJTCsystemprototype willbethegoalofthistestprogram.ThePhase3testprogramisexpected, tobecompleted bytheendofthefirstcharterof1982.RevisiontoSetion9.0SCHEDULEFOR'ICCINSTRUMENTATION"INSTALLATION
'EFlordiaPowerandLightisactivelypursuing, procuring andexpediting equipment necessary.to implement requirements forTHIitemII.F.2,"Instrumentation forInadequate CoreCooling".
However,thiscommitment ispredicated uponmanufacturers and.vendors meetingtheirscheduled deliverypromises.
Whenfirmschedules aredeveloped FPLwillinformNRCofthemostprobableimplementation date.
APPENDIX1.9BSection10WillBeDeleted Replacement TableI.9B-2TABLE'1.9B-2 EVALUATION OFICC'DETECTION INSTRUMENTATION TODOCUMENTATION REUIREMENTS OFNUREG-0737 ITEMII.F.2ITEM-RESPONSE1oa~l.b.Description oftheICCDetection Instrumentation isprovidedinSection3.0.Theinstrumentation tobeaddedincludes'.the modifiedSMM,theHJTCProbeAssemblies, andImprovedICI(CET)DetectorAssemblies.
/Theinstrumentation described inSection2.0'illbetheICCdetection instrumentation designforFPL.lac~Theplannedmodifications totheexistingUnit2instrumentation willbemadepriortofuelload.Modifications includechangestotheSMM,design,procurement andinstallation oftheHJTCprobeassemblies, andimprovedICIDetectorAssemblies (whichnecessitate installation ofimprovedICINozzleFlanges).
ThefinalICCDetection Instrumentation.
willbeasdescribed inSec-tion3.0.2.Thedesignanalysisandevaluation oftheICCDetection Instru-mentation isdiscussed inSections2.0and4.0.andAppendixA.Testingisdiscussed in.Section6.0.3.TheHJTCShasoneremaining testphase.ThePhase3testprogramwillconsistofhightemperature andpressuretestingofamanufactured production prototype systemHJTCprobeas-semblyandprocessing electronics.
ThePhase3testprogramwillbeexecutedattheC-EtestfacilityusedforthePhase2testandisexpectedtobecompleted bythefirstquarterof1982.Nospecialverification orexperimental testsareplannedforthehotlegandcoldlegRTDsensors,thepressurizer pressuresensors,ortheTypeK(chromel-alumel) coreexitthermocouples sincetheyarestandardhighqualitynuclearinstruments withwellknownresponses.
Forqualification testing,allout-of-vessel sensorsandequip-ment,including theQSPDSuptoandincluding theisolation totheSAS,willbeenvironmentally qualified toIEEStd.323-1974asinterpreted toCENPD-255 Rev.Ol,"Qualification ofC-EInstru-"ments",asinterpreted byCENPD-182, andseismically, qualified toIEEESTd.344-1975, "SeismicQualification ofC-EInstrumen-tationEquipment".
Thequalification toNUREG-0588 isbeingaddressed bytheC-EOwners'roup (Seetheresponsetoitem1inTable3formoreinformation).
Table1.9B-2Continued 4~Necessary augmenting ofoutofvesselclass1Einstrumentation toNUREG-0588 requirements willbeaddressed bytheFPLevala-tiontobecompleted bytheendofthefirstquarterof1982.Thistableevaluates theICCDetection Instrumentation's con-formancetotheNUREG-0737, ItemII.F.2documentation require-ments.Table1.9B-3evaluated conformance toAttachement 1ofItemII.F.2Table1.9B-4evaluates conformance toAppendixBofNUREG-0737.
5.TheICCdetection instrumentation processing anddisplaycon-sistsoftwocomputersystems;the2redundant channelsafetygrademicrocomputer basedQSPDS,andtheSAS.TheICCinputsareacquiredandprocessed bythesafetygradeQSPDSandisolatedandtransmitted tothe.primarydisplayintheSAS.TheQSPDSalsohastheseismically qualified backupdisplaysfortheICCdetection instruments.
Thesoftwarefunctions forprocessing arelistedinSection3.2,thefunctions fordisplayarelistedinSection3.3.ThesoftwarefortheQSPDSisbeingdesignedconsistent totherecommendations ofthedraftstandard, IEEEstd.P742/ANS4.3.2,"Criteria fortheApplication ofProgrammable DigitalComputerSystemsintheSafetySystemsofNuclearPowerGener-atingStations".
Thisdesignprocedure verifiesandvalidates thattheQSPDSsoftwareisproperlyimplemented andintegrated withthesystemhardwaretomeetthesystem'sfunctional require-ments.Thisprocedure isqualityassuredbymeansoftheC-EQADP;SinceC-Ehasdesignedtheonlylicensedsafetygradedigitalcomputersysteminthenuclearindustry, C-Ehasthefacilities andexperience todesignreliablecomputersystems.TheQSPDShardwareisdesignedasaredundant safetygradequalified computersystemwhichisdesignedtotheunava'il-abilitygoalof0.01withtheappropriate sparepartsandmain-tenancesupport.6.Section9.0discusses thescheduleforinstallation andimple-mentation ofthecompleteICCDetection Instrumentation.
7.Guidelines foruseoftheICCDetection Instrumentation "arediscussed inSection7.0.Afutureamendment willdiscusskeyoperatoractionsinthecurrentemergency procedures forICC.Theammendment willbesubmitted priortofuelload.Section7.0discusses theemer-gencyprocedures tobeimplemented uponincorporation ofthecompleteICCDetection
- System, Table1.9B-2Continued 9.Thefollowing describes additional submittals thatwillbeprovidedtosupporttheacceptability ofthefinalICCDetec-tionInstrumentation.
1)Environmental
'andSeismicQualification oftheinstru-mentation equipment.
Additional evaluation toNUREG-~0588willbeprovidedbyJune1982.2)Modifications toemergency procedures (priortofuelload)3),ChangestoTechnical Specifications (priortofuelload)
TABLE'.'B-3EVALUATION OFICC'DETECTION INSTRUMENTATION TOATTACHMENT 1ofII.F.2ITEMRESPONSESt.Lucie2has56coreexitthermocouples (CETs)distributed uniformly overthetopofthecore,Section3.1.3hasadis-criptionoftheCETsensors,Figure1.9B-7depictsthelocations oftheCETs.2.",TheSASmeetstheprimarydisplayrequirements forCETtem-peiatures.
2~'a~AspatialCETtemperature mapisavailable ondemand.2.b.Aselective representative CETtemperature willbedisplayed continuously ondemand.Althoughnotfinalized, thistempera-turewillbeeitherthemaximumCETtemperature ortheaverageofthefivehighestCETtemperatures.
2~c~,2.d.TheSASprovidesdirectreadoutofCETtemperature withade-dicateddisplaypage.Thelineprinterprovidesthehardcopy.
capability
'forrecording CETtemperatures.
ATheSAShasanextensive trendandhistorical datastorageandretrieval system.Thehistorical datastorageandretrieval systemfunctionallows allICCinputstoberecorded, stored,andrecalledbytheoperator.
The:operator (andotheruserstations) can'graphically trendanyCETvalueonthedisplayscreen.Adedicated ICCtrendpagewhichincludestherepresentative CETtemperature andrepresentative CETsaturation marginwillbeaccessible totheusers.2~e~TheSAShasalarmcapabilities andvisuallydisplayed valuealarmsonthesystemlevelpages.2.f.TheSASis.anextensively human-factor designeddisplaysystemwhichallowsquickaccesstorequested displays.
3~ICCinstrumentation QSPDSdesignincorporates aminimumofonebackupdisplaywiththecapability ofselective readingofaminimumof16operableThermocouples, 4fromeachquadrant.
AllCETtemperatures canbedisplayed within5minutes.4.5~Thetypesandlocations ofdisplaysandalarmsaredetermined for,theprimarydisplaybyperforming ahuman-factors analysis.
TheQSPDSalsoincorporates humanfactorsengineering.
Theuseofthesedisplaysystemswillbeaddressed inoperating proce-dures,emergency procedures, andop'erator training.
TheICCinstrumentation wasevaluated forconformance toAppendixBofNUREG-0737 (seeTable1.9B-4).
Table1.9B-3Continued 6.TheQSPDSchannelsareClasslE,electrically independent, energized fromindependent stationClasslEpowersourcesandphysically.
separated inaccordance withRegulatory Guide1..75"Physical Independence ofElectricSystems"January1975(Rl)uptoandincluding theisolation devices.7~ICCinstrumentation shallbeenvironmentally qualified pursuanttoC-Eownersgroupqualification program.Theisolation de-vicesintheQSPDSareaccessible formaintenance following anaccident.
8.Primaryandbackupdisplaychannelsaredesignedtoprovidethehighestavailability possible.
TheQSPDS.isdesignedtoprovide99%availability.
Theavailability oftheQSPDSwillbeaddressed intheTechnical S'pecifications.
9.Thequalityassurance provisions ofAppendixB,Item5,willbeappliedtotheICCdetection instruments asdescribed intheAppendixBevaluation inTable1.9B-4.
RevisiontoTable1-9B-4ITEMRESPONSE5.1.144"Auditing ofQualityAssurance ProgramsforNuclearPowerPlants"..
6.TheICCdetection instrumentation outputsarecontinuously avail-ableontheQSPDSdisplaysthroughmanualcallupofdisplays.
throughmanualcallupof'displays.
Additionally, onechannelofanalogtrend,,;recording willcontinuously indicatetheICCsummaryvariables.
~7.TheICCinstrumentation isdesignedtoprovidereadoutdisplayandtrendinginformation totheopeartorthroughtheSASandanalogtrendrecording oftheICCsummaryvariables.
(SeeSection3.3);8.Theinadequate.
corecoolinginstrumentation isspecifically andsingularly identified sothattheoperatorcaneasilydiscerntheiruseduringanaccidentcondition.
9.Transmission ofsignalsfrominstruments ofassociated sensorsbetweenredundant IEchannelsorbetween1Eandnon-1Einstru-mentchannelsareisolatedwithisolation devicesqualified totheprovisions ofAppendixB.10.TheQSPDSconsistsoftworedundant channelstoavoidinter-ruptionsofdisplayduetoasinglefailure.IfintheremotechancethatonecompleteQSPDSchannelfails,theoperatorhas:1)Additional channelsofICCsensorinputsforcoldlegtemperature, hotlegtemperature, andpressuizer pres-sureonthecontrolboardseparatefromtheQSPDS.'2)TheHJTCSandCEThavemultiplesensorsineachchannelfortheoperatortocorrelate andcheckinputs.3)TheHJTCSsensoroutputmaybetestedbytheoperatorreadingthetemperature oftheunheatedthermocouple andcomparing toothertemperature indications.
4)Othervariables areavailable totheoperatorontheMainControlBoardforverifying theICCparameter.
Servicing, testingandcalibrating programsshallbeconsis-tent-withoperating technical specifications.
12.13.TheICCinstrumentation, including theQSPDS,arenotintendedtoberemovedorbypassedduringoperation.
Administrative controlwillbenecessary toremovepower,fromachannel.Thesystemdesignissu'chastofacilitate administrative control'ofaccesstoallsetpoints adjustments, calibration adjustments andtestpoints.
RevisiontoTable1.9B-4Continued 14.TheQSPDSisdesignedtominimizeanomalous indications totheoperator(seesection3.3).15.Instrumentation isdesignedtofacilitate replacement ofcom-ponentsormodules.Thei'nstrumentation designissuchthatmalfunctioning components canbeidentifed easily.16.Thedesignincorporates thisrequirement totheextentprac-tical.17.Thedesignincorporates thisrequirement totheextentprac-tical.18.Thesystemisdesignedtobecapableofperiodictestingofinstrument channels.
