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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
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REGULATORY
" ORNAT ION DISTRIBUTION SY."+N (RIBS)ACCESSION NBR:8301200328 DOC~DATE: 83/01/14 NOTARIZED:
NO FA(:IL:55-389 St~Lucie Plantr Unit?i Flor ida Power L Light Co, AUTH~NAME AUTHOR AFFILIATION UHRIGrR~ED Florida Power L Light Co~REC IP, NAME RECIPIENT AFFILIATION EISENHUTiD.G, Division of Licensing DOCKET'0 05000389
SUBJECT:
Forwards modified responses to Items A~1 3rAR3~1rAR4~10r A.5,8 A.5.9 8 A.6, 11 of App C Suppl 1 to NUREG-0843 re control room designrper 821227 telcon.Updated Section F 1 of"Near"Term OL Summary Human Engineering Rept>>," also encl.DISTRIBUTION CODE: 8001S COPIES RECEIVED:LTR ENCL SIZE: 'ITLE: Licensing Submittal:
PSAR/FSAR Amdts 8, Related Correspondence NOTES: RECIPIENT ID CODE'/NAME A/D LICENSNG LIC BR P3 LA INTERNALs ELD/HDS2 IE/DEP EPDS'5 NRR/DE/AEAB NRR/DE/EQB 13 NRR/DE/HGEB 30 NRR/DE/MTEB 17 NRR/DE/SAB 24 NRR/DHFS/HFEB40 NRR/DHFS/OLB 34 NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DSI/I CSB 16 NRR/DSI/PSB 19 NRR/DSI/RS8 23 RGl42 EXTERNAL: ACRS 41 DMB/DSS (AMDTS)LPDR 03 NSIC 05 COPIES LTTR ENCL 1 0 1 0 1 0 1 1 1 0 2 1 1 1 1 1 1 1 1.1 1 1 1 1 1 1 1 1 1 1 3 3 6 1 1 1 1 1 1 RECIPIENT IO COOEINAYiE L I C BR N'3 BC NERSESrV~01 IE FILE'E/DEP/EPLB 36 NRR/DE/CEB 11 NRR/DE/GB?8 NRR/DE/MEB 18 NRR/DE/QAB, 21 NRR/DE/SEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/OS I/ASB NRR/DSI/CSB 09 NRR/DS I/METB 12 I/RA 8 22 REG F Ort IB BNL(AMOTS ONLY)FEMA REP DIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1 0 1 1 1 1 3 3 1 1 2 2 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED'TTR 53 ENCL 46
'P~'1~I FW I>)f'F 4, 4 WW I f>,if">>~.)I W (1>'ll'lfyttt)4 I')P)4 I l l 1 4'~'"~WL S Pc>f C 4'1 IF)t>t l (>l~wl,ur.">IIWg.'W" ll'Wff 4 1'IC 1 CI<>I>I'"" l4>>,>I IW~FF rl f">I 4 W l II,>>fwff>f q W 4 fWt>>g l 0~I t~W i~I Q Iy~n', w W r.~wrI'Ww,wa W l-', 0~'>II>FIICK, c,,ow" II~u IW>W'1 f Wfttfw 4 twFw'wFw 1 I'i W~f'Pww I)w>Wr I<<'hwf WI I,t'0 I 1>>1,>I~>>t m~aew>>~me,~~F I>j CW'I t'f 1>(1 I 4I)Fg Fttr IwT W 4)rf WA W lw>W Wfq f'>>>I ft 9>Wl>>"t w>SF,'X="Iw, rr s l>,fg C Jr>>I')www>>t>rf', I'r)j C II"WT J:W',W WIT'W l il l f>I II)I'I t'1>I'rr ,.W 1 If"I 4 7~il 3,,tt ft Ii W>4 h ll WN I, WW,'IX, 4I>'I Iii',W>>"Iw)X)I)l I rl W'l ff)Irl wt'w)>>'4 N')w'I),), 4lr l l[4 4 l If')II 0 V F'W, I>F Qv>I k>>III wt W,ft W I" I III II 4$>>I f, WW>>>k fr+i W J BOX 14000, JUNO BEACH, FL 3340B FLORIDA POWER&LIGHT COMPANY January 14, 1983 L-83-18 Office of Nuclear Reactor Regulations U.S.Nuclear Regulatory Commission Washington, D.C.20555 Attention:
Mr.Darrell G.Eisenhut, Director Division of Licensing
Dear Mr.Eisenhut:
Re: St.Lucie Unit No.2 Docket No.50-389 FPL/NRC December 27, 1982 Telecommunication on Control Room Design Review Su lement l of NUREG-0803 Attached are the agreed to modified responses to items A.l.3, A.3.l, A.0.10, A.5.8, A.5.9 and A.6.ll of Appendix C, Supplement No.l of NUREG-0843.
In addition, attached is an updated response on item 3.l of Florida Power R Light Company's NTOL Summar Human En ineerin Re ort on St.Lucie Unit No.2 Control Room (Supplement
$7I.If you have any questions regarding this submittal, please contact us accordingly.
Very truly yours, Rober E.Vhrig Vice President Advance Systems and Technology R EU/R JS/MT/au Attachments cc: 3.P.O'Reilly, Region II Harold F.Reis, Esquire goo I 830i200328 830ii4 PDR ADQC'K 05000389 PDR PEOPLE...SERVING PEOPLE C, I Attachment RECORD OF PHONE CONVERSATION December 2T, l982 A conference call between Florida Power R Light Company project and human factor engineering team representatives and representatives of the Nuclear Regulatory Commission licensing branch and human factor's branch was held on December 27, 1982 at approx~mately l300.The purpose of the call was to review and resolve any points of contention with regard to those items submitted to Mr.D.G.Eisenhut, Director, Division of Licensing under cover letters L-82-077, dated l0/29/82 and L-82-096, dated II/10/82.The following are submitted to provide modified responses to SER Supplement No.l Appendix C findings A.l.3, A.3.l, A.0.10, A.5.8, A.5.9 and A.6.ll as agreed to and provide additional information with regard to section 3.l of Florida Power R Light's NTOL Summar Human En ineerin Re ort on St.Lucie Unit No.2 Control Room (Supplement k/I dated October 28, l982.SER Su lement No.I A ndix C Findin A.l.3 The original finding and response were as follows:~Findin A.l.3 There are no provisions for key storage and no procedures for key access control for keys used in the Control Room and for keys used at the Remote Shutdown Panel.(I.6)~Res once Key storage will be provided as well as the necessary key access control procedures for those keys used in the Control Room and Remote Shutdown Panel prior to fuel load.The Remote Shutdown Panel SIS block keys will be maintained at RAB control access point.After discussions with representatives from FPRL Operations Staff and Human Factors.Branch of the Nuclear Regulatory Commission it was agreed that the response to Finding A.l.3 would be modified to read: "Key storage will be provided as well as the necessary key access control procedures for those keys used in the Control-Room and Remote Shutdown Panel prior to fuel load." Deletion of the last sentence was deemed appropriate since FPRL is implementing the same Remote Shutdown.Panel key control procedure and key locker access as presently exists on St.Lucie Unit No.I.Implementation of this plan provides for storage of the SIS block keys in a locked key locker located in the Remote Shutdown Panel Room.Location of the SIS block keys in the Remote Shutdown Panel Room greatly improves operator access to the subject keys and minimizes the amount of time it would take the operator to man his station with the subject keys.
SER Su lement No.I A ndix C Findin A.3.I The original finding and response were as follows:~Findin A.3.l The function of the annunciator tile labeled ANNUNCIATOR POWER SUPPLY on annunciator Panel K is not clear.(3.1)~Res onse The tile will be re-engraved to read"Annunciator Backup Power Supply" prior to the issuance of an operating license.After review of the subject annunciator Operations personnel at St.Lucie Unit No.2 felt that labeling the subject annunciator as"Annunciator Power Supply Failure" was more descriptive than the original annunciator label presented in the response above.The subject annunciator tile will be labeled"Annunciator Power Supply Failure".SER Su lement No.I A ndix C Findin A.O.IO The original finding and response were as follows:~Findin A.C.lo Rotary switches and keyswitches have unlabelled positions.
(0.12)Examples: a)SIAS Block Channel SA and SB keyswitches on Panel 206 b)MSIS Block Channel SA and SB keyswitches on Panel 206 c)Trip Circuit Reset rotary switches on the RPS Panel~Res onse These positions will be labeled prior to issuance of an operating license.After performing an engineering review and field inspection of plant documents, standards and switch escutcheon plates it was verified that the normal position on control switches is not engraved.The existing condition is as per the Architect Engineer's labeling specification and control switch position convention.
As a result of conversations with representatives from the NRC's Human Factors Branch and FPRL's Project Management Team and Human Engineering Group it was agreed to modify the subject response to read: "These positions will be labeled to be consistent with plant standards and existing control switch conventions prior to issuance of an operating license."
SER Su lement No.1 A ndix C Findin A.5e8 The original finding and response were as follows:~Findin A.5.8 Several meter scales have thick black marks to extend major thick marks to the scale numerals.These marks give the misleading appearance of minus (-)signs in front of the meter scale numerals.(5.11)Examples: (HVAC5'anel) a)PDIS-25-1B b)PDI-25-15B
~Res ense The marks viewed as being interpreted as minus (-)signs will be removed.This will be accomplished prior to fuel loading.During a field review of this item with NRC Field Inspector, Mr.Steve Elrod, it was agreed that the major thick marks on sigma meters did not pose ariy confusion to the control room operator.Where indicators display positive and negative values the scales are conspicuously marked indicating positive and negative values.Major graduation on sigmas are consistently marked as per the attached Figures 1 R 2.Figure 1 depicts a typical sigma scale showing a negative to positive value scale and Figure 2 depicts a typical sigma scale showing zero to positive values.As agreed to previously during conversations between representative of the NRC's Human Factors Branch and FPRL's Human Engineering Group FPRL has modified its response to.read: "The marks viewed as being minus (-)signs by the field inspection team pose no significant interpretation problem to the control room operator.The subject sigma meter graduations are consistently presented.
Where negative and positive values are displayed by indicators minus (-)and plus (+)signs are conspicuously placed on indicator scales.FPRL intends no further action on this item." SER Su lement No.1 A ndix C Findin A.5.9 The original finding and response were as follows:~Findin A.5.9 There are several displays which use unconventional scale graduations.
(5.12)Examples: a),Panel 201: DIESEL GENERATOR 2B MVARS VARM-1616 b)Panel 200: WIDE RANGE 96 POWER 31-00IB c)Panel 203: LOOP 2A COLD LEG TEMP TIC-lll d)Diesel Gen 2B Frequency
~Res onse The displays listed in the finding will be modified as follows: Meter faces will be color coded to reflect normal operating ranges prior to issuance of an operating license.Displays will be reviewed for scale convention during the long-term control room review and reported on in accordance with NUR EG-0700.After discussions with the NRC Field Inspector, Mr.Steve Elrod, on the above finding FPRL feels that the above'response should be modified to reflect the intent of the color coding program presently being implemented to denote normal operating ranges on indicators.
The modified response reads as follows: "The displays listed in the finding will be modified as follows: Meter faces will be color coded to reflect normal operating ranges.Those indicators which are used over a wide range of operating conditions and have no definite operating bands will not be color coded since no improvement in operator performance would.be expected and possible confusion as to the meaning of the color code may contribute to operator error during operation.
Items b and c in the above finding will not have any color operating bands placed on their scale since they are used under a variety of operating conditions and their normal operating band depends on plant status." SER Su lement No.l A ndix C Findin A.6.ll The original finding and response were as follows:~Findin A.6.ll The CONDENSER VACUUM DISPLAY (PI-10-7B) on Panel 20l has a mislabeled scale.It should read"Inches Hg Vacuum" instead of"Inches Hg ABS".(6.I3)~Res onse The condenser vacuum display will be labeled as"Inches Hg" prior to fuel loading.A review of St.Lucie Unit No.2 piping and instrumentation drawings indicates that Pl-l0-7B displays condenser pressure as"Inches Hg ABS".After discussions with the NRC Field Inspector, Mr.Steve Elrod, on the above finding it was agreed that the above response would be modified to read: "The condenser vacuum display (Pl-l0-7B) displays condenser pressure as"Inches Hg ABS", and is consistent with plant documentation.
The subject display will be labeled,"Inches Hg ABS"."
NTOL SUMMAR Y HUMAN ENGINEERING REPORT ON ST.LUCIE UNIT NO.2 CONTROL ROOM (Supplement Pl)Update of Section 3.1 (3.1)Control Room Environment
.A.Lighting A light survey of the control room was conducted during the month of August, 1982 with the results as previously presented in the NTOL Summary Human Engineering Report dated October 28, 1982.The emergency light levels were found acceptable and the normal AC light levels were to be reduced to approximately 50 ft.candle levels by switching off selected banks of A.C.lights not on the vital AC auto diesel load circuits.A light survey was conducted 3anuary 7, 1983 after normal light levels were reduced.The normal AC light levels were reduced to acceptable levels such that emergency light levels remain uneffected.
The normal AC light levels as tested are presented in Figure 3 and table 3.1.It should be noted that where control panels have vertical and horizontal work areas light levels were measured on both planes.In conclusion, FPkL considers the control room light survey to be satisfactorly complete and intends no further action as part of the Preliminary Control R oom Design R e view ef fort.CONTROL ROOM NORMAL AC LIGHT LEVELS TABLE 3.1 Level in Position Ft.Candels Position Level in Ft.Candels 1 2 3 6 7 8 9 10 11 12 13 JO 15 90 09 73 77 55 56 55 52 05 06 Ol 36 01 35 39 16 17 18 19 20'21 22 23 20 25 26 27 28 29 38 35 32 37 35 37 Q7 79 75 62 70 110 22 29 B.Temperature and Humidity An assessment of the St.Lucie Unit No.2 control room ventilation system was conducted from 3anuary 7 through 3anuary 10, 1983.No discrepancies were noted.The Control Room measured temperature and relative humidity ranged 5 from 72 to 75o F.and 50 to 50%respectively while the ambient dry bulb temperature and due point ranged from 59 to 75.5o F.and 52 to 68o F.respectively.
FPRL considers the temperature humidity survey of the control room to be satisfactorily complete and intends no further action as part of the Preliminary Control Room Design Review effort.C.Noise A noise survey of the St.Lucie Unit No.2 control room was conducted on December 30,,1982.Figure 5 shows the control room locations where sound measurements were taken.Table 5.1 lists the background levels and Table 5.2 lists the panel annunciator levels as measured, at position 1 of Figure 5.It was determined that the 8 Reactor Protection System cooling fans were the major contributing factor to the observed background noise levels.A second survey was conducted with only 0 of the subject fans running.By reducing the number of cooling fans by half, an approximate 3dbA reduction in background noise level was achieved.Presently FPRL is reviewing the redesign of the air supply to the reactor protection system and will implement the necessary system design changes to reduce the noise contributed by the subject cooling fans during the first refueling outage.FPRL will install carpeting in the control room which is expected to help reduce background noise levels.The carpeting will be installed af ter construction activity in the control room is complete.FPRL considers the control room sound survey to be complete.The presently installed annunciator sound devices are adjustable an'd will be raised to 10 dbA above background.
CONTROL ROOM BACKGROUND SOUND LEVEL SURVEY TABLE 5.1 Location Sound Levels in dbA 8 RPS Fans Running 0 RPS Fans Running 1 2 3 5 6 7 8 9 10 68 69 71 66 63 62 62 60 59 61 66 65 68 63 61 62 61 59 59 61 CONTROL ROOM ANNUNCIATOR.
SOUND LEVEL SURVEY TABLE 5.2 Alarm Location Reading dbA A B C D E F G H 8l 80 79 Not Operational 77/77'ot Operational 77 Not Operational NOTE: Readings were taken at location I FPRL considers this effort of the Preliminary Control Room Design Review effort to be complete.II.(3.l)Remote Shutdown Panel Environment A.Lighting A light survey of the normal AC and emergency D.C.light levels in the Remote Shutdown Panel area was completed on November 3, l982.Light levels were measured at three levels of each vertical paneI.The data are presented below: Remote Shutdown Panel Room Diagram:+NOTE: Readings taken at (3)different positions directly in front of the panel and at (3)verticle points: 30", 50", 70" for each position.Measurements readings in ft.-candles.
I 2 (TEST POINT POS)
LIGHT SURVEY FOR REMOTE SHUTDOWN PANEL ROOM Condition~Hei ht Position 1 Position 2 Position 3 J.Vital A.C.(Normal)(A 2 B Diesel)30I1 5 QADI 70" 26 30 16 35 38 36 OJ 00 50 2.A and B Battery (D.C.)3 0 I I 501 I 7 Qll 09 65 92 60 85 10565 75 3.A Battery/B Diesel (D.C.a A.C.)3 0 I I 5 QADI 7 Qll 18 18 15 22 25 20 28 25 32 B Battery/A Diesel (D.C.2 A.C.)3 01 I 5 0 I I 7/II 38 60 90 08 70 100 30 39 52 Light levels in the Remote Shutdown Panel room will be reduced for conditions 2 and 0 above by reducing the incandescent lamp size.Verification testing will be complete after installation of the two control relays which are scheduled for installation during the second week of February, 1983.B.Temperature and Humidity A review of the St.Lucie Site Environmental data presented in section 2.6 of the St.Lucie Unit No.2 Environmental Report was performed.
The data presented indicates that the upper extreme climatic conditions for the site can reasonably be expected for approximately 8.596 of the year (31 days-high temperature with high humidity).
The R emote Shutdown panel room is supplied with ambient air at approximately 1000 SCFM by the Reactor Auxiliary Building Supply.Fan.During the above mentioned extreme conditions the ambient air may be between 90 and 101o F with a maximum wet-bulb temperature of 76.5 F.It is estimated th'at the air flow rate mentioned above would provide the operator-with a working habitate having an air movement of 30 Ft/Min with a supply air temperature rise of approximately 3 F.Based on a maximum wet-bulb temperature of 76.5o F., a maximum dry bulb temperature of JQOo F.and an air velocity of 30 Ft/Min it is anticipated that the Remote Shutdown Panel Room environment will be within the 85o F.or less effective temperature range at least 9696 of the year.The 85o F.effective temperature limit referenced is as defined by MIL STD-1072 and extracted from the curves of figure 38, MIL STD-1072.Since the remote shutdown panel room environment is conservatively estimated to be marginally outside the 85o F.effective temperature range J6 days (0%)of the year FPRL intends no further action on this item as Part of the Preliminary Control Room Design Review effort.This item will be readdressed during the Detailed Control Room Design Review at which time the subject fan system balancing and fan performance testing would have been complete and a more accurate assessment of existing operational conditions 8
can be made.FPRL considers the results obtained and the Preliminary Control Room Design Review effort to be satisfactorily complete.C.Noise A noise survey of the St.Lucie Unit No.2 Remote Shutdown Panel Room was conducted on December 30, l982.The maximum sound level observed was 59 dbA which was well within the 65 dbA level presented in NUREG-0700.
The observed background'ound levels are acceptable and FPKL considers this portion of-the Preliminary Control Room Design Review effort to be satisfactorily complete.MT/au 0\
I IGURE NO.I A.5.8 lN CHES H,O 30 K5 ZCI t5 IO 5 0 IO I5 20 25 4-2.0 DC MA FIGUI~iXQ 2 CFM I l 4-20 BCMF'1m IN r4o-JK-!2D IIO/CO 80'70 kP 20 10 0"NOTE SKETCH=S PEP.FOR GF~AFH/C PUP,POSES 14 RMAL AC LIGHTIMG LEVELS (FOOT.CANDLES) v~v v p,, e~O'O~~*\vvv 2 FIGURE 3
-f o ENV, I.RO CONTROL ROOM DATA 10 12 2 SVNOaV<*.PQ lq 0 p.I'9 b.80 6/I I AO 2p~G~r~<qAqhg,ph L+"pr~),pr)9rr rig gO'p~~ee r~I'I...99 PV/97 IV.E.NTA L*'vr 9 re e V e I oX o~,eg, , urer"."'/i CI g gr.',:::,9/Py~
rr/r, III(<6<(gee't tOI g ,'RQ ring.r.%.r"..~"-~n/6n'op o~~O CC ,.a~<$$~o t o 9'X o xo~OM 9 pe Wy~c~)~PIIIIer Q~~1II I III I ill I I I I',I I~I 938 9's+'NC 7011.~"'Ve OL 05 OC., Oy OS O.0 e~o~S+qO~..'.'I I~~, IOl j't J e.I/'rv~b*, I~FIGURE 4 SOUNLEVEL SURVEY-SL N0.2 READING LOCATIONS Q2 Q4 Q5 3 Q6 U I I l Df6 sI F I GURE 5 g~I I