|
---|
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
~P.O.BOX 529100 MIAMI, FL 33152 I i>>ir rP+g (Q I;P I<I~~FLORIDA POWER&LIGHT COMPANY September 8, 1981 L-81-393 Mr.James P.O'Reilly, Director, Region II Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Mr.O'Reilly:
Re: St.Lucie Unit 1 Docket No.50-335 IE Ins ection Re ort 81-06 In accordance with 10 CFR 2.790 (a)(7), Florida Power&Light Company requests that the information regarding the identity of certain FPL employees and their positions in the company be withheld from public disclosure in'Investigation Report 80-335/81-6.
We request that this information be deleted as shown in the attached"marked up" copy of the report.Although the false statement referenced in the report resulted simply from an oversight by a site employee, the release of this information might be prejudicial to the future professional careers of the individuals involvedin the investigation.
It is our judgement that these deletions are justified because of the finding in the report that the"investigation failed to identify any information which would indicate that the false statement was made knowingly or willfully." The report also found that"the false statement does not appear to be material from the standpoint of the health and safety of the public".If the position titles and employees'ames in investigatory records compiled for law enforcement purposes are released, it would result in an unwarranted invasion of personal privacy.Therefore, this information should be exempt from disclosure in accordance with 10 CFR 2.790.Very truly yours, Robert E.Uhrig Vice President Advanced Systems 8 Technology REU/PLP/ah cc: Harold F.Reis, Esquire 8i092905i3 8i0923 PDR ADQCK 05000335 6'DR PEOPLE...SERVING PEOPLE I I ('f~'4""9" jl
~P,S IIEgI Wp 0-)~C i~)~0 C s t o UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA ST., N.'IN., SUITE 3100 , ATLANTA, GEORGIA 30303 AUG 5'2 198)INVESTIGATION REPORT NO.50-335/81-06 SUBJECT: Florida Power and Light Company St.Lucie Unit 1 St.Lucie, Florida 33101 Possible Material False Statement DATES, OF INVESTIGATION:
January 28-February 5, 1981 INVESTIGATOR
.Y.se, Regional Investigator, Region II.Enforcement and Investigation Staff oP-/-8/Date OTHER PARTICIPATING PERSONNEL:
E.C.Gilbert, Investigator Office of Inspection and Enforcement REVIEWED BY: C.E.A Enforc m erson, Director nt and Investigation Staff, Region II Date
.~e 1 0 TABLE OF CONTENTS Section I.SUMMARY OF INVESTIGATION A.INTRODUCTION B.SCOPE C.FINDINGS AND CONCLUSIONS Section II.DETAILS OF INVESTIGATION A.PERSONS CONTACTED B.BACKGROUND C.INVESTIGATIVE EFFORT
'h SECTION I'U51MARY OF INYESTIGATION FLORIDA POMER AND LIGHT ST.LUCIE JANUARY 28-FEBRUARY 5, 1981
A.INTRODUCTION In mid-January 1981 the NRC Resident Inspector.
at Florida Power and Light's (FPKL)St.Lucie Unit 1 plant observed a December 23, 1980 letter from the FPSL:)to the Office of Nuclear Reactor Regulation (NRR), Division of Licensing, with regard to post TMI requirements.
>stated, in part and under oath, that NUREG 0737 had been implemented for Senior Reactor Operators and Reactor Operators.
Item I.A.1.3,"Shift Manning" of NUREG 0?37 sets forth that there should be a break of at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (which can include shift turnover time)between all work periods.The Resident Inspector was aware that no administrative procedure had been implemented'for the 12-hours in between shifts as of approximately mid-January 1981.The Resident Inspector subsequently brought this to the attention of NRC Region II super-visory personnel.
B.SCOPE OF, INVESTIGATION An investigation was initiated on January 28, 1981, under the authority provided by Section 161;c of the Atomic Energy Act of 1954, as amended, to ascertain whether or not a material false statement had been made.The scope of the investigation included the following:
1.Interviews of responsible licensee management and line personnel.
2.'Interview of the NRC Resident Inspector, St.Lucie Unit l.3.Review of the following licensee documents:-Nuclear Hatch Engineer log-Night Order book-Administrative Procedure 0010119, Revisions 0, 1 and 2-Facility Review Group meeting minutes for December 23, 1980 and January 13, 1981-Overtime report for exempt employees for one employee as well as daily time tickets f'r that employee and two others C.FINDINGS AND CONCLUSIONS I The investigation disclosed that the response to NUREG 0737 sub-mitted under oath by an f,of Florida Power and Light contained a false statement with regard to Item I.A.1.3 of NUREG 0?37 in that the procedure implemented at St.Lucie on December 23, 1980 did not include all of the restrictions included in NUREG 0737 and the response did not take exception to the restric-tion omitted.However, the information obtained during the investi-gation also indicated that except where exceptions were documented by FP8L in their response, the procedure included all of the other restrictions identified in Item I.A.1.3 and that the single restriction omitted was a result of an oversight by a site employee.The investigation failed to identify any information which would indicate that the false statement was made knowingly or willfully.
With regard to materiality, the investigation disclosed information which indicated that the licensee was attempting to comply with the requirements of Item I.A.1.3 and while failure to doc~ment the few instances where exceptions to the restrictions were granted by site management constitutes a deviation from comnitments, the'false statement does not appear to be material from the standpoint of the health and safety of the public.In view of the above, it is concluded that the statement did not constitute a material false statement.
However, it is further concluded that the licensee needs to develop a more formal system for assuring the accuracy of information submitted to NRC.
SECTION II DETAILS OF INVESTIGATION FLORIDA POllER AND LIGHT ST.LUCIE JANUARY 28-FEBRUARY 5, 1981
A.PERSONS CONTACTED Florida Power and Li ht Cor orate Office St.Lucie.Site Steel, Hector and Davis U.S.Nuclear Re ulator Commission S.A.Elrod, Re,sident Inspector, St.Lucie 1 B.BACKGROUND The U.S.Nuclear Regulatory Commission (NRC), Offi'ce of Inspection and Enforcement (IE), issued Circular 80-02 entitled"Nuclear Power Plant Staff Work Hours" on February I, 1980, which recommended, among other things, that for scheduling purposes, personnel perform-ing safety related functions should have at least a 12-hour break between shifts.No written response to IEC 80-02 was required from the licensee.The NRC's Office of Nuclear Reactor Regulation (NRR), Division of Licensing, issued.a letter dated July 31, 1980, (hereinafter referred to as the Eishenhut letter)to all power reactor licensees addressing tlie subject of interim criteria for shift staffing.Although it contained criteria similar to IEC 80-02, this letter did not list or make any reference to the 12-hour break between shifts as previously
recommended in IEC 80-02.On page 3 of that letter, four overtime restrictions were listed as follows: "l.An individual shall not be permitted to work more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> straight (not including shift turnover time).2.An individual shall not be permitted to work more than 24=hours in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.3.An individual shall not work more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period.4.An individual shall not cwork more than 14 consecutive days without having two consecutive days off." This letter further stated that administrative procedures (required by license conditions)
shall also set forth a policy concerning overtime work for Senior Reactor Operators, Reactor Operators and Shift Technical Advisors, and that development and implementation of the administrative procedures at operating plants would be reviewed by IE beginning 90 Days after the date of the letter.Subsequently, another letter from NRR dated October 31, 1980, set forth post-Three Mile Island (TMI)requirements in a document entitled"Clarification of TMI Action Plan Requirements" (NUREG 0737).Section I.A.1.3 of NUREG 0737 entitled"Shift Manning Requirements" set forth the following in regard to overtime restric-tions:~/"l.An individual should not be permitted to work more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> straight (not including shift turnov'er time).2.There should be a break*of at least 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> s (which can include shift turnover time)between all work periods.3.An individual'hould not work more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period.4.An individual should not be required to work more than 14~consecutive days without having 2 consecutive days off.However, recognizing that circumstances may arise requiring deviation from the above restrictions, such deviation shall be authorized by the plant manager or his deputy, or higher levels of management in accordance with published procedures and with appropriate documentation of the cause." NUREG 0737 further specified in, the transmittal letter that pursuant to 10 CFR Par't 50,54(f)operating reactor licensees were required to furnish, within 45 days of the letter (October 31, 1980), confirmation A
that the implementation dates indicated in Enclosure 1 of NUREG 0737 would be met.The requirement for limiting overtime was supposed to be implemented by November 1, 1980.Part 50.54(f)states: "The licensee will at any time before expiration of the license, upon request of the Commission, submit.written statements, signed under oath, to enable the Commission to determine whether or not the license should be modified, suspended or revoked." In mid-January 1981, the NRC's Resident Inspector at Florida Power and Light's St..Lucie Unit 1 nuclear power plant reviewed a letter to NRR (Division of Licensing, Attention Mr.D.G.Eishenut)from FP&L's l The letter, dated December 23, 1980, (FPSL identification:
L-80-418)was in response to NUREG 0737 and stated that the October'1, 1980 letter which transmitted NUREG 0737 had been reviewed.The attachment to the FP8L letter indicated that with regard to shift manning, the overtime restrictions as described in the July 31 Eisenhut letter and NUREG 0737 had been implemented for Senior Reactor Operators and Reactor Operators.
The letter and attachment from ,.were subscribed and sworn to before a Dade County Notary Public on the 23rd of December, 1980 as being true and correct to the best of his knowledge, information, and belief.The resident inspector was aware that'the'2-hours-in:betwe'en shifts had.not been formally implemented sn'he St Lucie administra-tive procedures.
This was brought to the attention of the Resident Inspector's supervisor.
It was later determined by Region II management that an investigation would be conducted to determine if a material false statement had been made by Florida Power and.Light.The investigation was initiated on January 28, l981, under the authority provided by Section 161.c of the Atomic Energy Act of 1954, as amended.INVESTIGATIVE EFFORT'nterview of On February 2, 1981, the!, was interviewed by the investigator at the.Florida-Power and Light office in Miami, Florida.Also present were the~and an attorney from the firm of Steel, Hector and Davis in Miami, Florida.They were advised of the purpose, authority and scope of the NRC's.investigation.
~"~q~I In essence, the)related that he issued the December 23, 1980 letter believing that the overtime restric-tions as described in the July 13, 1980 Eisenhut letter and NUREG 0737 had been implemented.
However, on February 2, 1981, he learned that a procedure revision for the 12-hour in between work periods had not been approved until January 15, 1981.Apparently, the i had been aware of the procedural requirements, but was on vacation when the St.Lucie Facility Review Group (FRG)having.responsibility for reviewing and approving plant procedures met on December 23, 1980.Hence, the 12-hours between shifts was inadvertently omitted from the administrative procedure.
He pointed out that during the time period from December 20, 1980 to and including January 15, 1981, of 351 licensed shift positions manned only 3 instances occurred in which the 12-hour in between shifts rule was not adhered to.He explained that when he signed the letter to the NRC dated.December 23, 1980, he had not seen the administrative proce-dure covering shift manning requirements as it was developed by and maintained at the St.Lucie plant and he did not normally see copies of-such procedures.
During the interview the investigator was also i'nformed that FPSL had determined that a similar situation had occurred at Turkey Point Units 3 and 4;that is, the response to NUREG.0737 for Turkey Point indicated that Item I.A.1.3 had been implemented when, in fact, it had not.The~'agreed to provide further details regarding Turkey Point should they be desired.2.Interview of NRC Resident Ins ector On February 3, 1981, the NRC Resident Inspector, St.Lucie Unit 1, was interviewed'nd provided details of his knowledge of this situation.
In essence, he stated the plant administrative procedure did not comply with the requirements specified in NUREG 0737 regarding the 12-hour break between shifts.During the months of November, December and January he brought this to the attention of several St.Lucie supervisory-personnel.
In mid-January 1981, when he observed the December 23, 1980, letter from the licensee to the NRC advising that Item I.A.1.3 of NUREG 0737 had been implemented for SROs and ROs, he knew this to be untrue and brought it to the attention of NRC Region II management.
I
Subsequent to the interview, the inspector provided copies of St.Lucie Adminisbative Procedure 0010119, Revisions 0, 1 and 2.Additionally, he provided copies of the Facility Review Group meeting minutes for December 23, 1980 and January 13, 1981.Interview of On February 3, 1981,), St.Lucie Unit 1, was interviewed and provided details concerning his knowledge regarding this matter.In essence, he was pursuing implementation of the procedure change for all plant staff personnel performing safety related functions.
However, in mid-December 1980, FPSL corporate personnel gave oral notice that their position in response to Item I.A.1.3 of NUREG 0737 would be to address only SROs and ROs and they would take exception to applying the restrictions to non-licensed personnel.
The plant staff was instructed to prepare a procedure which was consistent with that position.He had no further involvement in the procedure change.Regarding the 12-houi between shifts, he.said'that although only recently formalized by the operations group at St.Lucie 1, they had adhered as closely as possible to that rule.He could not recall the method he used to provide the 12-hour between shifts policy to the shift supervisors.
He thought it may have'been done orally or written in the night orders.During the December 23, 1980, to January 12, 1980, time frame, he recalled being called several times by operations personnel about granting exceptions to one of the overtime restrictions set forth in NUREG 0737.At that time, he was designated to perform the function of Plant Manager Designee as defined in Chapter 13 of the FSAR.He could not recall documenting these exceptions on any forms and was not aware of any file.Interview of On February 3, 1981, the;St.Lucie 1, was interviewed.
In essence, he became aware of the 12-hour between shifts requirement when it was brought to his attention by the NRC Resident Inspector.
After confirming this bv reviewing NUREG 0737, he instructed a ,'o ensure the 12-hour between shifts for SROs and ROs was placed in the procedure change draft.He then went on vacation on December 20, 1980, and returned on January 5, 1981.He subsequently learned from the.that the 12-hour requirement had been inadvertantly omitted from the proposed procedure revision, and the FRG had approved the"
administrative procedure revision without the 12-hour requirement.
He later revievied the FP8L time card records and found 2 operators and one plant supervisor who had worked 8-hours on, had only 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> off and returned to work for another 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during the D'ecember 20, 1980 to January 16, 1981 time frame.The names, times and dates were provided to the investigators.
On February 4, 1981, the', St.Lucie 1,<<as reinterviewed by the investigators.
and provided the following information.
The interface between FPRL corporate and St.Lucie site personnel concerning the 12-hour in between shifts, was with the Power Resources (corporate)
staff and St.Lucie's technical staff.He had coordinated with a regarding the drafting of the letter which was ultimately sent to the NRC.Shift manning, among numerous other things, was mentioned, but he could not definitely recall any discussions regarding the 12-hours in between shifts.He recalled a meeting with the~on December 15, 1980 and numerous telephone calls and also remembered observing a rough draft of the letter.To ensure that St.Lucie was complying with the letter as stated regarding the implementation of NUREG 0737, he instructed a,~to make the change in the procedur e.He assumed it would be done and therefore the letter to be sent to the NRC would be accurate.Interview of.On February 4, 1981, the (former))at St.Lucie 1 during the period 1976 through 1980 was interviewed by.the investigators.
In essence, he stated he was aware of the 12-hour in between shift limitations after being informed of it sometime'in the first half of December 1980 by the.5 In accordance with the instructions, he prepared a procedure change request with the 12-hour limitation included in it.However, prior to presentation to the FRG, another change regarding shift technical advisors was directed by corporate personnel; therefore, he prepared another procedure change request.The 12-hour between shifts was inadvertently left off of this new procedure change request, which was submitted to the FRG and finally approved on December 23, 1980.Hence, the December 23, 1980 Administrative Procedure, approved by the FRG and signed by the Plant Manager, did not have the 12-hour in between shift limitations included.
Meetin With Plant Mana er and Other Plant Personnel On February 4, 1981, the investigator was advised that when-ever a procedure change is necessary Quality Control (QC)keeps track of it.That is, a tracking document (" Pink Slip")is generated and forwa'rded to the responsible department head who is required to respond by providing a date and what action will be initiated.
In regard to the 12-hours between shifts, the"Pink Slip" was not issued because the QC p~rson who reviewed NUREG 0737'did not realize that there was a difference between the Eishenhut letter of July 31, 1980, and NUREG 0737 and did not realize a procedure change was required.Therefore, they expl'ained, it was an oversight by QC that resulted in th'omission of the 12-hour between shift requirement.
Record Reviews On February 4 and 5, 1981, the St.Lucie Nuclear Watch Engineer's Log was examined by the investigator for the period from 7:30 a.m.on December 22, 1980 through 3:30 p.m.on February 4, 1981.The log is a chronological listing of personnel present during each eight hour shift to include hours of overtime, sick leave and vacation time incurred by each individual during each shift.The purpose of this review was to deter-mine whether or not any entries were made regarding exceptions from overtime restrictions for the three individuals who worked 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> off and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on.No information pertinent to this investigation was identified.
The St.Lucie Night Order Book was reviewed on February 4, 1981, by the investigator.
The night order book is utilized as an informal method of issuing management instructions which have short-term applicability, but require dissemination.
Such instructions encompass special operations, housekeeping, data taking, publ.ications and their distribution, plotting process parameters, personnel matters and other similar items.Inquiries by the investigator disclosed the contents are periodically purged or extraneous informa'tion.
The purpose of the review was to determine if the had made any entries in the book regarding implementation of the 12-hour between shifts.An analysis of the existing information, dated between September 12, 1980, and February 2, 1981 revealed no data*pertinent to this investigation.
The three revisions of St.Lucie Administrative Procedure 0010119,"Overtime Limitations for Licensed Operators" were also reviewed by the investigator.
This review disclosed that Revision 0, approved by the Plant Manager on October 31, 1980, formally implemented the restrictions contained in the July 31 Eisenhut letter (which did not include the 12-hour between shifts restriction).
Revision 1 which was reviewed by the FRG on December 23, 1980 and January 13, 1981, and approved by the Plant Manager on January 15, 1981, picked up the 12-hour between shift restriction, but was not specific as to who could approve exceptions to the restriction or the documenta-tion required.Revision 2 approved by the Plant Manager on February 4, 1981, provided the necessary amplification of approval and documentation requirements.
A review of the minutes for the FRG meetings conducted on-December 23, 1980 and January=13, 1981, disclosed that the change considered by the FRG on December 23 involved.the dele-tion of the Shift Technical Advisor from the positions covered by the restrictions.
The change to add t'e 12-hour between shift requirement was not considered by the FRG until the January 13 meeting.Re uest for Overtime Exce tion.Documentation I On February 4, 1981, the Technical Staff Supervisor was requested by the investigator to interface with the Plant Manager, and attempt to locate and present any documentation of the granting of the exceptions to the overtime restrictions for the three individuals.
On February 5, 1981, the Plant Manager was contacted by the investigator and he advised that no documentation had been found at that time.Interview of On February 5, 1981, the 1 was interviewed at the Florida Power and Light Company Corporate office in-Miami, Florida.During the interview, he stated that on November 17, 1980, NUREG 0737 was delivered to his department, Power Resources-Nuclear (PRN).In that there was a response due, PRN set about to prepare the response with input from.all responsible parties.The issue of complying with the shift manning restrictions was addressed right from the start;however, the emphasis was placed on who should be covered by the restrictions.
FP&L eventually took exception in the response to extending coverage to non-licensed personnel.
There was then a review and comment cycle which ultimately
.resulted in a semi-final draft that was discussed on December 15, 1980, in a meeting at St.Lucie between the ,, St.Lucie 1,.an individual from Licensing and Environmental Planning and himself.The final draft of the December 23, 1980 letter (L-80-418)
was prepared by himself (noted by the initials.'I), and transmitted to the~for.final signature.
STATE OF FLORIDA))ss.COUNTY OF DADE)E.A.Adomat , being first duly sworn, deposes and says: That he is Executive Vice President of Florida Power 8 Light Company, the Licensee herein;That he has executed the foregoing document;that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.Information regarding the identity of certain FPL employees and their sti si v t't-3-a uni gg the enclosed material is/aM(exempt from public disclosure in accordance with Section 2.790 of the NRC"Rules of Practice", Title 10, Code of Federal Regulations.
Pursuant to section(s)
10 CFR 2.790 a 7 this information is exempt from disclosure because it will constitute an unwarranted invasion of ersonal rivac if the osition titles and em lo ees'ames in investi ator records com iled for law enforcement ur oses are released.E.A.Adomat Subscribed and sworn to before me this'day of , 19~.: NOTARY-'PUBLIC, i and for the County'of-Dade, State of Florida.s,<Roads a<<~fgo lgotarv Pubgc.o~bcr 30,=1983~Mv~%1A~4 BOAdlAQ AgCllCQ My commission expires:-dw e~~w>>'
J'L)('C P