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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:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20207L5671999-03-12012 March 1999 Forwards Facility Submitted Outline,Initial Exam Submittal & as Given Operating Exam for Test Administered on 981130,1204-14 & 18 ML20207E6091999-03-0303 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980622-26 ML20236Y6301998-08-0808 August 1998 Forwards Monthly Rept Reflecting Status of 10CFR2.206 Petitions as of 980731.Petitions on Plant GT97494 & GT97339 for Which DD Became Final Actions During Month Were Closed. Portion of Encl Withheld ML20237A0011998-08-0707 August 1998 Informs That Extension Granted on Envirocare Decision of 980904.Two Week Extension on Philadelphia VA Decision of 980828 Requested.Submits Concurrence of Changes.Rept on 2.206 July Status for Plants Encl ML20248L8621998-06-0909 June 1998 Forwards May 1998 Rept on Status of Public Petitioners Under 10CFR2.206.Petition on Seabrook (GT970873) for Which DD 98- 03 Became Final Agency Decision on 980413 Closed.Attachment 3 Withheld ML20203M6681998-02-23023 February 1998 Forwards SER Re TR CENPD-199-P,Rev 1-P-A,Suppl 2-P, CE Setpoint Methodology Proposing CRGR Review Be Waived IAW Suggested Procedures in 890929 Memo ML20202E0141997-11-25025 November 1997 Forwards FOIA Request Received Direct in Region II from E Barton on 971125.Encl Partially Deleted IA-97-461, Forwards FOIA Request Received Direct in Region II from E Barton on 971125.Encl Partially Deleted1997-11-25025 November 1997 Forwards FOIA Request Received Direct in Region II from E Barton on 971125.Encl Partially Deleted ML20205D4281997-08-15015 August 1997 Discusses Concern Identified During Special Design Architect-Engineer Insp Re EQ of Unit 1 Terry Turbine Woodward Governor Controls for Steam Turbine Driven Auxiliary Feedwater Pump IA-99-106, Discusses Concern Identified During Special Design Architect-Engineer Insp Re EQ of Unit 1 Terry Turbine Woodward Governor Controls for Steam Turbine Driven Auxiliary Feedwater Pump1997-08-15015 August 1997 Discusses Concern Identified During Special Design Architect-Engineer Insp Re EQ of Unit 1 Terry Turbine Woodward Governor Controls for Steam Turbine Driven Auxiliary Feedwater Pump ML20205M3331997-07-28028 July 1997 Provides Final Agenda for Region II Enforcement Meeting to Be Held on 970730.OI Attendance Requested for Issue Involving Termination of Turkey Point Radwaste Operator Who Failed to Follow Procedure IR 05000335/19970051997-07-17017 July 1997 Forwards Allegation Evaluation Rept & NRC Insp Repts 50-335/97-05 & 50-389/97-05 Re RII-97-A-0116 ML20202E0261997-04-23023 April 1997 Discusses Technical Staff Actions Associated W/Three Concerns in Allegation RII-96-A-0251 ML20137L2971997-03-31031 March 1997 Forwards Matrix Containing Answer to Listed Questions in ,Rev 1 ML20137R8831997-03-27027 March 1997 Provides Info Requested by 960208 Memo from J Stolz Re Review of Spent Fuel Pool Practices & Current Licensing Basis ML20137L0981997-03-25025 March 1997 Forwards Summary of Changes Made to Safeguards Review Rept, Rev 37 to St Lucie Physical Security Plan,Case Control Number N5S63VA50033593.W/o Encl ML20137L2311997-03-25025 March 1997 Forwards Summary of Changes Made to Safeguards Review Rept, Rev 47 to St Lucie Physical Security Plan,Case Control Number N5S76VA50033596.W/o Encl ML20136E9261997-03-0606 March 1997 Forwards SALP Input Feeder Info at St Lucie Facility from 940102-960106 & Requests That Technical Staff Complete Review by 951222 ML20136A9241997-02-28028 February 1997 Partially Withheld Memo Discussing drop-in Visit of J Broadhead,Chairman & CEO FPL Group & Chairman & CEO FP&L Co & J Goldberg ML20137L2751996-12-16016 December 1996 Requests Guidance in Addressing Issues Re Use of Temporary Fire Pump W/O Evaluation & Construction of Enclosure for Control Rod Drive Electronic Equipment within Cable Spreading Room,W/O Appropriate Evaluation ML20136A6751996-12-0909 December 1996 Partially Withheld Memo Discussing Directors Decision 96-19 Under 10CFR2.206 Re Steam Generator Issued at St Lucie ML20137R5381996-11-22022 November 1996 Informs That Rept IR 94-008 for St Lucie Opens Item 94-008-02-URI Quality Level of PORV & SRV Discharge Piping ML20136E6991996-11-19019 November 1996 Requests Info Re Sheron St Lucie Visit.Info Requested by 961120 ML20136E6221996-11-19019 November 1996 Informs That Draft in on Operator Activities Affecting Reactivity Being Distributed ML20136E6881996-11-18018 November 1996 Forwards Background Info on St Lucie Nuclear Instumentation Insp ML20136E6791996-11-18018 November 1996 Forwards Background Info on St Lucie Nuclear Instrumentation Insp ML20136E6081996-11-15015 November 1996 Provides List of Corrective Actions That Have Been Rolled Into Speakout Program ML20136E5461996-11-14014 November 1996 Forwards File Submitted to Kerry on 961024 Re PIM-like Summary of Events from 92-93 ML20136E4911996-11-13013 November 1996 Forwards Updated Schedule for St Lucie FY1 ML20140E5361996-11-12012 November 1996 Forwards Plant EA Worksheet ML20138G4131996-11-12012 November 1996 Requests Technical assistance,TIA-019,re Discrepancies Between Containment Radiation Monitoring Sys Described in Usfar & Regulatory Guide 1.45 at Plants ML20140E6591996-11-12012 November 1996 Provides Revs of Plant Violations for Current Hour ML20140E5301996-11-0808 November 1996 Forwards Input Received from Dan & Revised EA Worksheet from Incorporating Input.Few Slight Revs Were Made to Notice of Violation ML20140E6521996-11-0707 November 1996 Informs That D Barss Will Be e-mailing Input on Items 5 & 6 for Incorporation Into EA Worksheet ML20140E6201996-11-0707 November 1996 Provides Two Violations That Are Subjects of EA Worksheet ML20137R9031996-11-0606 November 1996 Requests That Info Re St Lucie Be Mailed to Author.Info May Be Found in Plan of Day Handout,Provided by Residents ML20140E5941996-11-0606 November 1996 Informs That Plant Violations 1 & 2 Re Emergency Prepardness Program Insp,Being Looked at for Escalated Enforcement.Feedback Requested ML20137Y5401996-11-0505 November 1996 Forwards Info on Two Issues to Be Discussed W/Panel at Meeting Scheduled for 961106.Partially Deleted ML20138G3651996-11-0505 November 1996 Requests That Listed Info Be Forwarded to Licensee in Connection W/Unescorted Access Visits to Plant by Listed NRC Contractor Employees During 961118-970110 for Purpose of Assisting NRC in Conduct of Design Insp.Partially Deleted ML20136E3011996-10-31031 October 1996 Forwards Schedule for Activities at Plant for Next Few Months ML20136E3961996-10-31031 October 1996 Informs That Violation Withdrawn Re Licensee Use of Ccw/Icw (Svc Water) in Mode 5 at Plant ML20136E4691996-10-31031 October 1996 Discusses Criticality Monitoring Ltr & Requests Response to Listed Question ML20140E5801996-10-29029 October 1996 Discusses EA Worksheet on Plant Re Wiring Error Affecting Nuclear Instrumentation ML20140E5191996-10-29029 October 1996 Discusses Addl Info for Plant Panel,Just Received from Inspector ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20140E5241996-10-29029 October 1996 Forwards Wordperfect Version as Requested ML20140E5901996-10-29029 October 1996 Forwards Enforcement Action Worksheet ML20136E5641996-10-28028 October 1996 Replies to News Summary Re Escalated Enforcement for Plant on 961025 IR 05000335/19950151996-10-28028 October 1996 Forwards Draft Insp Repts 50-335/95-15 & 50-389/95-15 on 960907-1012 ML20136E5791996-10-28028 October 1996 Discusses Plant Ni Eaw 1999-03-03
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20207L5671999-03-12012 March 1999 Forwards Facility Submitted Outline,Initial Exam Submittal & as Given Operating Exam for Test Administered on 981130,1204-14 & 18 ML20207E6091999-03-0303 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980622-26 ML20236Y6301998-08-0808 August 1998 Forwards Monthly Rept Reflecting Status of 10CFR2.206 Petitions as of 980731.Petitions on Plant GT97494 & GT97339 for Which DD Became Final Actions During Month Were Closed. Portion of Encl Withheld ML20237A0011998-08-0707 August 1998 Informs That Extension Granted on Envirocare Decision of 980904.Two Week Extension on Philadelphia VA Decision of 980828 Requested.Submits Concurrence of Changes.Rept on 2.206 July Status for Plants Encl ML20248L8621998-06-0909 June 1998 Forwards May 1998 Rept on Status of Public Petitioners Under 10CFR2.206.Petition on Seabrook (GT970873) for Which DD 98- 03 Became Final Agency Decision on 980413 Closed.Attachment 3 Withheld ML20203M6681998-02-23023 February 1998 Forwards SER Re TR CENPD-199-P,Rev 1-P-A,Suppl 2-P, CE Setpoint Methodology Proposing CRGR Review Be Waived IAW Suggested Procedures in 890929 Memo ML20202E0141997-11-25025 November 1997 Forwards FOIA Request Received Direct in Region II from E Barton on 971125.Encl Partially Deleted IA-97-461, Forwards FOIA Request Received Direct in Region II from E Barton on 971125.Encl Partially Deleted1997-11-25025 November 1997 Forwards FOIA Request Received Direct in Region II from E Barton on 971125.Encl Partially Deleted ML20205D4281997-08-15015 August 1997 Discusses Concern Identified During Special Design Architect-Engineer Insp Re EQ of Unit 1 Terry Turbine Woodward Governor Controls for Steam Turbine Driven Auxiliary Feedwater Pump IA-99-106, Discusses Concern Identified During Special Design Architect-Engineer Insp Re EQ of Unit 1 Terry Turbine Woodward Governor Controls for Steam Turbine Driven Auxiliary Feedwater Pump1997-08-15015 August 1997 Discusses Concern Identified During Special Design Architect-Engineer Insp Re EQ of Unit 1 Terry Turbine Woodward Governor Controls for Steam Turbine Driven Auxiliary Feedwater Pump ML20205M3331997-07-28028 July 1997 Provides Final Agenda for Region II Enforcement Meeting to Be Held on 970730.OI Attendance Requested for Issue Involving Termination of Turkey Point Radwaste Operator Who Failed to Follow Procedure IR 05000335/19970051997-07-17017 July 1997 Forwards Allegation Evaluation Rept & NRC Insp Repts 50-335/97-05 & 50-389/97-05 Re RII-97-A-0116 ML20202E0261997-04-23023 April 1997 Discusses Technical Staff Actions Associated W/Three Concerns in Allegation RII-96-A-0251 ML20137L2971997-03-31031 March 1997 Forwards Matrix Containing Answer to Listed Questions in ,Rev 1 ML20137R8831997-03-27027 March 1997 Provides Info Requested by 960208 Memo from J Stolz Re Review of Spent Fuel Pool Practices & Current Licensing Basis ML20137L0981997-03-25025 March 1997 Forwards Summary of Changes Made to Safeguards Review Rept, Rev 37 to St Lucie Physical Security Plan,Case Control Number N5S63VA50033593.W/o Encl ML20137L2311997-03-25025 March 1997 Forwards Summary of Changes Made to Safeguards Review Rept, Rev 47 to St Lucie Physical Security Plan,Case Control Number N5S76VA50033596.W/o Encl ML20136E9261997-03-0606 March 1997 Forwards SALP Input Feeder Info at St Lucie Facility from 940102-960106 & Requests That Technical Staff Complete Review by 951222 ML20136A9241997-02-28028 February 1997 Partially Withheld Memo Discussing drop-in Visit of J Broadhead,Chairman & CEO FPL Group & Chairman & CEO FP&L Co & J Goldberg ML20137L2751996-12-16016 December 1996 Requests Guidance in Addressing Issues Re Use of Temporary Fire Pump W/O Evaluation & Construction of Enclosure for Control Rod Drive Electronic Equipment within Cable Spreading Room,W/O Appropriate Evaluation ML20136A6751996-12-0909 December 1996 Partially Withheld Memo Discussing Directors Decision 96-19 Under 10CFR2.206 Re Steam Generator Issued at St Lucie ML20137R5381996-11-22022 November 1996 Informs That Rept IR 94-008 for St Lucie Opens Item 94-008-02-URI Quality Level of PORV & SRV Discharge Piping ML20136E6991996-11-19019 November 1996 Requests Info Re Sheron St Lucie Visit.Info Requested by 961120 ML20136E6221996-11-19019 November 1996 Informs That Draft in on Operator Activities Affecting Reactivity Being Distributed ML20136E6881996-11-18018 November 1996 Forwards Background Info on St Lucie Nuclear Instumentation Insp ML20136E6791996-11-18018 November 1996 Forwards Background Info on St Lucie Nuclear Instrumentation Insp ML20136E6081996-11-15015 November 1996 Provides List of Corrective Actions That Have Been Rolled Into Speakout Program ML20136E5461996-11-14014 November 1996 Forwards File Submitted to Kerry on 961024 Re PIM-like Summary of Events from 92-93 ML20136E4911996-11-13013 November 1996 Forwards Updated Schedule for St Lucie FY1 ML20140E5361996-11-12012 November 1996 Forwards Plant EA Worksheet ML20138G4131996-11-12012 November 1996 Requests Technical assistance,TIA-019,re Discrepancies Between Containment Radiation Monitoring Sys Described in Usfar & Regulatory Guide 1.45 at Plants ML20140E6591996-11-12012 November 1996 Provides Revs of Plant Violations for Current Hour ML20140E5301996-11-0808 November 1996 Forwards Input Received from Dan & Revised EA Worksheet from Incorporating Input.Few Slight Revs Were Made to Notice of Violation ML20140E6521996-11-0707 November 1996 Informs That D Barss Will Be e-mailing Input on Items 5 & 6 for Incorporation Into EA Worksheet ML20140E6201996-11-0707 November 1996 Provides Two Violations That Are Subjects of EA Worksheet ML20137R9031996-11-0606 November 1996 Requests That Info Re St Lucie Be Mailed to Author.Info May Be Found in Plan of Day Handout,Provided by Residents ML20140E5941996-11-0606 November 1996 Informs That Plant Violations 1 & 2 Re Emergency Prepardness Program Insp,Being Looked at for Escalated Enforcement.Feedback Requested ML20137Y5401996-11-0505 November 1996 Forwards Info on Two Issues to Be Discussed W/Panel at Meeting Scheduled for 961106.Partially Deleted ML20138G3651996-11-0505 November 1996 Requests That Listed Info Be Forwarded to Licensee in Connection W/Unescorted Access Visits to Plant by Listed NRC Contractor Employees During 961118-970110 for Purpose of Assisting NRC in Conduct of Design Insp.Partially Deleted ML20136E3011996-10-31031 October 1996 Forwards Schedule for Activities at Plant for Next Few Months ML20136E3961996-10-31031 October 1996 Informs That Violation Withdrawn Re Licensee Use of Ccw/Icw (Svc Water) in Mode 5 at Plant ML20136E4691996-10-31031 October 1996 Discusses Criticality Monitoring Ltr & Requests Response to Listed Question ML20140E5801996-10-29029 October 1996 Discusses EA Worksheet on Plant Re Wiring Error Affecting Nuclear Instrumentation ML20140E5191996-10-29029 October 1996 Discusses Addl Info for Plant Panel,Just Received from Inspector ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20140E5241996-10-29029 October 1996 Forwards Wordperfect Version as Requested ML20140E5901996-10-29029 October 1996 Forwards Enforcement Action Worksheet ML20136E5641996-10-28028 October 1996 Replies to News Summary Re Escalated Enforcement for Plant on 961025 IR 05000335/19950151996-10-28028 October 1996 Forwards Draft Insp Repts 50-335/95-15 & 50-389/95-15 on 960907-1012 ML20136E5791996-10-28028 October 1996 Discusses Plant Ni Eaw 1999-03-03
[Table view] Category:NRC TO ASLP
MONTHYEARML20247A7621989-03-24024 March 1989 Forwards Corrected Pages 15,24,25 & 26 to NRC 890317 Findings of Fact,Per Stated Clarifications & Corrections ML20151G5461988-07-26026 July 1988 Advises That Time for Commission to Review ALAB-893 Expired. Commission Declined Review.Decision Became Final Agency Action on 880725.Served on 880726 ML20150C6181988-03-17017 March 1988 Informs That Staff Made Final No Significant Hazards Determination & Issued Amend Expanding Facility Spent Fuel Storage Capacity to 1,706 Fuel Assemblies.Amend & Supporting Safety Evaluation Distributed by Encl 880311 Memo ML20149F1001988-02-0505 February 1988 Forwards Corrected Page to 880204 NRC Staff Response to Amended Petition to Intervene Re Spent Fuel Pool Expansion ML20236E0161987-10-16016 October 1987 Forwards C Rich Request for Hearing on Util Request for Amend to License DPR-67,for Appropriate Action.Served on 871020 1989-03-24
[Table view] |
Text
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MAR. 2 4 1989 789 liar 27 P3 :27 1
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-B.' Paul Cotter, Jr., Chairman Dr. Richard F. Cole Administrative Judge- Administrative Judge
. Atomic Safety and Licensing Atomic Safety and Licensing Board Panel Cocrd Panel U.S. Nuc16er Regulatory Connission U.S. Nuclear Regul6t.ory Connission Washington, D.C. 20555 Washington, D.C. 20555-Glenn 0. Bright Administrative Judge Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter cf FLORIDA POWER & LIGNT COMPANY (St. Lucie Plcnt, Unit No. 1)
Docket No. 50-335-01.A; ASLHP No. 883560-01-LA
Dear Administrative Judges:
TheNRCstaff(Staff)hasdiscoveredtwoareasofitsproposed"Findingsof Fact" (findings) filed in this' proceeding on March 17, 1989, which it, believes require clarification and correction. These are as follows:
- 1. The first sentence of paragraph 38 on page 15 presently states that:
- 38. The Staff and +.he Licensee have reviewed nud evaluated the performance records of Boraflex used in the storage racks at four facilities.
This sentence should be revised to read as follows:
- 38. The Staff has reviewed and evaluated the performance records of Boraflex used in the storage racks at four facilities.
In cddition, the fc110 wing record reference, ubich was inadvertently omitted on the final version of the Staff's findings, should be inserted following the above revised sentence.
Wing on Contention 3, ff Tr. at 4-5.
- 2. At line 6 of finding 57 on page 24, the last line on page 25 (finding 61) and the third line from the bottom of finding 61 on page 26 of the 8903290184 B90324 5 .
/j ADOCK 0500 -
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( l s findings, the Staff inadvertently stated that Dr. 5tanley E. Turner's criticality analyses assumed "one-half inch gaps every 6 inches in the Boraflex in the St. Lucie racks". The number "6"'should read "12" in all .
three of the above cited' places in the findings. (See Turner on
~
Contentions 3 and 6, ff Tr. 110 at 19 (fni).
The Staff inadvertently used the number "6" in its findings because it was focusing on the fact that the Boraflex sheets in region one have scallops or cut outs on each side. Each side has the scallop or c.at out twelve inches apart. However, the scallops or cut outs are not lined up directly on both sides of the Boraflex sheets. They are offset by six inches. (See, for example, Exhibit 10-Boraflex Panel in Region I, copy attached). However, the use of the number "6" in the context of the above-noted findjngs was, in fact, incorrect.
For the convenience of the Board and parties, enclosed are corrected pages 15, 24, 25 and 26 of the Staff's findings which include the above changes. These pages should be substitued for the current pages 15, 24, 25, and 26.
The Staff apologizes for any inconvenience caused by the above corrections to its findings.
Sincerely, fden. d bd/4 Patricia A. Jehle 8 Counsei for NRC Staff Encis.: As stated cc w!Encls.: Sarvice List l l
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- 37. We find that Boraflex is a material with proven neutron f ,
absorption characteristics and that minor degradations will not l
, significantly affect the. neutron attenuation capability of Boraflex. We g conclude that 'Boraflex is .a satisfactory poiron material and that it is ,
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, . t suitable for use in the Ett Lucie 1 spent fuel pool. In fact, the record il 1 amply demonstrated that trie naterial ~ ~ been subjected to testing environments more severe than environmental cs 41tions which will be encountered.in the St. Lucie 1 spent fuel pool, an ' still retained its I;eutron absorptt:n capability and physical integrity.
- 6. In Plant Performance of Boraflex
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- 38. The Staff has reviewed and evaluated the performance records of Boraflex used in the storage racks at four facilities. Wing on Contention 3, ff Tr. 110 at-4-5. The Staf f learned that gaps (separations) of up to 4 inches had formed in some k raflex panels at the Quad Cities Nuclear Power i
Station, Units 1 and 2.in April of 1987. Wing on Contention 3, Tr. 110, 1 l
at 3. The NRC I,1 formation Notice No. 67-43 " Gaps in Neutron Absorbin0 '
Material in High-Density Spent ftiel Storage Racks" (September 8, 1987) on I page 1:
)
"[A] lerted recipient; to a potentially significant problem
- _' pertaining to gaps identified in the neutron absorber component of the high density spent fuel storage racks 1
at Quad Cities Unit 1 [a BWR facility]. The safety concern ... [was] that certain gaps might excessively reduce the margin of nuclear subcriticality in the fuel pool." )
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f7. The NRC : staff did not' perform its own criticality analyses for ;
St. lucie because that is not generai practice in an NRC review of a' l4#6 I . kl .
licensee's sut,mittal for 3 spent fuel pool expansion. ' Testimony of.
Laurence 1 ,Kopp,' transcript at'495 [ hereinafter Kopp, Tr. at ). The' .]
s !
j Staff did not review the criticality analyses performed by Dr. Stanley E. ,,
~
l Turner, which assumed .oehalf inch. gaps every 12 inches in the Boraflex in the St. Lucie racks, because these were not ava'11able at the time the l j \
Staff conducted its' review. Kopp, Tr. at 530; s_ee gene; ally Tourigny, Tr.
]
i at 507-14. However,3 Maf f mecber reviewed the written direct testimony j q
and heard.the oral testimony of Dr. Stanley E. Turner on these criticality -)
analyses and concluded that there would be no adverse effect on k,ff which I ,
would violate the acceptance criteria of 0 295. Kopp, Tr. at 535. Dr. ]
Kopp olso reviewed generic criticality calculations and criticality calet:- i g
lations performed by the Staff for the Turkey Point Mant Units 3 and 4
-which verified these findir.gs. Kopp,.Tr. at 531-537. )
i
- 58. Although the various parameters such as U-235 enriche nt, fuel ;
l assembly center-to-center spacing and B-10 a m i density in these.
.]
calculations are not identicci to those in'the St. Lucie spent fuel recks, l
1, they are similar enough so that one would not expect changes in reactivity !
due to postulated varying gap size to be significantly different. Kopp, Ti. at 532. The base reactivity assuming no gaps would be dependent on
)
all of these parameters. Kopp, Tr. at 536. Changas in reactivity due to a given gap size, however, would not be dependent on these parameters.
Kopp, Tr. at 536. {
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- 59. An analysis of the reactivity consequerites of a physically ]
1 impossible condition, namely, the tote f 'ross of Boraflex in the storage j l
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, racks, was analyzed to demonstrate the very large reactivity margin in the 3
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St. Lucie 1 pool. . Turner on Contentions 3 ;ar.d 6, ff. TP. 139, at 9. With consideration of the double contingency principle and with credit for the soluble boron present, calculations for the hypothetical loss ~of all the i
Boraflex resulted in a maximum k,ff of 0.875 for Region 1 and 0.831 for e Region 2, both of which are still well below the limit of K eff 0.95.
, Turner on Contentions 3 and 6, ff. Tr. 139, at 9.
- 60. Prior to the issuance of the St. Lucie 1 spent fuel amendment, the design basis k,ff limit was 0.95. Turner on Contention 7, ff. Tr. 21, at 13. The spent fuel pool expansion did not modify this design basis limit. Turner on Contentions 3 and 6, ff. Tr.139, at 8d. Thus, the LRensee and the Staff have established on the record that the amendment has not decreased the margin of safety for preventing a criticality l sccident at St. Lucie 1. l
- 61. The central issue to be resolved is whether unsafe and unpredictable gap formation will develop in the St. Lucie 1 racks. The-Staff did not identify a mechanism for gap development based on the FSAR i
submitted by the Licensee. Wing, Tr. at 543-47. The Licensee, however, has postulated a possible mechanism for gap development in the St. Lucie 1 i
}"
storage racks; that is, the use of a cut-out design in conjunction with spot-welding every 12 inches along the sides of the Boraflex panels.
Singh, Tr. at 310-14. The Licensee has concluded that gaps may occur in a i
systematic pattern. Id. The Licensee's conclusion is based on additional analyses which were not available to the NRC when the Staff reviewed the FSAR enti prepared its SER and the written direct testimony. Tourigny Tr.
l at 507-14. Using a conservative assumption that 1/2 inch gaps every 12 I
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1n N inches, the Licensee established that the degree of gapping would not 11 effect reactivity in the~ spent fuel pool. Turner on-Contentions 3 and 6 j <
ff. Tr. ^139, at 6. Furthermore, the NRC staff evaluated the sworn written testimony and heard the oral testimony of the Licensee's witnesses which-described: 1) ths rack design in. detail; 2) the conservative' assumptions concerning gap formation; and 3) the effects on the reactivity of the -
pool. Kopp Tr. at 534-36; Tourigny, Tr. at 499-504, 507-14, 540-48; Wing Tr. at 544 45. The Staff concluded that'should the maximum-projected' gap formation, of 1/2 inch gaps every 12 inches, occur there will O '
be no criticality concern. .Kopp, Tr. at 534-36; Tourigny , Tr. at 540-48;-
' Wing, Tr. at 544-45.
62.- The Intervenor raised the issues that the Boraflex racks at St.
Lucie 1 spent fuel pool 1) use a significantly modified. design and are-essentially the result of new. technology and fabrication process; 2) that the'designis.unprovenanduntested;3)thatgapformationproblems-reported with in-service Boraflex panels at other plants are unresolved; l
and 4) that gap formation, the separation of neutron absorbing material, may compromise safety. The Licensee established _that both the design and the materials used to fabricate the St. Lucie'I spent fuel pool racks are based on established technology which has been tested. The Licensee also established that the reported incidents of gapping have been resolved and that gapping will not compromise safety.
- 8. Licensee's In-Service Surveillance Program
- 63. Boraflex is a satisfactory neutron absorber, capable of performing its intended function of criticality control, Turner on ;
Contentions 3 and 6, ff. Tr. 139, at 15. The Licensee and the Staff
- _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _