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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17241A5001999-10-21021 October 1999 Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C ML17309A9981999-10-19019 October 1999 Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points ML20217F6171999-10-0808 October 1999 Forwards Insp Repts 50-335/99-11 & 50-389/99-11 on 990827 & 990907-09.No Violations Identified.Matl Encl Contained Safeguards Info as Defined by 10CFR73.21 & Disclosed to Unauthorized Individuals Prohibited by Section 147 of AEA ML17241A4811999-10-0101 October 1999 Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a ML20212M1601999-09-28028 September 1999 Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl ML17241A4701999-09-25025 September 1999 Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant ML17241A4721999-09-24024 September 1999 Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999 ML17241A4681999-09-22022 September 1999 Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6) ML17241A4671999-09-20020 September 1999 Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. ML17241A4581999-09-13013 September 1999 Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program ML17241A4531999-08-31031 August 1999 Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006 ML17241A4521999-08-31031 August 1999 Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval ML17241A4501999-08-26026 August 1999 Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached ML17241A4371999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d) ML17241A4461999-08-11011 August 1999 Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999 Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3) ML17309A9911999-07-26026 July 1999 Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified ML17241A4471999-07-22022 July 1999 Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure ML17241A4221999-07-22022 July 1999 Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. ML17241A4151999-07-22022 July 1999 Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2 ML17241A4101999-07-16016 July 1999 Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17309A9881999-07-0707 July 1999 Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager ML20209F1541999-07-0606 July 1999 Informs That NRC in Process of Conducting Operational Safeguards Response Evaluations at Nuclear Power Reactors. Plant Chosen for Such Review Scheduled for Wk of 990823-26 ML17241A4011999-06-30030 June 1999 Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604 ML17241A3971999-06-30030 June 1999 Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17241A3951999-06-29029 June 1999 Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML17241A3731999-06-17017 June 1999 Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16) ML17241A3641999-06-14014 June 1999 Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139 ML20195F3871999-06-11011 June 1999 Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5) IA-99-247, Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)1999-06-11011 June 1999 Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5) L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999 Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3) ML17241A3561999-06-0707 June 1999 Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209 ML17241A3601999-06-0707 June 1999 Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998 ML20195F3941999-05-27027 May 1999 FOIA Request That Memo from J Calvo to Fl Lebdon Re TIA - St Lucie,Unit 1 Environ Qualification of Woodward Governor Controls Be Placed in PDR ML17241A3461999-05-24024 May 1999 Forwards Revised Relief Request 22 to Clarify Several Areas of Relief.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage ML17241A3391999-05-20020 May 1999 Forwards Notification of Change to Small Break LOCA ECCS Evaluation Model Used for St Lucie Unit 1.Anomaly Was Discovered & Corrected That Resulted in Reducing Calculated PCT for Limiting SBLOCA by More than 50 F ML17241A3371999-05-20020 May 1999 Forwards Util Suppl to GL 95-07 Response Re pressure-locking & Thermal Binding of safety-related power-operated Gate Valves,In Response to NRC Second RAI Dtd 990225 ML20207C7531999-05-17017 May 1999 Discusses Issue Identified by FPL in Feb 1998 Involving Potential for Fire to Cause Breach of Rc Sys High/Low Pressure Interface Boundary & NRC Decision for Exercise of Enforcement Discretion ML17241A3301999-05-17017 May 1999 Forwards LER 99-004-00 Re as Found Cycle 10 Psv Setpoints Outside TS Limits,Which Occurred on 990415.Root Cause Determination Not Yet Complete.Suppl to Include Root Cause & Corrective Actions Will Be Submitted ML17309A9821999-05-10010 May 1999 Forwards Rev 36 to St Lucie Emergency Plan, Per 10CFR50.54(q).Executive Summary & Summary of Changes Incorporated by Rev,Encl IR 05000335/19980141999-04-29029 April 1999 Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated ML17241A3221999-04-29029 April 1999 Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated ML17229B1071999-04-28028 April 1999 Forwards 1998 Annual Environ Operating Rept for St Lucie Unit 2. Rept Includes Discussions of 5-inch Barrier Net Maint & Taprogge Condenser Tube Cleaning Sys Ball Loss,As Agreed at First Biennial Sea Turtle Meeting Held on 980120 ML17229B1051999-04-22022 April 1999 Requests That Listed Individuals Be Placed on Official Serve List for Nuclear Matl Safety & Safeguards Info Notices ML17229B1061999-04-21021 April 1999 Notifies NRC of Change in Medical Status of Licensed Operator Pf Farnsworth (Docket 55-21285,license SOP-21094). NRC Form 3996, Medical Exam Certification, Encl.Encl Withheld Per 10CFR2.790(a)(6) ML17309A9851999-04-15015 April 1999 Requests That NRC Review Denial of Appeal from Assessment of Fees Assessed in 981101 Invoice RS0062-99 & Assessment of Fees in Invoice RS0182-99 Which Was Also Denied in 990305 Ltr.Both Invoices Are for Fees Re Inspector GG Warnick ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML17229B0951999-04-0808 April 1999 Requests Approval of Encl Revised Relief Request 6,in Response to 990322 Telcon with NRC & 10CFR55.55a(a)(3). Request States That Visual VT-3 Exams Will Be Conducted IAW IWA-2213 & Repairs Will Be IAW Util ASME Section IX Program ML17229B0821999-04-0707 April 1999 Requests Approval of Interim Relief Request 26 Re Repair Requirements for Class 2 ECCS Piping,Per 10CFR50.55a(a)(3) & 50.55a(g)(iii).Alternative Actions Apply Guidance of GLs 91-18 & 90-05 & ASME Code Case N-513.Evaluation,encl 1999-09-28
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17241A5001999-10-21021 October 1999 Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C ML17309A9981999-10-19019 October 1999 Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points ML17241A4811999-10-0101 October 1999 Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a ML17241A4701999-09-25025 September 1999 Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant ML17241A4721999-09-24024 September 1999 Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999 ML17241A4681999-09-22022 September 1999 Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6) ML17241A4671999-09-20020 September 1999 Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. ML17241A4581999-09-13013 September 1999 Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program ML17241A4531999-08-31031 August 1999 Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006 ML17241A4521999-08-31031 August 1999 Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval ML17241A4501999-08-26026 August 1999 Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached ML17241A4371999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d) ML17241A4461999-08-11011 August 1999 Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999 Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3) ML17309A9911999-07-26026 July 1999 Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified ML17241A4221999-07-22022 July 1999 Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. ML17241A4471999-07-22022 July 1999 Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure ML17241A4151999-07-22022 July 1999 Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2 ML17241A4101999-07-16016 July 1999 Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17309A9881999-07-0707 July 1999 Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager ML17241A4011999-06-30030 June 1999 Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604 ML17241A3971999-06-30030 June 1999 Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17241A3951999-06-29029 June 1999 Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML17241A3731999-06-17017 June 1999 Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16) ML17241A3641999-06-14014 June 1999 Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139 L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999 Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3) ML17241A3601999-06-0707 June 1999 Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998 ML17241A3561999-06-0707 June 1999 Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209 ML20195F3941999-05-27027 May 1999 FOIA Request That Memo from J Calvo to Fl Lebdon Re TIA - St Lucie,Unit 1 Environ Qualification of Woodward Governor Controls Be Placed in PDR ML17241A3461999-05-24024 May 1999 Forwards Revised Relief Request 22 to Clarify Several Areas of Relief.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage ML17241A3371999-05-20020 May 1999 Forwards Util Suppl to GL 95-07 Response Re pressure-locking & Thermal Binding of safety-related power-operated Gate Valves,In Response to NRC Second RAI Dtd 990225 ML17241A3391999-05-20020 May 1999 Forwards Notification of Change to Small Break LOCA ECCS Evaluation Model Used for St Lucie Unit 1.Anomaly Was Discovered & Corrected That Resulted in Reducing Calculated PCT for Limiting SBLOCA by More than 50 F ML17241A3301999-05-17017 May 1999 Forwards LER 99-004-00 Re as Found Cycle 10 Psv Setpoints Outside TS Limits,Which Occurred on 990415.Root Cause Determination Not Yet Complete.Suppl to Include Root Cause & Corrective Actions Will Be Submitted ML17309A9821999-05-10010 May 1999 Forwards Rev 36 to St Lucie Emergency Plan, Per 10CFR50.54(q).Executive Summary & Summary of Changes Incorporated by Rev,Encl ML17241A3221999-04-29029 April 1999 Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated IR 05000335/19980141999-04-29029 April 1999 Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated ML17229B1071999-04-28028 April 1999 Forwards 1998 Annual Environ Operating Rept for St Lucie Unit 2. Rept Includes Discussions of 5-inch Barrier Net Maint & Taprogge Condenser Tube Cleaning Sys Ball Loss,As Agreed at First Biennial Sea Turtle Meeting Held on 980120 ML17229B1051999-04-22022 April 1999 Requests That Listed Individuals Be Placed on Official Serve List for Nuclear Matl Safety & Safeguards Info Notices ML17229B1061999-04-21021 April 1999 Notifies NRC of Change in Medical Status of Licensed Operator Pf Farnsworth (Docket 55-21285,license SOP-21094). NRC Form 3996, Medical Exam Certification, Encl.Encl Withheld Per 10CFR2.790(a)(6) ML17309A9851999-04-15015 April 1999 Requests That NRC Review Denial of Appeal from Assessment of Fees Assessed in 981101 Invoice RS0062-99 & Assessment of Fees in Invoice RS0182-99 Which Was Also Denied in 990305 Ltr.Both Invoices Are for Fees Re Inspector GG Warnick ML17229B0951999-04-0808 April 1999 Requests Approval of Encl Revised Relief Request 6,in Response to 990322 Telcon with NRC & 10CFR55.55a(a)(3). Request States That Visual VT-3 Exams Will Be Conducted IAW IWA-2213 & Repairs Will Be IAW Util ASME Section IX Program ML17229B0821999-04-0707 April 1999 Requests Approval of Interim Relief Request 26 Re Repair Requirements for Class 2 ECCS Piping,Per 10CFR50.55a(a)(3) & 50.55a(g)(iii).Alternative Actions Apply Guidance of GLs 91-18 & 90-05 & ASME Code Case N-513.Evaluation,encl ML17229B0851999-04-0505 April 1999 Requests Approval of Encl Relief Request 25 Which Proposes to Use Alternative Requirements of ASME Code Case N-613 in Lieu of Requirements of ASME Section XI Figures IWB-2500-7(a) & IWB-2500-7(b).Action Requested by Aug 1999 ML17309A9791999-03-31031 March 1999 Forwards Revised EPIPs Including Rev 2 to EPIP-00,rev 2 to EPIP-09,rev 2 to EPIP-10 & Rev 10 to HP-207.Summary of Revs Listed ML17309A9761999-03-23023 March 1999 Forwards Revised Epips,Including Rev 4 to EPIP-03, Er Organization Notification/Staff Augmentation, Rev 3 to EPIP-05, Activation & Operation of OSC & Rev 14 to HP-200, HP Emergency Organization. Changes to Epips,Discussed ML17229B0691999-03-19019 March 1999 Transmits TS Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity,Per Soluble Boron Credit ML17229B0721999-03-16016 March 1999 Requests Approval of Enclosed Relief Requests 23 & 24 Re ISI Plan for Second ten-year Interval.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML17229B0481999-03-10010 March 1999 Informs That Util Delivered Matls Requested in Encl 1 of NRC Ltr by Hand on 990308,as Requested by NRC Ltr Dtd 990218 1999-09-25
[Table view] Category:UTILITY TO NRC
MONTHYEARML17223A9401990-09-13013 September 1990 Forwards Evaluation of Potential Safety Impact of Failed Control Element Assemblies on Limiting Transients for Facility ML17223A9341990-09-10010 September 1990 Forwards Addl Info Re Generic Implications & Resolution of Control Element Assembly (CEA) Failure at Facility,Per NRC Request.Description of Testing Program for Old Style CEAs in Unit 1 Core Encl L-90-315, Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 81990-08-30030 August 1990 Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 8 ML17223A9201990-08-28028 August 1990 Forwards Forms NIS-1 & NIS-2, Owners Rept for Inservice Insps as Required by Provisions of ASME Code Rules, Per 900725 Ltr ML17223A8911990-08-20020 August 1990 Forwards Corrected Monthly Operating Repts for Jul 1990 for St Lucie Units 1 & 2 & Summary of Operating Experience ML17348A5041990-08-17017 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990 L-90-301, Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant1990-08-16016 August 1990 Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant ML17223A8751990-08-0909 August 1990 Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor IR 05000335/19900141990-08-0909 August 1990 Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor ML17348A4701990-07-27027 July 1990 Forwards Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per Unsatisfactory Performance Testing ML17223A8621990-07-25025 July 1990 Advises That NIS-1 & NIS-2 Forms,As Part of Inservice Insp Rept,Will Be Submitted by 900831 ML17348A4281990-07-25025 July 1990 Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b) ML17223A8631990-07-25025 July 1990 Submits Addl Info Re Implementation of Programmed Enhancements Per Generic Ltr 88-17, Loss of Dhr. All Mods for Unit 1 Completed & Operational.Mods for Unit 2 Schedule for Upcoming Refueling Outage L-90-271, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders1990-07-20020 July 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders ML17223A8581990-07-19019 July 1990 Forwards Implementation Status of 10CFR50.62 Mod at Facility Re Requirements for Reduction of Risk from ATWS Events for Light Water Cooled Nuclear Power Plants ML17223A8491990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Transmitters Models 1153 Series B,1153 Series D & 1154 Mfg Prior to 890711 Supplied by Different Vendor ML17223A8521990-07-17017 July 1990 Forwards Addl Info Requested Re Generic Implications & Resolution of Control Element Assembly Failure at Plant.Encl Confirms Util Intent to Follow C-E Regulatory Response Group Action Program IR 05000335/19900131990-07-0909 July 1990 Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements ML17223A8421990-07-0909 July 1990 Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements ML17348A3881990-07-0505 July 1990 Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs ML17223A8391990-07-0303 July 1990 Forwards Results of Beach Survey Procedure & Reduction of Field Survey Data,Per Tech Spec 4.7.6.1.1.Unit 1 Updated Fsar,Section 2.4.2.2,concluded That Dune Condition Acceptable Per Tech Spec 5.1.3 ML17223A8381990-07-0202 July 1990 Requests Termination of Operator License for s Lavelle.Util Also Requests That Ltr Be Withheld (Ref 10CFR2.790) L-90-239, Forwards Rev 6 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990 Forwards Rev 6 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21) ML17223A8371990-06-27027 June 1990 Provides Details of Implementation Plan Re Recommendations & Schedular Requirements in Generic Ltr 89-10,per 891228 Ltr.Design Basis Review of safety-related motor-operated Valves & Determination of Switch Settings in Progress ML17308A4981990-06-27027 June 1990 Responds to Generic Ltr 90-04 Re Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML17223A8341990-06-19019 June 1990 Forwards Corrected Proposed Tech Spec Figure 3.4-2 Per 900207 Application for Amend to License NPF-16,incorporating Revised Pressure/Temp Limits & Results of Revised Low Temp Overpressure Protection Analysis Into Tech Specs ML17223A8241990-06-18018 June 1990 Forwards Revised Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1988. ML17223A8271990-06-18018 June 1990 Forwards Ma Smith 900601 Ltr to WR Cunningham of EPA Requesting Mod to Plant NPDES Permit to Permit Cleaning of Facility & to Establish Discharge Limits for Chemical Cleaning Wastes ML17348A2981990-06-12012 June 1990 Forwards Rev 16 to Topical QA Rept. ML17223A6761990-05-31031 May 1990 Advises That Air Operated safety-related Components Will Perform All Design Basis Events,Per 881227 Ltr.All Actions Required by Generic Ltr 88-14 Complete for Plant ML17348A2651990-05-29029 May 1990 Submits Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per 10CFR26,App A.2.8(e)(4) ML17223A6741990-05-22022 May 1990 Forwards Info Re Status of 10CFR50.62 Mods to Meet ATWS Requirements as of 900515.Plant Change/Mod Package Necessary for Installing ATWS Will Be Issued by 900630.Hardware Procurement for Diverse Scram Sys Approx 90% Complete ML17223A6361990-05-0808 May 1990 Forwards Final Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. One Untraceable Circuit Breaker Installed in Unit 2 Qualified SPDS & Replaced W/Traceable Breaker ML17223A6281990-04-21021 April 1990 Forwards St Lucie Unit 2 Annual Environ Operating Rept, Vol 1 1989. ML17223A6081990-04-13013 April 1990 Responds to Violations Noted in Insp Repts 50-335/90-02 & 50-389/90-02.Corrective Actions:Nuclear Plant Supervisor Required to Remain in Control Room During Significant Changes in Power Operation & Preventive Maint Upgraded ML17223A6071990-04-0505 April 1990 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. Removal & Replacement of Cold Leg Side Plugs of Heat Number 3513 for Unit 1 Completed During Refueling Outage ML17308A4911990-04-0202 April 1990 Forwards Description & Summary of Safety Evaluations of Plant Changes/Mods Reportable Per 10CFR50.59.Repair &/Or Replacement of Protective Coatings on Surfaces Inside Bldg Pose No Unreviewed Safety Question ML17223A5931990-03-30030 March 1990 Forwards Status of 10CFR50.62, Requirements for Reduction of Risk from ATWS Mods at Plant as of 900315.Diverse Scram Sys Module Prototype Fabrication in Progress ML17223A5921990-03-27027 March 1990 Forwards Addl Info on Proposed License Amend Re Increased Max Allowable Resistance Temp Detector Delay Time,Per 891219 Telcon & Advises That Util Request to Increase Plant Resistance Temp Detector Response Time Remain Unchanged ML17223A5831990-03-19019 March 1990 Forwards Response to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implications of Control Sys in LWR Nuclear Power Plants,' Per 10CFR50.54(f) ML17347B6191990-03-13013 March 1990 Provides Listing of Property Insurance Programs ML17223A5531990-03-0909 March 1990 Submits Results of Investigation of Error Detected in Dose Assessment During 900124 NRC Evaluated Exercise at Plant. Operator Error Caused Keyboard Hangup Requiring Computer Restart ML17223A5451990-03-0808 March 1990 Forwards Revised Tech Specs Re Steam Generator Tube Repairs, Per 890602 Telcon & Subsequent Discussions W/Nrc ML17308A4871990-03-0707 March 1990 Forwards Response to Eight Audit Questions & Licensing Bases Criteria to Resolve Station Blackout Issue.Util Currently Has Procedures to Mitigate Effects of Hurricanes & Tornados Which Meet or Exceed NUMARC 87-00 Guidelines ML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML17347B6031990-02-27027 February 1990 Requests Approval to Use Code Case N-468 at Plants ML17223A5321990-02-26026 February 1990 Forwards CEN-396 (L)-NP, Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2. ML20012A0011990-02-26026 February 1990 Notifies That Followup Actions Completed on Schedule & Incorporated Into Rev 25 to Plant Physical Security Plan,Per NRC 890605 Request ML17223A5411990-02-26026 February 1990 Provides Addl Info Re Proposed License Amends Re Moderator Temp Coefficient Surveillance Requirements,Per 891026 & 900109 Telcons IR 05000335/19890241990-02-22022 February 1990 Responds to Violations Noted in Insp Repts 50-335/89-24 & 50-389/89-24.Corrective Actions:Applicable Procedures Changed to Clarify Which Spaces & Blocks Required to Be Completed on Plant Work Order & QC Supervisor Counseled 1990-09-13
[Table view] |
Text
ACCELERATED DISOIBUTION DEMONSTRCi'ION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR-8807010691 DOC.DATE: 88/06/23 NOTARIZED: NO DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335
. 50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION CONWAY,W.F. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION STELLO,V. Ofc of the Executive Director for Operations
SUBJECT:
Responds to Questions 471.5 471.12 re App A exemption request for worker respiratory protection apparatus.
DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR (
Submittal: General Distribution ENCL J SIZE: ( g NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 5 5 TOURIGNY,E 1 1 INTERNAL: ACRS 6 6 ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/PMAS/ILRB12 OGC 15-B-18 RES/DE/EIB l,l 1
1 1,1 1
1 1
0 NRR/DEST/MTB 9H
-NRR/DOEA/TSB 11 NUDOCS-ABSTRACT 01 1
1 1
1 1
1 1
1 EXTERNAL: LPDR 1 1 NRC PDR ~ 1 1 NSIC 1 1 R
I'~
D '"
'A f
TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 25
P. 0 X 14000, JUNO BEACH, FL 33408-0420
+Iu/o
+~AN+
e JUNE 2 3 1988 L-88-280 10 CFR 20.501 10 CFR 20.7 Mr. Victor Stello, Jr.
Executive Director for Operations U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
Dear Mr. Stello:
Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Request for Additional Information 10 CFR 20 Appendix A Exemption Request for Worker Respiratory Protection A aratus TAC Nos. 67138 and 67139 By NRC letter dated March 16, 1988, the Staff requested additional information relating to the above subject for St.
Lucie Plant, Unit Nos. 1 and 2.
The purpose of this letter is to provide the second set of responses. The first set of responses was provided in Florida Power 6 Light Company's letter L-88-209, dated May 5, 1988. This submittal provides responses to Questions 471.5, 471.6, 471.7, 471.9, 471.11 and 471.12.
Should there be further questions, please contact us.
Very truly yours, W. . Con y Senior Vice President Nuclear Enclosures WFC/MSD/gp cc: Dr. J. Nelson Grace, Regional Administrator, Region USNRC II, Senior Resident Inspector, USNRC, St. Lucie Plant goo/
MSDAASS . RAI SS0701069i SS0623 PDR ADOCK 05000335 p DCD an FPL Group company
~ ~m1 4
QUESTION 473..5 Provide a description of the SCOTT 631-TEDA-H canister including particulate filter, sorbent and percent TEDA.
Address the question of the potential toxic hazard to the respirator user from inhalation of TEDA desorbed from the SCOTT 631-TEDA-H canister. Describe the criteria for use of these SCOTT canisters at St. Lucie (e.g., radioiodine concentration, canister labeling, prevention of canister reuse).
RESPONSE
A. Descri tion of SCOTT 631-TEDA-H Canister The 631-TEDA-H chin style gas mask canister is constructed using a 12 x 20 mesh (U. S. Sieve series) activated carbon, impregnated with 54 by weight triethylenediamine (TEDA), and a high efficiency particulate air (HEPA) filter.
construction.
Figure 1, attached, depicts the canister The sorbent in the canister is batch certified to meet the ASTM D3803 and D4069 radioiodine performance requirements.
The"volume it occupies within the canister"is'340 cc's.
The HEPA filter is a radially pleated high efficiency filter with greater than 99.97% removal efficiency against a 0.3 micrometer dioctylphthalate (DOP) aerosol.
Canisters are 1004 tested for DOP removal efficiency at the time of manufacture per NIOSH respirator certification requirements of 30 CFR Part 11.
B. Potential Hazard from Desor tion of TEDA Studies have been performed on the desorption characteristics of TEDA from impregnated activated carbons. It has been found that the desorption rate of TEDA is not a function of the linear flow rate or sorbent bed depth within the canister. However, desorption rates are linearly related to temperature on a semi-log plot.
At 48.9'C (120'F) a maximum TEDA desorption rate of approximately 2 mg/m has been measured (1) .
There 's no toxicological data available for TEDA, however, there are similarities between other amine type compounds. A sample of several compounds and their threshold limit values are given below (2):
MSDAASS. RAI
(mg/m3) (ppm)
Ethylamine 18 10 Diethylamine 30 10 Triethylamine , 40 10 Ethylenediamine "'25 10
'iethylene/triamine 4 1 The 2 mg/m, desorption value at 48.9'C is 'well below the lowest threshold limit 'value for similar',type substances and therefore should not present a toxic hazard to the user.
C. Use of SCOTT Canisters at St. Lucie FPL does not plan to reuse the canisters after initial use. All canisters will be removed after use and discarded to prevent any further use. The canisters will not be used when the radionuclide concentrations of radioiodines, particulates or a combination of each exceed 50 times the applicable limit for the radionuclides in question in 10 CFR 20 Appendix B, Table I Column 1 as described in 10 CFR 20.103.c.1. FPL does not plan on any labeling outside the labeling required to show compliance to NIOSH/MESA requirements.
QUESTION 471.6 The FPL submittal includes tabular summaries of test conditions and test results provided by SCOTT for the SCOTT 631-TEDA-H canister but contains no other information on these tests or on the means for ensuring the reliability of the tests and test results. Provide a complete description and discussion of the test program (including apparatus used), the means for ensuring the reliability of the tests and the test results, and the basis for your acceptance of the test results. Include the complete name and address of the manufacturer (SCOTT) and the identification of the organization or group that actually performed the tests, other than SCOTT.
if
RESPONSE
A. Canister Test S stem Descri tion A sketch depicting the test system used to determine the performance of the SCOTT 631-TEDA-H canisters against methyl iodide is shown in Figure 2. The primary MSDAASS.RAI
t E
components and key features. of the system include:
~ Detection S stem:
Gas chromatograph equipped with an electron capture detector for measuring methyl iodide concentrations in the canister effluent. The chromatograph is calibrated against CH3I using two independent techniques. The first technique employs a permeation tube while the second technique was by volume dilution. Excellent agreement between the two methods was realized.
~ Tem erature Humidit Flow S stem:
A modified Miller-Nelson (MN-301) airflow, temperature and humidity controller is employed for generation and control of the humidified air. The MN-301 unit delivers air at the desired temperature and flow rate to a humidity vessel.'s" ,the air passes through the water vapor laden headspace of the vessel, air-stream humidification and final air heating is accomplished.
The temperature and humidity of the air stream is monitored using an optical dew point hygrocomputer.
The hygrocomputer is located in the thermal enclosure for monitoring the air immediately prior to entering the canister inlet.
~ Meth l Iodide Generation:
A syringe pump is used to generate the methyl iodide challenge concentrations of interest. Capability for generating challenge concentrations using this method was verified using a Miran 1A infrared analyzer and the gas chromatograph. Concentrations generated throughout the test program are verified using volumetric displacement measurement techniques and by use of the chromatograph.
~ Challen e Atmos here Deliver Due to the high temperature and water vapor concentration of the airstream, in-line condensation in the transfer tubing was eminent unless appropriate measures were taken to prevent this condition. A heated enclosure was utilized to contain the canisters, the stream selector valve (which selected the appropriate air stream to be sampled) and the hygrocomputer.
Temperature of the enclosure is set and controlled to the same temperature as the challenge airstream (i.e.
120 F or 100'F). Water vapor condensation is thereby eliminated. No temperature gradients were observed in the thermostated enclosure. A radial manifold is used MSDAASS.RAI
~ \
~l
'\
L D
for distribution of the flow to the test canisters.
Three solenoid valves controlled by an electronic timer unit allows for 192 lpm airflow delivery to each canister for 0.82 seconds and 0 lpm flow for 1.64 seconds (equivalent to a 64 liter minute volume). A pressure vs. time history of each flow segment is used to verify system pressure symmetry (i. e. flow), correct operation of the solenoid valves and "squareness" of the pulsed waveform. A fast response pressure transducer is used for these pressure measurements.
~ S stem Control:
The "brain" of the system is the computing integrator which controls information flow in the instrument network loop (INET). A basic program was written and loaded into the integrator for control of the INET system operation. The program dictates which canister is to be sampled and at what. time. The sampler event control module positions the stream selector valve to the appropriate location for canister effluent sampling.
After the sample is processed by the chromatograph, the integrator computes the amount of methyl iodide in the air and stores the information. At the end of the test, the stored data is loaded into the IBM PC/AT for further analysis, presentation and storage.
B. Discussion of the Test Pro ram As a result of the symmetry in the pulsed cycle (flow for 0.82 seconds, no flow for 1.64 seconds), this pattern lends itself to simultaneous testing of three canisters.
In some instances, data from one or more of the test stations (i.e. number 1, 2 or 3) is not reported in the data tabulations as they related to either empty stations or stations which were used to evaluate prototype product.
Another important feature of the test program was that the detector in the chromatograph was calibrated routinely to monitor and correct for deterioration of the cell. The cell deterioration is caused by oxygen present in the sampled air stream from the canister effluent.
C. Reliabilit of Test Results Data on the performance characteristics of various air purifying respirator cartridges or canisters for methyl iodide exists (3,4). However, data on the performance of the SCOTT 631-TEDA-H canister at the test conditions of interest has not been previously reported. Therefore by comparison of the data enclosed in this exemption request with previously published data, a correlation can be MSDAASS.RAI
established which substantiates the SCOTT results. These conclusions are summarized below:
~ Test data on the SCOTT P/N 600252-75 canister which contained 305 cc of 8 x 16 mesh, 5% TEDA carbon, tested with air at 64 lpm constant flow, 25'C, 974 R.H. was greater than 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to 14 penetration.
The SCOTT 631-TEDA-H canister with 340 cc of 12 x 20 mesh, 54 TEDA carbon provides 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> duration to 14 penetration. Test conditions were 64 lpm constant flowi 48 ' Ci 904 R H.
Due to the increased sorbent volume and smaller sorbent particle size distribution, improved canister performance has been realized in the 631-TEDA-H canisters.
~ It has been reported in the published data that service life of air purifying canisters decrease with increased relative humidity of the air stream. Performance of the 631-TEDA-H canister was 13.7 hrs. at 904 R.H and 23.9 hrs. at 60% R.H. (48.9'C, pulsed flow conditions, Co =
10 ppm). This trend is also consistent with the published data.
~ Under steady flow conditions, time to a 1: penetration fraction is greater than under cyclic (pulsed) flow conditions for equivalent minute volumes. For the 631-TEDA-H canister, steady flow conditions provided times approximately 2 times greater than pulsed flow tests.
This result is also consistent with the published data.
~ Other tests were performed by SCOTT (not reported in the exemption request) under steady flow conditions, with various methyl iodide challenge concentrations and with a 60 cc sorbent bed volume. The test results demonstrated that for steady flow, removal efficiency was independent of the challenge concentration.
Penetration fractions with time remained identical over the 0.5 3.0 ppm concentration range of interest.
This result has also been previously reported in the literature.
Therefore, by correlation of SCOTT test results with previously reported data, reliability of the SCOTT results has been demonstrated.
D. Test Location All the methyl iodide tests were performed by SCOTT Aviation, 225 Erie Street, Lancaster, NY 14086.
MSDAASS.RAI
QUESTION 471.7 Describe how the quality and function of the SCOTT 631-TEDA-H canisters will be verified by Florida Power & Light Company (FPL). It is the utility s responsibility to ensure that canister performance and quality are fully adequate through such measures as verification of vendor quality assurance/quality control (QA/QC) and through development of utility/site QA/QC procedures which provide a continuing assurance of canister quality. (a) Include a general discussion of any vendor audits performed, or outline the basis for, your acceptance of, vendor QA/QC controls for the SCOTT 631-TEDA-H, canisters. (b) Cite general controls and procedures related to SCOTT 631-TEDA-H canister QA/QC to be utilized at St. Lucie by FPL. (c) Clarify the "Equilibration" entry for the "SCOTT RADIOIODINE PROPOSAL" in Table A of Attachment 1 of the FPL submittal. Clarify how and by whom the "Quality Control Lot Acceptance Plan..."
(Attachment 3 of the FPL submittal) has been and is to be used; verify that only the SCOTT 631-TEDA-H canisters from lots accepted under this MIL-STD 414 acceptance plan will be used at St. Lucie by FPL.
RESPONSE
A. ualit Control Lot Acce tance Plan The Q.C. lot acceptance plan will be employed by SCOTT Aviation on each manufacturing lot of 631-TEDA-H canisters produced. Therefore, all canisters consumed by FPL will have been tested per the requirements of the Q.C. plan.
MIL-STD-414, level II, AQL 14 the number of canisters needed will be used to determine for testing based on lot size with acceptability criteria based on canister performance results. The canister test conditions would be as follows:
Air Temperature, 4 Relative Humidity 120F /904 R. H.
Airflow rate conditions 192 lpm for 0.82 seconds 0 lpm for 1.64 seconds Contaminant/Concentration CH3I/10 ppm Test Duration 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Performance Criteria 14 maximum penetration An improved test procedure and lot acceptance plan is MSDAASS.RAI
0 being investigated. The improved test procedure will be devised with the intent of being capable of verifying the acceptability of a manufacturing lot of canisters.
However, the test conditions will not be as severe as the qualification test . conditions. Future work will be directed toward constant flow and high methyl iodide challenge concentrations. Correlation between the qualification test results and the new test condition results will be accomplished.
B. A C General Controls FPL will accept only those canisters that have been certified by SCOTT as meeting the acceptance criteria of the MIL-STD 414 acceptance plan. FPL will perform a receipt inspection of each shipment of the canisters to verify lot number, expiration date of the canisters and physical integrity of the canisters. SCOTT will be required to provide to FPL the results of the acceptance testing for each lot of the canisters that FPL purchases from SCOTT. 'I lt C. Equilibration The SCOTT test program tested canisters without pre-conditioning air flow through the canister.
QUESTION 471.9 The FPL submittal states that the SCOTT canisters are to be stored in sealed, humidity barrier packaging, but does not specify whether the canisters are hermetically sealed nor does it specify the conditions of storage. Specify whether or not the canisters are to be stored in hermetically sealed packaging. Identify the specific procedures that will be used to control canister storage, indicate the range of temperature and relative humidity allowed in the storage area(s), and describe where these canisters will be stored at St. Lucie. Specify the shelf life of the canisters and testing to verify shelf life.
RESPONSE
A. Humidit Barrier Packa in The 631-TEDA-H line canisters are sealed at time of manufacture using a paper backed, heat sealable, aluminum foil laminate. The seals when applied to the canisters, produce an essentially hermetic seal which inhibits water MSDAASS.RAI
V I
C f
'h
vapor transmission through the seals. Once the seals are removed by the user, they cannot be reinstalled.
t B. Shelf Life of Canisters The manufacturer of the TEDA carbon sorbent used in the 631-TEDA-H canister suggests a shelf life in excess of 3 years under normal room temperature storage conditions in sealed containers. The 631-TEDA-H canister with the foil-lined hermetic seals provides such a satisfactory container. A product shelf life under room temperature storage conditions is therefore taken to be 3 years.
Methyl iodide removal efficiency tests performed on 631-TEDA-H canisters stored in a 70-75'F, 30-70% R.H.
environment for 6 month periods displayed no performance degradation characteristics. Studies are underway to better define high temperature storage conditions on product shelf life.
C. Stora e of Canisters at St. Lucie Health Physics Procedure HP-62 "Inspection, Maintenance, and Quality Assurance of Respiratory Protection Equipment" will be used to control canister storage. Long term storage of large quantities of the canisters will be in one of the plant store rooms. The environmental conditions found in the store rooms to be used for canister storage is that normally found in an air conditioned office type of environment. The general temperature ranges are from approximately 70-80 F with a relative humidity of 30-804.
Short term storage of the canisters will also be in an air conditioned environment in the plant's respiratory protection equipment issue rooms. This short term storage is designed to maintain a stocking level adequate to meet the immediate needs of ongoing work in the plant.
Environmental conditions in the equipment issue rooms are generally the same as the plant store rooms. There may be instances when the temperature may reach 85'F for short periods of time, however, should not affect the performance of the cartridges.
QUESTION 471.11 The FPL submittal states that the canisters are not to be used in challenge concentrations of total organic iodide, including "nonradiometric" (nonradioactive?) iodide, greater than 1 ppm. Describe the methods and particular procedures that will be applied to prevent the use of the SCOTT
~
canisters in the presence of challenge concentrations of MSDAASS.RAI
'f
\
J.
total organic iodides and other halogenated compounds greater than 1.0 ppm, including nonradioactive compounds.
RESPONSE
There are no known sources of nonradioactive organic iodides or halogenated compounds to which the canisters would be exposed, either in storage or during use. The only other source of exposure of the canister to organic iodides would be the exposure to the radioactive iodides while the canister is in use. Calculations have been performed for selected radioiodines found in the reactor coolant system to determine the atmospheric concentration equivalent to 1.0 ppm of the radioiodines. The results of the calculations indicate that the atmospheric concentrations would be in excess of 1.0 E+09 times the maximum permissible concentrations listed in 10 CFR 20 Appendix B. These atmospheric concentrations are far in excess of the limitations of the respirators which provide a protection factor of 50 times the 10 CFR 20 Appendix B concentrations. The calculations are contained in Attachment 1~
QUESTION 471.12 The FPL submittal states that the SCOTT canisters are not to be used in environments greater than 120'F but does not provide a limit on the relative humidity. Specify a limit on the relative humidity for canister use and provide the basis for this limit. Specify how compliance with the limits for temperature and humidity will be demonstrated.
RESPONSE
A. Maximum Conditions of Use The performance of the 631-TEDA-H canister has been characterized at various conditions which include 37.8'C/48.9'C temperatures and 60/90% relative humidity.
The ability to extrapolate test results from one set of humidity conditions to another humidity level has been demonstrated (3). Using data at the 48.9'C temperature, a log-log plot of breakthrough time vs. % relative humidity has been prepared and is shown in Figure 3. Using a linear extrapolation, canister service life to a 14 methyl iodide penetration value is projected to be 12.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
Use of the 631-TEDA-H canister in a saturated air stream MSDAASS.RAI
at 48.9'C (120'F) should provide a nominal 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> duration to a 14 methyl iodide penetration.
MSDAASS . RAI
REFERENCES:
(1) Wood, G. 0.: Desorption of TEDA from Impregnated Respirator and Absorber Charcoals, Am. Ind. Hyg. Assoc.
J 45: 622-625 (1984)
(2) American Conference of Governmental Industrial Hygienists: Threshold Limit Values and Biological Exposure Indices for 1987 1988, ACGIH, Cincinnati, OH (1987)
(3) Wood, G.O., F. 0. Valdez, V. Gutschick, "Criteria and Test Methods for Certifying Air Purifying Respirator Cartridges and Canisters against Radioiodine", NRC FIN No. A 7041, Los Alamos National Laboratory, August, 1983.
(4) Wood g G ~ 0 ~ g "Respirator Canister Testing for Radioiodine", Am. Ind. Hyg. Assoc. J. 42: 570-578 (1981)
MSDAASS. RAI
FIGURE SCOTT Ghl -TEDA- H CAN l5TER OUTLET GASKET FOIL LINED SEAL PLASTIC COVER SEALANT ALUMINUM SHELL HOUSING 5% TEDA CARBON CANISTER SORBENT STOCK MASER RETENTION FILTERS 65I- TEDA PERFORATED PLATE HE PA FI LT ER FO I L L I NE D S E A L I NHALAT ION CHECK VALVE INLET
FIGURE 2 METHYL tODIDE TEST SYSTEM WATER HOMIDIFICATIOSI HEATER ONTIIOLL VESSEL VENT TEMP SENSOR AIR AIR FLOW ELECTROI4IC AND TIMER TEMPERATURE COI4TROLI ER
+5 t
RH TEMP HYGRO l~
I I RECORDER qc I I SENSOR COMPUTE l I I I I I
I I THERMAL RADIAL MANIFOLD I I I I
ENCLOSURE r
I r J I
I I
CI CE. CS
'I 5M PC/AT PRKSSU COMPUTER TRANS-RECORDER OUCER SEQUENCE EVENT INTEgggOR CONTROL MODULE SSV I I I
I I
EXHAUST I I
I p
I PURIFI ED FLOW GSV ECD VENT Np CARRIER GAS SEI4SOR GAS CHROMATOGRAPH WITH ELECTRON CAPTURE DETECTOR SSV = STREAM SELEC'TOR VALVE G SV = GAS SAMPLING VALVE COLUMN ECD= ELECTRON CAPTURE DETECTOR
FIGURE 3 RELATIVE HUMIDITY vs. BREAKTHROUGH TIME FOR THE SCOTT 631-TEDA-H CHIN CANISTER 100 90 80 70 60 50 40 RELATIVE HUMIDITY 30 10 10 80 30 40 50 60 70 80 90 100 BREAKTHROUGH TIME (hour s) 624. 16367NXww (-0. 737711)
TEST CONDITIONS:
CHALLENGE CONCENTRATION - 10 ppm METHYL IODIDE BREAKTHROUGH CONCENTRATION 0. 1 ppm PULSED FLOW ( 192 LPM FOR 0.82 sec., 0 LPM FOR 1.64 sec.)
TEMPERATURE 48 . 9 C, VARIABLE Fo RELATIVE HUMIDITY
ATTACHMENT 1 ATMOSPHERIC CONCENTRATIONS EQUIVALENT TO 1.0 ppm OF RADIOIODINES j
'w A
In order to'etermine the atmospheric concentration of the radioiodines at 1.0 ppm equivalent, a two step approach is necessary. The first step is to determine the specific activity of each radioiodine. The second step is to determine the mass of each radioiodine that is equal to 1.0 ppm and to determine the concentration in uCi/ml from the specific activity and the mass. The calculations are as follows:
MSDAASS . RAI
SPECIFIC ACTIVITY Specific Activity = SpA = X XN / 3.7 E10 = Ci/gm where X = 1n 2 = 0.693 Tl/2 Tl/2 N = 6.023 E+23 atoms/gram atomic mass Ci = 3.7 E10 dps Tl/2 I-131 = 6.96 E+05 sec Tl/2 I-132 8.14 E+03 sec Tl/2 I-133 7.31 E+04 sec Tl/2 I-134 3.12 E+03 sec Tl/2 I-135 2.40 E+04 sec I-131 SpA = 0.693 X 6.023 E+23 X 1 Ci 6.96 E05 131 , 3.7 Elo 1.24E05 Ci/gm I-132 SpA = 0.693 X 6'.023 E+23 X 1 Ci 8.14 E03 132 3.7 Elo 1.05 E07 Ci/gm I-133 SpA = 0.693 X 6.023 E+23 X 1Ci 7.31 E04 133 3.7 Elo 1.16 E06 Ci/gm I-134 SpA = 0.693 X 6.023 E+23 X 1Ci 3.12 E03 134 3.7 Elo 2.7 E07 Ci/gm I-135 SpA = 0.693 X 6.023 E+23 X 1Ci 2.40 E04 135 3.7 Elo
= 3.47 E06 Ci/gm MSDAASS. RAI
0 t 1'
CONCENTRATION EQUIVALENT TO 1.0 ppm IN AIR The next step after the determination of the specific activity of the radioiodines is to determine the mass equivalent of 1.0 ppm in 1 ml of air and using that mass equivalent and the specific activity to determine the concentration in air.
Molecular iodine exists as I2 in the elemental 1 gram mole of I2 contains 6.023 E+23 molecules state 1 mole of air occupies 22.4 liters at STP 1 mole of air contains 6.023 E+23 molecules of air 8.93 E-11 gm/ml = conversion factor SpA = specific activity 6.023 E23 molecule air X 1 molecule I2 X 1 22.4 liters air 1.0 E06 molecule air 1000 ml X ~2m I2g 8.93 E-11 gm/ml
- 6. 023 E23 molecule Concentration Calculation uCi/ml = 8.93 E-11 gm/ml X SpA Ci X Atomic Wt X 1.0E06 uCi gm Ci I-131 8.93 E-ll gm/ml X 1.24 E05 Ci/gm X 131 X 1.0 E06 uCi/ci
= 1.45 E+03 uCi/ml I-132 8.93 E-ll gm/ml X 1.05 E07 Ci/gm X 132 X 1.0 E06 uCi/ci
= 1.24 E+05 uCi/ml I-133 8.93 E-11 gm/ml X 1.16 E06 Ci/gm X 133 X 1.0 E06 uCi/ci
= 1.38 E+04 uCi/ml I-134 8.93 E-11 gm/ml X 2.70 E07 Ci/gm X 134 X 1.0 E06 uCi/ci
= 3.23 E+05 uCi/ml I-135 8.93 E-ll gm/ml X 3.47 E06 Ci/gm X 135 X 1.0 E06 uCi/ci
= 4.18 E+04 uCi/ml MSDAASS.RAI