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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
J REGULATORINFORMATION DISTRISUTION OATEN (RIDE)ACCESSION NBR 82P3309149 OOC PATE!82/03/23 (OTARI'ZED:
NO FACIL:50>>389
'St.Lucie Planti.Unitt 2E Florida'Power K Light Co~AUTH'AMP AUTHOR AFFII,IATZON UHRIGE R~E~'Fl orida Power 8'Light Co.RBCIP~NAME RECIPIENTAFFIL'IATION EISENHUTED.G.
Division of Licensing"
SUBJECT:
For,war ds response to request for addi info r e mini'urtge sos valves.DISTRISUTIOIJJCODEl A03AS iCOPIES iRECEIVEDIL'TR
.'I ENCL,~(SIZEI"3 L TI TLE: Containment
~Pur g i rig NOTES!DOCKET 05000389 RECIPIENT ID CODE/NAgE LIC BR 03 BC 01 INTERNALs IE 06 NRR.SHUMED 15 NRR/DL/ORAB 10 NRR/DSI/AEB N/ETSB.08 REG F 04~COPIES LTTR ENCL 7 7 1 1 1 1 1 1 1 1 1 1 REC IP I/NT ID CODE/NAME NRR REEVES iE 14 NRR/DE/EQB 09 NRR/DS I AORS NRR/DSI/CSB 12 NRR/DS I/RAB 11 RGN2..COPIES LATTR ENCL 1 1 1 1 1 0 1 1 EXTERhlALe ACRS 13 NRC,PDR 02 NT I'10 10 1 1 1 1 LPDR NSIC'03 05 1 1 1 rTOTAL NUMBER OF COPIES REQUIRED~LITTR"33'NCL'32
'qX('r Ir r'Irgt~W>>r;~I',y ll 3(.'<<f I~It<<<<,<<f tr h I ll II grt f<<I r<<~t<<II)lr 4 Il (.I gr r>>rr<<iq r'4>>~rh/1~3fi,(~'I'fair 1<<>>fr>>r'l I g 1$4 Qr I r r<pp149
>ppppelp sepsis-',~-'.'pog ADOC~pog f p',,'~")'i.it-p~'EOPLE...
SERVING PEOPLE L g I t g~1' PURGE SYSTEM 1.QUESTION: Provide installation details for the containment mini purge valve I-FCV-25-26.
RESPONSE: The installation details fox the mini purge valve are provided on Attachment 1 (Ebasco Dwg.No.2998-G-869, R.6).The general ar-rangement (P&ID)for these valves is provided in FSAR Figure 9.4-11.k 2.QUESTION: Provide EQ and SQRT Qualification data'for mini purge valves I-FCV-25-26 and I-V-25-25.
I RESPONSE')
I, The SQRT qualification information for the above valves was sub-mitted to the NRG on December 2, 1981 (FPGL Letter L-81-507)in response to Questions, 271'.1 thxu 271.5 of the Equipment Qualifi-cation Branch-Seismic Dynamic Loads Section.b)The Environmental Qualification for valve I-FCV-25-26 was sub-mitted November 1981 in response to the Generic Environmental Qualification Effort.3.QUESTION: Provide the closure times for all the purge valves.RESPONSE: Each purge valve is designed to close in less than 5 seconds.4.QUESTION: What is the maintenance program for the butterfly valve rubber seat?RESPONSE: A maintenance program will be developed for St.Lucie Unit f/2 simi-lar to St.Lucie Unit//1.The pxogram utilized for St.Lucie Unit/!1 involves testing to 10CFR50 Appendix J requirements.
Seat leak-age tests are conducted every 18 months at each refueling outage.Any repair or replacement is done as required subsequent to the test.Inservice inspection is performed on the valves every 18 months in accordance with the requirements of ASME Section XI.5.QUESTION: Are all solenoids used with the valve operators environmentally qualified?
RESPONSE: The mini purge valves utilized ASCO solenoid valves Part No.NP8321AIE which meet the requirements of IEEE-323 1974, and 344-1975 as sub-stantiated by testing valves of generically equal design in accordance with ASCO qualification specification AQS-21678 Rev.1, 2/15/78.
6.QUESTION: What is the'stablished ISX Pxogram for the valves?RESPONSE: The Insexvice Xnspection Pxogram will.follow the requirements of ASME XI, 1977 Edition thru the summer l978 agenda.This program will be submitted to the NRC for review and approval at a later date.7.QUESTION: Do the purge valves have handwheels for manual operation and how do you prevent overriding Automatic Isolation?
RESPONSE: The containment mini purge valves are air-operated valves with spring actuators provided for prompt closure.Those valves are designated containment isolation valves and receive the appro-priate CIAS for closure.Handwheels are provided for valve opening and are used only if the air supply is not available.
Xf the handwheels are utilized fox opening during norma1 plant opexation, the valve will require the restoration of this in-operable valve to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or bring the plant to Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.These provisions will prevent overriding of the Automatic Containment Xsolation.
8.QUESTION: How is closure of the check valve on the mini.purge makeup line assured?RESPONSE: During operation of the continuous Containment/Hydrogen Purge System makeup aix is provided to the containment via penetra-tion P-56.The motive force behind this makeup air is the'light negative pressure (approximately 3" W.G.)created inside containment by t'e operation of the purge system.Isolation of the makeup line is assured by a power operated butterfly valve and a swing type check valve.This check valve (I-V-25-25) is designed to open at 1.4" W.G.and is spring loaded to insure closure as containment pressure approaches atmospheric.
Thus, the valve disc would be at rest against the valve seat pxior to the generation of elevated pressures inside containment due to a postulated accident.Valve integrity is further assured by its design pressure of 150 psig and a differential pressure test at 75 psig.This valve is manufactured'by GPE Controls to ASME III, Class 2 standards and is seismically qualified.
(J~'
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<a1+P>>-+).-SCHKH5-O CONT+<4%V JNYCEOCgl PUSGI 6YSIrg ggpf<<TCAVOIIY%YICC AIICtCtWtIIT NO,O 1LOII FLORIDA POWER 6 LIGNT COIIPAN'Y ST.LUCIE PLANT UNIT 2 Illc OIIC:raal Ol 20IICOII CIA IAIV cl CONTINUOUS COHTAINIIENThIYOROGEN PURGE SYSTEN P 6 IO FIGURE 9A ll O.CESrS<;ca I t gS 1 c5*~lA.LOCATION OF LIHI T SWI TCHKS ADJUSTABLE SCREW STOPS SEAT SIDE BELL INLE1'CREEN BY PRATT (I TEH 11 ONLY)CUSTOMER: FLORIDA POM CUSTOMER P.O'RATT ORDER NO.~0 OC PROVEC.:ST.
LUCIE UNI PRATT OPER~ATE OUAN S)Z POS iO 2 87!I'-r TT 1 8<<1 12 GA GALVANIZED WIRE I<<~Q HFSH SCREEN.LIHI f SWI TCH 1 N~P~T Z , CONDUIT CONNECTIONSG
---H~-APPROX.LOCATION OF NUClEAR NAHE PLATE~s~B L HH-sea'L V I VV VV h Va V~F PI.ACE EOUALLV SPACED STRADDLE CENTERLINE G=BOLT, CIRCLE r=""'"'*'"""""" INTERIOR OF VAI.VE'XTERIOR OF VALVE AND OPERATOR: CARBO ZINC 11~ALi X O HENRY PRAT T t Qg,'W.EAII PSI AT f llllllE Ihl NO QOCIT ClAT 4hR 77SIC>>NCCLCAH HlLHC NANCSLAEC)SCC AACNC O01 AEONOH lOCATION)OEEHIHG 7IHE G SEC~CLOSING 7IIIE~SEC~ucSra,~2~E n l Ql I ice~
~uP-H4-y'~Qozs.: g Air<"-<>ke.r YwcuE.BY: DATE CHKD By: DATE Oua1i.ication Sur.-..harv of Eouiny-.en-7~4 Plant Hare: ST LUCIE UNIT NO.2]faa-" Qti)$0)T FLORIDA POWER 6 LIGHT CO Re" NSSS: CE 3a AfE EBASCO gf germen~ga V4 c 5/2 Eyn kBIZ V~K L t/6 c~" j~Tee: PMR x Scope: f)NSSS~So~Z.gode1 gunger: L02"IO-0 Ig-l guanttty:~~
~D~<3 Vendor: 4 Ef the ccnpcnent is e cabinet or pane1.naze and eedee1 No.oft Cevices inc1uded: a 6-Location: Suilding:/, EJevation:
5)e-C)O E'Systee tn'wMeA lanated:~d+lŽ~8d<1Ai4,+YD.~%46 4YS P c Ts the equipment required for~Hot Standby f g Co Shutdct l 3 Soth hei r 12/M
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and hw they (er tweeter in o>>ra El qua1ificat.on yrogr a=:~a%%~%a~~~NUDGE gf care han one repor co'ru1ete$ec IV thou VD for eecn r ocr.12!Lj 1
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ck f 3$':a.fc QaTgsh iqv'.valen.
Sta.ic Analysfs f 3 Dynamic Analysis: 5)Tive-his.ory f)R s-ense pe.r"=~P P~2.Sutural Frecaencies Sa Kecb Ofrec:ion (SiCe/Side.
Fron-lSa4.
~e c'1): P e'P P'P P P P P P P P PP P P P P%[)zQ f 1 Seem 5/S~P P P P 0 0 PIP P P P PPP P~3 Hodel Type: f, g M f)FinS:e Klewn p~ID (1csed For=S-: m t, I It I 4 5o He.bod of Cominform Ops->>'c Responses:
8.Oemfng: 0'=IS=Sesks A solu-.e Su~<g S~S Cpne"'Pa as a P~OPPP OPPOSE PP POP PAPPP gs,=eB=.I7 ffar:lte fh~<ay IIM"': t 4 I'oncerning t,oad or Resoonsc Seismic To.al AP B ePlf<c c'fen j (4Pfon'0 nao on~S ss Soress H<<f E.$144FT.,~<~~ii~l 8,9 S'sp>'e II I I I.',Location P~Lt8)Disc.I-tt~8.Z~.S~ss P PP POP lP 4sop~~Vexing:r Ql~ab1e Def ie..ion co Assure Func:ipnal C-c.x bf lily PP 0 0 P 0 PP P P P P PP PP 0 0 P>>~P>>'P P 9.Rex.Crf fcnl"DeflecPion PIPPPPPPP'PPP%%
l O.og o.co I rd.+El5f4if4 LPADilJQ: i.i 8+(j.f Eti I)y l l 8=P.75 P (++~~+U~TEP kl57V~I.~~~l-~++~l Hz Ph'l,&.Y pt sc.
1~50'1~'QO~~VLSTVh VOlTS L~Le~5 TOVVh55 hfe LK}t VLLtt l05hKOe000 Sf lhl}5lCV T51f SO.S FLOOR SPECTRA HURIZQNTAL e.-H..4 H-S.OBE E.4OKSl~"i REACTOR Bl.OG HASS PT 19 KL 68.0 I SLTaEl Ce4g(lubfeuT'.
~~e~~1'0~I~~g~1~20 1~10 1.00 O.SO O.eo 0.70 0 60 0.50 Oo}lO 0.30 0.20 0010'~-~~~Z C)~~~~~(J'.e e}-~CC':~.s'.~~,~~~)~~e~,~-.}}~1~00~e'e~)~'~,)~~~~~~I$~e ee~e c~2e00 PICURE 2~~l 7 i'l l"'7 7 7'7 7~5.00 10.00 20.00 FREQUENCIES f CPS 3 0=2'I.SO.03\'1 I I I l l t l~e~~~e
).00 FLQOR SPECTRR VERTICAI, QBE E=QO KSl.REACTOR 8LOS BASS PT 9 KL 68.0~'.-'..Cl'GEL C:OLlTklUMSLJT KfZ 7lNICL 1~ST.NC:t)la>>'19%II 00Oo000 Q CITCNC If IeOo~W r 0.90 0.80~~~~I I I i a.70 L~0.60 I CC 4J Q, o Q(p 0.50 q.!~"s'.~~I~~~,I~I~o 0.30 0.20 IeIGGRE 3 0>>10~~],00-=----=---Roaa-s.ao)0-00'ao.oo FREQUCIMClCS (CPS).so.oa gc.0,'e~~<<~See<<OSO<<et Oae<<e Sea+>>I~'~OOSO ie1~I a<<aae<<O,<<SO<<a4ae
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'ST@-]4'70-1460 1~50 lo QO 1 o 30 1~20 1~'10 1.00 0.90~<'u~%.080~04 10 0.60 CC LU CI I-r,~>,~~~~'E,~I QT~'I r I I'q.~~~4 I~~6~~~~~0~~~0 50.000 04 30 0.20 Oo l0 I I~l Rz~~~~~~~~6~~~0 I.'I I I I'I'I~I~I FIGURE 5 i.00., S 00 5 00 10 00 ZO-00 FREQUENCIES t: CPS)50 00~~r 100 rrl~044~r~r 04>>I~~~tr N~~~~
~~2+00)ISO).80 l~70)o60)ISO I, 0~q FLOOR SPECTRA VERTICAL OBE E=OO KSI REACTOR BLDG HASS PT 9 K 68 0-.~%ca L'~~QM&v7 srq:.: PLClt5b~iA tt~Nitty 1'90.000 tl Kit~to'tt Def RL t~I I~.~~g tatt0~)o30)+20', a~IO""" 3~00 Vo90 O.eo 0.70 0.60 0.50 0.90 0.30 0.20~0.10~~~~~K Q CC J~t t.~~~-~I~~~'I I~~W>>I~~I I., I I I Fl.OOR SPf CYRA HODIFIKD 0 0'lAT10H Il4 fRERtt'LNctES.
4T'fP.FIGURE 6 OR3%~~l F00 2.00 S.00)0-00 FREQUKNCIKS t: CPS)20.09 I I SO 00
~~~~.'.'.'FL SPECTRA N-5 68E.Ee tl'40<<<.3>>60'>>QO 3>>20 3>>00*~:..-:::.2.80 2>>60 2>>QO I~~p~~.'.*.2>>20-:"..2>>00 2~80 ie60~~':I.lyQO~~l>>20 1>>00'>>800': 'I: ','>>A>>BLDO Kt.%2>>s~~~>>I~'~~e~)~Igr llv~~Ud (~O'~~...(K I~i'I~~, (~.~.~~~'vv'~.~mmieac-
~~I g, g g7iLt gavioto4>~~p~0.60 0>>QO FIGURE 11~O>>20'~~l>>00 2>>00 5 00 tO>>00 FREQUENCIES (CP53 20.00 avv AA vv~Ve
~g r~~~~~I~'hr)'~~4glIC' I~s~~~~'I.t~t 3.60 3.'40 3o20 3.00 2o80 Ro60 Ro40"2o20 Ro00 ,~~1 o80 IQ 1 o60 i 1oQO 1~20 1~00 0.80 0.60-;:.FLOOn s~ECTRA~-v OBE E=QO KSI go)g~~~~I~AoAoBLOS Et.QRo'S I FI'.I.~~~~~~I~~~-I, CC'I o~'(g'=" rI r"~r~)0~r I I~~~)~r I)~~g I~~OI fiTCADS TCCCR ACI terre COQQY st.teat r~Rm.st,ooo rr aetatcs.cat m.Q Do%0~I~~PIGURE 1)Qo20 0~2 X 1 o00 2o00 5 00 10.00 FRFAUFNr:~F~
rr.~~~20.00 l~T<'l.I.'0
~C 2000 FL SPECTRA VERT GBE E-"40 NS I 4UX acOG wp V Kt.Q2.S WiN:Dl WS of)t$I0<<ge'W tfr tot!C etae!i019CSMrO.'0 l1 ttetN!0)I'f'lf lOC 0 1~90 l~80 l.70~~~~1~SO-1000 1030 l 02/l010.l~00 l 0090 0080 0..70 0.60 0.SO~1 o'r o, (g~~~~'I h~~~)~r'0 I I irw Q't~=o C~~~~~~~~~~~I I~~0040.0.30 0020 0.10~~I~~FIGURE 33 Qsg%~~pr 1000 2000 6.00 10.00 FRKQUENCIKS (CPS 3 20 00 t SO.03 I~~~~SIOO QI 80'Q.60 Q~QO~~~~~~FL SPECTRA N-S DBK K-Ao K~r AIAIBLOG KL 02IS QAIISl t IT%AW liras CA7LZf I)StS 1I.,C:O a u':C:S=.:i-Wt n.t%Gal'~lan!
l Q~00 3IBO 3460 3IQO o.ao g 3,00 3 o.so J 2+60 2IQO 2I 20 2IOO i,aa l I60 1I40 l I'20 r,,~~J~~~~CC UJ~er I I~i~*I I~~~~0*fI~M 4Ir Ct~~~, VIIURE N)I 00~OI80 Oa60 OI40 OI20 I~I~~t~~l 43 R lIOO 2.00-S.QO 10.00 FAl=Allrr.r vrC rr oc.~20.00~~~a ss~sr FLGQR SPECTRA E-H OBE E~QO NSI'few 0 oo A~.00 o80 o~AoAoGLOO BL QRo5 1Wll&f~(~tag V~ggygpt Si.~:.'<C o:ar'%~OR,O.O%l Dtfd" CJ lit FJ B.60~QO oRO F 00 Io 80'.o60'o40!o20'.~00 o60~QO~'~P~~~~~..r~'J~,'".i)'::.~,a'~~C)l CC CC UJ UJ~~CJ a~~~~.aO-lo00)o80)o60 I o'I~PICURE I)~QO)o20'Q3%io00 2.00 5ooo e'OC'hilt" asr v r a r o.ra~i 10o00 Ro oo 50.00 odtwop4Asd4l~
30 20~10.00~~FL SPKCTRR V'ERT OBE E=CO KSI (COlg RUX BAZOO HP 7 Kt.<r2 8 li4tlPL tOCR le Uc!?CMICE r..u..:c r.si;RlT9~e000't?&Kl tCZr"%l?10.t.90.80 s70 o50 F 40, o30 o20~10 F00 i.90 is 80 i.70 i.60 i.50 i~40.l.30 la 20)~LO,~~~~~~~~~~n~~1~CC CC~r~,.43 O a.~~~.~~~~0~r~r 1~~Cq~~I~'~~~~!i[~I I~~I~.I~~)~'rxcuaz t6'Or3 K>.00 2+00 FREQUENC?ES (CPS)20.00 50.00 Ouaii!ication Suc;..arv o!touicuant Plant.'far"e: ST LUCIE UNIT NO.2 Utility: FLORIDA POWER&LICHT CO.~Toe: PMR X 1'I Ze NSSS.CE Concone.".
Ha."s kPW 3 A/E: aaaeco Bn'R Pu(m S~C"P-'P'-Z>Zlg c 4 Scope: 5 3 htSSS~SOP//'Model Nunber: 8'gX Vendor: rz~HH Quantity: 4 If the ccnpcnent is a cabinet or panel, nar:.e and rachel No-m~e devices included: 6.Location: Buii ding: VcFZV4'>Zdc"c'~~>>a Eievation:
Zev'd'a Co Syst i in which loc'ted':~~~Is the equip;.ent required for~Hot Standby 5 3 Co<~Shutdoi C 3 Both Cj lfw=r J
~~III.Is Eouip.-..ant Ptii iiahle for Insoeo:ion in the lit: p g Yas f g lio IV.Eouiorent Qua15ficat'-ra
..ethod: E 1 Test)~3 AnaIysis'uaIiiioation Ileport: 57~Zy n~+itHo., Titie and Date)2>-iOO9'8-/O Dl//',Cospany that Prepared P.por://w/ry'~a'7 P I I II ,'" Vibration Input: I t.oads considered:
a M Seis-.c only E 1 Coriination of Tes-and Ana1ysis b.{.g Hydrodynamic on1y c.j g Corbination of fa)and (b)4 2.'tethod of Comining RRS: t: g Absolute Sum t: g SRSS i.3-Required Response Spec ra tattach the graphs): 4.Oarping Corresponding to RRS: OBE , 55E~&w~&M'w u~E'3~o-ner, spec>~g c'cpsf p f4.vAs Other gp~/d/'a\(Required Acce1era ion in Ka&Direction:
f g ZPA i S/S I'F/8~S/S~~" f/8~Mere fatigue effects or other vibration 1oads consideredT OBE SS" 6'C 3 Yes'~Ho: If yes, describe broads considered and hew they vere tree;ed in overa?1 qua1ification prograr-':
ONOTc,.WW&WW&WW&W\~W~&W~W a I If were than one report corp1ete items IY thru VII for each repor 12/BO
~l N'1.I 3 Single Frequency 2.t.3 Single Axis f.j multi-rro""fancy:
t.j Hulti-Axis YI.If Qua1ification by Test, then Co.-..piete~:
t: g'andom C 1 sine~" L1 Nf N l(atural Freouencies in Each Oirec-ion (Si¹/Side, Front/Sack.
Ver-ical):
fi S/S~Fz-fl v-NI IN 8.Inout a-level Tes: OBE S/SSK SS I F/B~CN:est Res its inclu 10.Functional ooerabil t-v rii ed: E g Yes 5 3 Ho 5 3 Not Applic ble 11 di ae f t d Q;,~!'ote: If qualification by a co~ination of test and analysis also co~Nlete"Item YII 12/80 N
~~H VII~If 0"aiifican by maiysis, then cn;..nIete:
~'%W W W I.method o.Ana1ysis:{.3 Static Ana1ysis~Kquiva1ent Static Ana1ysis E 3 Dyhamic Ana1ysis: f j Tire-History f g Response Spectrum 2 Natura1 rrecuencies in Each Direction (Side/Side, Front/Back, Ver-.ical):
280 H~g s 0&'Aae O&%%&WW 3.Hode1 Type: g g 30 E3~D~ID II H f g F'inite K1emnt f 3 Beam~Closed rorm Solu.5-."method of Comining Dynamia'c Responses:
E 3 Abso1ute Sum E 3'.PSS M Other:SESS 2~o~lz,+uE~rtc~a gspecivy)6-Garying: OBE'SE Basis for he dampino used: W%%W~WW&w&w&w~B.Hax.Critica1 Def1ec ion l.ocat$on Maxirum A11cwaole Der lec.ion to Assure Font-iona1 Opera-bi1ity' A/E: EBASCO SERV1CES INC..Uf ILI TY: FLORIDA POKER b LIGHT Q~~s z FAC}LITY: COMPO}4ENT rd Tip ST.LUCIE HO.EVALUAT}ON SHEET NSSS: COMBUSTION ENG.-PVQ CAPACITY: 890 MV(E).V~0 CESe-0447 EOUI PM}N'f I ENVIRONMENT DESCR IP I}ON I PARAMETER SPECIF}ED t DOCUMENTATION I DUAL IF}DEM.OUAL1F.I SPKClF lEO DEM.OVAL IF~f ME}HOG I 2--<<I--o-o3o--4---I-5 I OUTS I I TK}4S I H/M!oo6 I eo7o f TAG HO: FCV-25 26 (01AP I OPKRABIL-I HRAGM.F.C.
)--I: ITY I.==--=-=INORM/TEST I VALVES IOBA I EOUIPMENT:
TYPE I I I I I I---=I COMB.I TEST 6 EXTRA POL'N!HONE I ACCKL T}MK: I I ACCKL TEMP: el----CDMPONENT:
B'TFLY f TE}4PERAT t 9}.SF NORM URE t I.----=I!}BF1200HR I TA821F f I SL2 FSAR I I 1'ABLE3}f-I I COMB.I TKST 6!EXTRA I M t HONE f RKPLACEMENT:
MANUFACTURER:HENRY PRATT t I I I o\I T395--}I POL'N!ee a ea a o oe eo e e e e e eeeea!MA(NTA!N~I PRESSURE I ATMOS NORM I I OPS1G I PAB21 I!SL2oFSAR I COMB.I TF.ST 6!NONE I I 14A JOR SUPPL1ER MODEL AND:.SER}AL V*FUNCT.DES:
CONT 1SOL:.'SERV}CE CLOSE(C1AS)
TEST 6.I EXTRA I I SPRAY f~I I I-!I I f I-.-'I (ACC.OBA)I I TABLE3ft 1 I I EXTRA I I I}P394---I I POL'N I e I RELATlVE}58.0%HORN I'I HA827F='I I COMB.I HUMIOfTY f--...I I SL2oFSAR I'I TEST 6!I~I 60.0)(}200H
!'TABLE3}tet I--..}EXTRA I==-.-=I;,., I I H395 I I POL'N I ICHK}41CAL I I I---I.....I COMB.I I/I I I I/I I SUBCOMPONENTS:
I e'I NO UNIOUE TAGGED NONE I SUBCOMPONENTS ARK., I ENVELOPED BY THIS I KOU}PMENT I o eeet HONK I ACCUR.SPEC: HDT APPL1CABLK oee ee\e p t~COOQDlNATKS X-609.0 Y-}5!6.0 Z-45.0 T35.7 P35~7 H35.7 35.7 R35.7 35.7 35.7~~e~~~~ee~~~e~~~e~e~~~~~eeeet}RAD}AT}ON PHYS DVG REF: 2998G.395 PHYS DWG LOC: MOUN11NG EO.DOC.LOC:
'I AGING ISUBMERGENCE
!SAR ENV CAT: K 10588 CA 1 E G.: A!APPENDIX E I It 2 HRI 480 3.0E4 ACCUR.DKMot NOT I A 30 OI5.0ES 5.6ES APPLICABLE I D t YR!1.3E5 5.8ES I.40YR/R'@IS.OE3 5.0KS SPEC1F 1CAT1ONS: I t AGE-P.O P:422537 I1NST L1FE I l(PEQ 323-I PLA}41;LOC.: AB21 I!974 OEF.)I I I SUBMERGEOI I YES/NO!I I}I INSTALLED (Y/N): LTR I INSTAL.RKF:BY-FLO PARA SUPPL.OUALIF EXEMPIN: NOT APPLIC I METER REVIEW~~e~~~~~~~~~~~~~~~~~~~~~~~e~~~IOPERA81L I TY~DUAL IF:~ITEMPK'!ATURE
~STATUS~tPRESSURE~fREL.HUl4}O}TY~ICHK}4.SPRAY I I RAB27U I t I SL2-F SAR I I I TABLE31lef I I R395 I I}OCFRSO I t I PARA 50.5}I I I I I I I I I I I I I I I o o POL'N COMB.TEST 6 KXTRA-POL'N t I COMB.I I TEST 6!EXTRAo POL'N!oo eeet I NONE I ol HONK I I SAFETY FUNCTION: COMB.HOHE I TES!6}I I EXTRA-I t I AUT}(.
REFERENCE:
'I POL'N I I I 3.9}0 oo ee o~ee o I OPERATING
REFERENCE:
}PREP/DATE
- C/5 SIGNOFFS!CHECK/DATE:OQ EOUIV.IN KO.F ILE I OUALIF1CATIDN REFERENC'E f RKV>-0!PREP/DATE
- CKS SIGNOFFS tCHECK/DATE:OQ Enu}V.IN KO;F ILE SYSTEM I TAG FCV~25 26}DIAP HQAGM.F.C.
}I OIHER EOU}PMENT TH15 CES APPLIES 1'0: I I FCVo25e!(PISTON,FC)
I I I REFEREHCES:
~~S%e DISCUSSION ON MAINTENANCE PROCEDURES RUBBER SEAT: The rubber seat is made of RESILOSEAL N*which is an ethylene propylene compounded specifically for nuclear service under elevated background radiation and temperature levels.Although"indications show that RESILOSEAL N has an excellent service life, not enough data has been collected to accurately predict its expected life under varying conditions of use and environment.
It is.known that higher radiation levels and temperature shorten the life expectancy of the seat.Failure mode is characterized by a shrinking along with a hardening of the rubber and eventual cracking.For this reason we recommend the following semi-annual checks: l.A visual inspection of the seat be made to check for dimensional shrinking and cracking.2.A Durometer reading be taken.(If a reading of over 75 is indicated, we recommend that the seat be replaced.):
These are strictly precautionary measures taken due to the I'ccelerated aging'.caused by radiation and heat and the fact..that relative life expectancy can change from installation to , installation.
- Resiloseal is a trademark of Henry Pratt Co., Inc.0-5.
C f'E'4 For information about Pratt Rubber Seat Butterfly Valv not conta ative, or ined in this manual, contact our local Sales Represe write direct to: HENRY PRATT COMPANY 401 South Highland Avenue Aurora, Illinois 60507 1 Jl~I II tlf I I~1 II I'I II,ii, I f~gati~y I ff , i'~I'ff II j 0-6 J'~+~
REPLACING RUBBER SEAT IN NUCLEAR BUTTERFLY VALVE A.DISASSEMBLY 1.Turn disc in open position.M 2.Remove adjusting screws in segments.II 3.~Number all reta'ining segments and mark proper location"on valve body.4.Pry segments out of body.5.Remove old rubber seat.6.Clean seat groove with clean dry rag.B.INSTALLATION l.Apply light coat of silicone grease to seat groove.*2.Insert new liner seat into place by pushing rubber snug.3.Insert segments back into body and install screws.4.Close valve disc.5.Tighten all segment adjusting screws to assure reason-able interference between seat and disc.6.Bubble or leak test valve and tighten adjusting screws as needed to stop all apparent leaks.M I*We recommend Dow Corning valve seal or Dow..Corning III Compound.Please note.that the use of Petroleum grease negates all guarantee 0-7 g~-s~~math Sxvkek Co.'IManufacturere ot DEPENDABLE CONTROL Since 1SBS.?ARK,NBV JERSEY 07N i NQP i2OO cee goo)N.Y;taQl 34.3reS~~I(~(((~((t CERTlFICATE OF GOMPLIANCE
'e I'CF Xndusteiesg X c...".Customer P.O.No.~"~I~~~~'ASCO Shop Order No.063 H~~(-: ASCOPaIINO.
~~~+Ua((IIIP~\,~P wo,~pot~l25"VDC Png Job No 672L5 CHECKE GK BY (~Pe o certify that the subject valvegs)meet the performance requirements of lEEE-323-1974,$82-1972 and lEEE-344-1975, as substantiated by testing valves of generically equal design dance with ASCO Qualification Specificatio AQS-21678, Revision"B", 2I15I78.els-I g Simolatio'n (Thermal Aging-268 F for 12'days to simulate 4.4 years at 140 F ambient.The test temper-ature and period are based on the 10oC role (Arrhenius Equation).
'adiation Ayng-50 megarads of gamma radiation at a rate not cxcccding 1 me arad per hour.I Wear Aging-40,000 operations at maximum operating prcssure differential and nominal voltage Vibration Endurance-1 mQlion cycles,'distributed equally among the three orthogonal axes, between 50 and 100 Hz, at an input acceleration level of 0.75g.The valves werc cyckd once every 15 minutes during the test.'Xley werc attached to the table by rigid test fixtures using.the standard valve mounting provisions, with the solcnoids vertical and u>tright..Flexible hoses~werc used at all ports;thercforc, the test setup did not affect the riydity or mass of thc valves i.(buno tested.47~~~(I a~I~~~~~~~~e!c Event Simulation
-The valves were attached,to the taHe by algid test.fixtures using the~, Md valve mounting provisions, with the solenoids vertical an8 upright.Flexible hoses werc at a11 ports;thercforc, the test sct-up did not affect the rigidity or mass of the valves being d.The seismic shaker used had the following minimum performance qharacteristicst 1-2 Hz~~~~I~~~~~~~~~~~~~~6" double ampltu8c~\t e~~O~0+0 2-33~.~~...~~~..~..35 snrsec.velocity t'ai acceleration required, then constant acceleration.
(I C)perating Basis Earthquake (OBE)-'Ac valves were exposed to two sinusoida>
sweeps aug".(within machine limits)in each orthogonal axis from 1-33-1 Hz, at 1 octave per ainotc,zone
@veep with the valves cncrgbed and one with the valves dc-cneryzed.
Thc two sine mvet.'ps arc designed to provide the mechanical aging of 5 OBE's.Paaclof2 l'f I I~~l~I SECTION 2 DESCRIPTION OP TEST SAMPLES The folloving descr p io i tion of the valve samples vas provided by Automatic Switch Co.Isomedix numbers vere marked on valve housing with a marker pen.t~g~~TABLE 1 VALVE DESCRIPTION LIST Isomedix No.8 ASCO Cat.No.HVA-206-381.-6P NP8344A71E HVA-206-380-3RP NP8320A184E NP831665E NP8321A5E DC Class H leaded coil, Nema 4, 7 and 9 solenoid enclosure, normally closed, 3-way construction vith metal seating.DC, Class H leaded coil, Nema 4, 7 and 9 solenoid enclosure, 4-way construction with resilient seating.AC<Class H screw terminal coil, Nema 6 solenoid enclosure, normally closed, 3-way construction vith resilient seating.AC,'lass H leaded coil, Nema 6 solenoid enclosure<
normally closed, 3-way construction with resilient----seating.1 DC, Class H leaded coil, Nema 4, 7 and 9 solenoid enclosure, normally closed, 3-vay construction vith resilient seating.DC, Class H leaded coil, Nema 4, 7 and 9 solenoid enclosure, normally closed, 3-vay construction vith resilient seating.NP8323A39E
={Solenoid A)AC, Class Class H screw terminal normally closed, 3-way seating.H leaded coil,{Solenoid B)DC, coil, Nema 6 solenoid enclosures, construction with resilient 0 an C4 O 0 9 I rt 0 9 O I V 5 Qs g 4 n Ql Ul Qt r 9 ol 0 8'0 rt 0 I Ql 0 I 8 lA'M Ul Ql~pi Q 0 I Vl 8 cf'rt P 8 Q V 5 rt 8 0 0 N 4b Ql n H 0 CQ CATALOQ NQ NP832IA1E g l25 VDC B.Safe Shutdown Earthquake (SSE)-The valves were exposed to single frequency sinusoidal tests at 1(3 octave frequency interv'al dwell points where the g-level was recorded at which'he cylinder port pressure (zero when de-energized and full inlet pressure when energized for a normaHy closed valve, opposite for a normaHy open valve)differed from the nominal by 0, 5 and 10%%uo of inlet pressure]up to'10g maximum).The valves are considered to function properly~: 'p to a 10jo change in cylinder poit pressure.(This level was selected as beino insufficient to: '.cause spurious shiifting of thecustomer's main valve or other equipment).
The duration of each'dwell was the time required to operate the valves through one complete openfclose cycle or 15..'seconds, whichever was longer Motion was applie8 at the same frequency and acceleration
': "'limits in each of the three orthogonal axes separately.
~~~~~~'".'Maximum Acceleration:
.-.i~~I~+P ro~~~g~..;3.0g a11 conditions V~~~~~~4,~~~~~~~o~~~~Loss of Coolant Accident (LOCA)-The valves were exposed to an accident dose of 150 megarads of gamma radiation at a rate not exceeding 1 megarad per hour.The valves were installed in a pres-sure vessel and subjected to a 30-day exposure of steam and chemical spray following the suges-tions of lEEE-382-1972 (chemical spray per Table 1 (b)and test chamber temperature proQle per Figure 1 and Table 2).The valves had been pressurized to maximum operating pressure and contin-ously energized for 4 hours prior to the first transient (to produce coQ saturation).
The;i were de-energized when the temperature of the est transient reached 280oF to show satisfactory shifting for demonstration of safety function.The valves were l'ept pressurized and were cycled during the 30 day exposure, as suggested in lEEE-382-1972, to demonstrate their aMity to operate on demand during the XOCA.~~~~The test report on AQS-21678 is on Gle at Automatic Switch Company'n Florham Park, New Jersey, and is available for customer perusaL~.r OO'~~h I ,~II~'ated~~Authorized Signature~t e/c~~rich K..Plaut Project Engineer~0 Page 2 of 2~~~0 Ch s'nnesvj M'pAghr%,
I Apl I 1 C I}}
