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Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-01-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 ML23275A1142023-10-0202 October 2023 Improved Technical Specifications Conversion, Chapter 2.0, Safety Limits, Revision 1 - Volume 4 L-2023-126, Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal2023-10-0202 October 2023 Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal ML23275A1262023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 5.0, Administrative Controls, Revision 2 - Volume 16 ML23275A1252023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 4.0, Design Features, Revision 2 - Volume 15 ML23275A1242023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.9, Refueling Operations, Revision 2 - Volume 14 ML23275A1232023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.8, Electrical Systems, Revision 2 - Volume 13 ML23275A1222023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.7, Plant Systems, Revision 2 - Volume 12 ML23275A1212023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.6, Containment Systems, Revision 2 - Volume 11 ML23275A1192023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 2 - Volume 9 ML23275A1202023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.5, Emergency Core Cooling Systems, Revision 2 - Volume 10 ML23275A1182023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 2 - Volume 8 ML23275A1162023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 - Volume 6 ML23275A1172023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.2, Power Distribution Limits, Revision 2 - Volume 7 ML23275A1152023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.0, LCO and SR Applicability, Revision 2 - Volume 5 ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 ML23275A1112023-10-0202 October 2023 Improved Technical Specifications (ITS) Revision 2 Submittal Volumes 1 Through 16 ML23275A1122023-10-0202 October 2023 Improved Technical Specifications Conversion License Amendment Request Self-Identified Administrative Changes - Volume 2 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-154, Subsequent License Renewal Application Revision 1, Supplement 42022-09-22022 September 2022 Subsequent License Renewal Application Revision 1, Supplement 4 L-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022 Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal L-2022-043, Subsequent License Renewal Application Revision 1 - Supplement 12022-04-0707 April 2022 Subsequent License Renewal Application Revision 1 - Supplement 1 ML22010A0962022-01-0505 January 2022 Trp 010 St Lucie SLRA - Boricacidcorrbreakoutq - Makar ML21285A1072021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1 ML21285A1082021-10-12012 October 2021 Enclosure 1: St. Lucie Nuclear Plant, Units 1 and 2, Subsequent Licensee Renewal Application, Revision 1 ML21285A1112021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report2021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 ML21215A3152021-08-0303 August 2021 Application for Subsequent Renewed Facility Operating Licenses ML21215A3162021-08-0303 August 2021 Enclosure 1: Subsequent License Renewal Application Enclosures Summary ML21215A3192021-08-0303 August 2021 Appendix E - Applicant'S Environmental Report for St. Lucie L-2021-192, Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-05-26026 May 2021 Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 L-2020-164, License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2020-12-21021 December 2020 License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2020-020, License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years2020-02-18018 February 2020 License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2019-10-0909 October 2019 License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019 Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG L-2018-161, License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2018-12-20020 December 2018 License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2018-182, License Amendment Request Iodine Removal System Elimination2018-11-0909 November 2018 License Amendment Request Iodine Removal System Elimination L-2018-201, Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-0909 November 2018 Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2018-147, Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications2018-08-0202 August 2018 Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications L-2018-121, License Amendment Request to Reduce the Number of Control Element Assemblies2018-06-29029 June 2018 License Amendment Request to Reduce the Number of Control Element Assemblies L-2018-120, License Amendment Request to Remove the Site Area Map from the Technical Specifications2018-06-25025 June 2018 License Amendment Request to Remove the Site Area Map from the Technical Specifications L-2018-111, Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-06-0707 June 2018 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018 Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications L-2018-031, License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme2018-01-31031 January 2018 License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2017-12-19019 December 2017 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors L-2017-139, License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply2017-09-14014 September 2017 License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply 2023-06-14
[Table view] |
Text
r NRC FonM 195 U.S. NUCLEAR REGULATORY COMh ON DOCKET NUMBER Iz-vB) 50-335 r'JRC Fll E NUMBER DISTRIBUTION FoR -ppRT 50 DOCI(ET MATERIAL To: FROM: DATE OF DOCUMENT Florida Power & Light Company 8/3/76.
Mr. Dennis L. Ziemann .Miami, Florida DATE RECEIVED Mr. Robert E. Uhri 8/4/7.6 ETTE R NOTORIZED PROP INPUT FORM" NUMBER OF COPIES RECEIVFD 0 ORIGINAL PflPNCLASSIF I ED One signed copy
.QCDeX DESCRIPTION EN CI.OSU RE I
Ltr'. notorized 8/3/76 ~ ~ .requesting .that section J, of Enclosure 1'o the Unit No'.
'1 Operating'L'icense'e deleted a's a condition of k
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a, j PLANT NAME: (4 P)
ACKNOWLE9GED
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St, Lucie gl DO NOT REMOVE SAFETY FOR ACTION/INFORMATION 8 4 76 RJL ASSXGNED AD: ASSX NED BRANCH CHIEF: Ziemann AD'RO
~OJECT MANAGER: IIANA LIC, ASSTo: Diggs L INTERNAL DISTRIBUTION 6 FI SYSTEMS SAFETY SITE SA NRC PDR HEINEMAN ENVI 0 N I&E SCHROEDER 8ENAROYA EN OELD GOSSICK & STAFF ENGXNEERING IPPOLITO MIPC MACCARRY K RKIJOOD CASE KNIGHT SDMEIL OPERATING REACTORS ES PAMLXCKI PROJECT MANAGEMENT REACTOR SAFE'IIY OPERATIN C BOYD ROSS EISENII P COLLINS NOVAK SHAD HOUSTON ROSZTOCZY PETERSON'ELTZ CHECK BALER GRIiifES HELTEMES AT&I SKOVHOLT SALTZMAN RUTBERG EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: Ft. Pierce Fl NAT LAB: BROOKHAVEN I TIC: REG VIE ULRIKSON ORNL N
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August 3, 1976 E.-76-?8l OEX'ice of Nuclear Reactor Regulation Attn: Dennis X.. Sie.'!~ann, Chief Operating Reactors .srrnch No. 2 Division of Operating Reactors REcgyg U. S. Nuclear. Regvlatory Commission bash3.ngton, D. C. 20555 Deax'r. 7.iemann:
Rc: S t. Lucio Un it No.
Opec;ati ng License DPR-67 l ~Nil-~'-"
Condition of T,iconse Iegule ory Docket File Florida Po! rer s X.i ght Company (="PL} hereby re.guest.s that Section J of Fncloaure l to the St. Eucic Unit. No.
Operating L'icense bc relet.cc's a Condition of License.
l As cRiscussec: herein, PPX believes that this Condition been sat,isfiec'. and i, no longe" recuixed.
'L'he subject Concition of License reads as fo3.louis:
Control Element. Drive E'.c:chanism (CEDN) 44 shall be rcaai ed oz replaced at the next ext:enrage@ reac" or shvtaose expected to last qg.S at least tL~'o vmer.s."
This Condition was added by AlMACTtlc.'nt 4 to Di'R-67 be-cause FPL was unahlo to comple e the cold rod drop time testing requi rm'. by a preceding Condition of Ei cense. 'i'he testing as recoiree1 to preclude the reactor being made criti cal under conti tion (i. e., coLd) which had not. fix'sK been te" ted for roc drop t imcs, since it was conceivable
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that t.he plant would bc in a cold critical conait.ion at. some time. during i ts expected se'vice lifetime. Thi s testing was not co!npletod due to oifficvlty experienced ia ~~.ithdx'awing the rod controlled. by CEDE 44 Ln cold condit5.on. The test procedure recuircd. that the two tastes rods be tested several times at various Xlov conditions. It the second fastest rod. was that controlled by CE'Dt< 44. Al-happened that.
thour>f} the rod cauld not be withdra! n successively in a cold condition in order t-.n coalpl.ate the leqoircd number of tests, xt operated sati sf Bciorily at hot opckatincf conditio7ls e Accordingly, the Zi cense eras conditioned to add. Section J to Enc?os@ra l of DPR-67 anc~ t'ai delete t: he authorization for low temperature critical.i ty containcB in Technical Speci f ica-tion 3. 10 3.
t'o STAT= GP ." LQ>7. N' ss
( COU-'.<TY Q" QZ DK Rober ~ '. Uhrig, being" irs+ Buly s'~~ore, serosa@ aa6 says-That he is a Vice Presiciont of'lor'Qa. Po~~er & Light Company~
the L'ensee he sin; That he has execu e8 the -foreco'nc~ aocamen"; that tne st<"-e-Rc3T s IQ" QG B. thi s saS.Q document are true and, correct. to the best Qf .ale kGO'19C@e ( X,:liolaHP t1OQ ( an'8 bali& BliQ that -le is au=hori ed to execute "'he c=.ocv~e~t on behalf of sai8 f g Licessae.
Rober" R. Uhr q Svasc ihec'.".c: swor. to before me th's CQ J~'f NOT'ABY PU~>X C, in am'x'l~f~fhe County of Da&e, S'tD 0 0 Pluri IMV $ TATc Qf f~~g p7 ~~
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l TQ Ponrx,r s L 7 xema~ln August 3r i&76 Re: <.8 I,uci q Linc t.:4o. 3, Page i Opcx'8.ti 1lg I col'c OPS- 67 Candid.ion of License J Since the i-suance of Amenc":mont 4 to DPH-67, the pcx'formance of.'he CHDM has improved considerably. Althougtr it x'eclui red beati J>g the RCS to approxima tele 360<F before the CEDN initially coul<'. bo withdrawn, consis "cntly, it now reaches this level of operation at approxirretel.y 290oi'. 'She rod has been tested on several occasdons "S.nce the initia3. colo rod cxrop time testing-On June 3.2, 3 9 I 6, during a maintenar.ce shutdown, and fol Lowing
,'oo3c'.own to 260oF, the rod v:as <<Kthr3x'own three times in succes-sion anQ dropped once to verify it.s previous timing. Xt was thes'x v:i thdrae,n and dropped nine times '-n succession un8er various flow conditions in accorr3ancq v.'ith the test, procedure. During the heatup bacF". to 'pov er on June 18, 1976, the rod v;as again tested and was v~ithara~in successfully at. 260oF. fowever, on $
July 10, 1976, during the shutdown to inue.tigate an observed power di stribution anomaly and fol logic cooMo~m to 260oF, t.he rod ~~as successfu3.3y vi thdre.wn on t.he first, at tempt, but. cou3.d not be ful3y vi thdrawrx on succeeding a'tempts. '1'bus, although considerable improvement has been observed in its v;ithdrawal at 3.ov ternpercat<<re, the Cabot'ontinues to shove some inconsis-teTxcy 5n its perforrnarrce.
Despite this i neon".i stency successive r,'ithdrawal o f the rod the test. t.en~perature has occurred suf ficieot.l y to a11o~ cov~pletion of the cold roc~ r3rop time testing. These tcs s c.. tablish the rod cont.ro3.led by CRD~1 44 a, the Ca test. rod during successive drops z~t low temi~czntnze u."idler vari ous flovr conditions These
<>ate> .3iave been revie>>c'.c'. by the Faci 3 it y Reviev'roup and are ava$ 3ob3e on "ite for re+'vI by Region IL 26K personnel.
Hilviog sate sf actor i 1) co%pl 6 ted the regvircd te o~ CERN 44 loses any signi r.icgnce it have had ti lip the repair as g
a Condition may of Li car c. Di.faculty in witMrav:a3. at low temperature now has onl.y operat.ional significance "incc a Sully inserted rod iappropriately s inhex Qn'tly sa fe Thus the repaix. 0 f CHON 4 4 bee orucs more a rovtiJ)e maintenance item rather than a Condition of License. Furthermore, the perfornarxce of the rod at. low tempt- ra tvre doe not <<vezx have oper a tional si on i f icance since FPL has no i.ntenti on of reinstat.ing Technica3. Speci. f icat:i on 3.3D. 3 which ivogld allow 1ow temperature criticality.
hl.though FPE beLievcs that Section J is no 3,anger a necessary Conc. i ti on of' icense, FPL does plan to undex't.ake inspection of the rnechani.sm during the'resent outage Vpon .r emoval of the CEDM upper <guide structure, the extension shaft of CEDH 44 ail.1 bc visua) 3y inspected. Following x'erriova3. o$ the reactor head, the mechanism ail.1 be inspected internally using a
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~~UN'T.~ VOX t Aug< -', 1976 I
Ope;a -ir.r Lice:is'e DPR-C7
'8a".~x.C ion of lex cenGC boroscopi.. to Qe+cr:.n ne @bethe anv ivat.eria3. obstructions icjYsL.'zi.ticMAoiv2.its cg st.
cnc~rgiaad an~ 'he gripocrs .~ii3.3 '.je exercisac3.
I Thc CEQYi co) H wil3. then be ox'ari
~'he horoscope vill vil be urea to obsess've their m. nner ofcompl.etymon 1 be x>ader t.aken a, red,ui roc~. Upon operate on. Flushing of thi s in-spect 1 0'0 and QQ !Yf the s 948 cogent }Jeat Qp ~ CEDN l 4 vile agan 0
~
be tested a" 260 P. The its-ection efforts replacement for CEDN 44 are expect.ed to xequi re one wee ~. Since necks .ax'y, and since reolace~cnt ~oui@ require t~:a weel:s to t may cor!)piete vhich wool(',, ',hereby, interfere with the present
, reactor inspectien and t.es be o f in'rop am (the reactor head >rill for only one. v eR}, replacement of CEDt4 44 is not
'plan'net ciu in@ this ovta~e. Should the ef fox ts dux'in@ t hi..
ovta~e prove unsccccs=-;..x~1, the roecnani Gw
,the next scheduled refueling outage and. replaced 5.f necessary.
vill be tea ed during All indications are the CFOG 44, which is located in t.he
'norther quadrant of t.he core, is not a factor in the pone" distribution anomaly which has been observed in the nor" hi~'est qua6x'ant of the core.
On. t he basis e f the forcqoi n-, F'PL believes that fied the reoiii >eriients leveeing to the unco-"r Qratxon of Scctxon it has sat is-into the St. Jucie Unit Yo. l Operati>>g I icense and that.
futu-e. repair or repla<QK" lt of CFTJM 44 i a routine maintenance lnatter. This repair is no ciif fez'oned, from that of. any other CEDN vL>ich fai3.s to opera"e prod lv during t he service life o the rcactox. Repair or rep3.acescent. of CF.D! l 44 vril3. be undertaken in a Nanne which vill not impact the present.
schedule for inspection. anc'. test.in'o resolve t.he observed poi ex'.x.s ribtxtion inc.maly. Accordingly, FP?, reaues s that Section J of. Enclosure ) to the St. Lucie Unit. Yo. l Operating I icense be de le ted..
n Yours verjj t:x-uly, S {p~
h C/l prl
~C7
~ ~ X~
Robert E. Uhri g a Vice President REV/I LI./hlc cc: Nolan C. Noseley, Region XI J ack R Nemnan, Esq .
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