|
---|
Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-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) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 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, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 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 IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 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-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes 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-2023-112, 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 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 1 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 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 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 ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review 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) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request 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) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 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 IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter 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 ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[Table view] |
See also: IR 05000335/2007006
Text
June 5, 2007
Florida Power and Light Company
ATTN: Mr. J. A. Stall, Senior Vice President
Nuclear and Chief Nuclear Officer
P. O. Box 14000
Juno Beach, FL 33408-0420
SUBJECT: NOTIFICATION OF ST. LUCIE NUCLEAR PLANT - COMPONENT DESIGN
BASES INSPECTION - NRC INSPECTION REPORT 05000335/2007006,
05000389/2007006
Dear Mr. Stall:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a component design bases inspection at your St. Lucie Nuclear Plant
during the weeks of August 27-31, 2007, September 10-14, 2007 and September 24-28, 2007.
The inspection team will be led by Mr. R. Moore, a Senior Reactor Inspector from the NRC's
Region II Office. This inspection will be conducted in accordance with the baseline inspection
procedure, Procedure 71111.21, Component Design Bases Inspection, issued June 22, 2006.
The inspection will evaluate the capability of risk significant / low margin components to function
as designed and to support proper system operation. The inspection will also include a review of
selected operator actions, operating experience, and modifications.
During a telephone conversation on May 29, 2007, Mr. R. Moore confirmed with
Mr. D. Cecchett of your staff, arrangements for an information gathering site visit and the three-
week onsite inspection. The schedule is as follows:
- Information gathering visit: Week of August 13-17, 2007
- Onsite weeks: August 27-31, 2007, September 10-14, 2007 and September 24-
28, 2007.
The purpose of the information gathering visit is to meet with members of your staff to identify
risk-significant components and operator actions. Information and documentation needed to
support the inspection will also be identified. Mr. Rudy Bernhard, a Region II Senior Reactor
Analyst, may accompany Mr. Moore during the information gathering visit to review probabilistic
risk assessment data and identify risk significant components which will be examined during the
inspection.
The enclosure lists documents that will be needed prior to the information gathering visit. Please
contact Mr. Moore prior to preparing copies of the materials listed in the enclosure and provide
this information to the Region II office by August 1, 2007.
FP&L 2
The inspectors will try to minimize your administrative burden by specifically identifying only
those documents required for the inspection preparation.
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space, supplemental documents requested to be made
available to the team in the Region II office prior to the inspection preparation week of
August 20-24, 2007; arrangements for site access; and the availability of knowledgeable plant
engineering and licensing personnel to serve as points of contact during the inspection.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRC's document system
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
Thank you for your cooperation in this matter. If you have any questions regarding the
information requested or the inspection, please contact Mr. Moore at (404) 562-4628 or me at
(404) 562-4876.
Sincerely,
/RA/
L.M. Cain, Acting Branch Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.:50-335, 50-389
License Nos.:DPR-67, NPF-16
Enclosure: Information Request for St. Lucie Nuclear Plant
Component Design Bases Inspection
cc w/encl:
FP&L 3
cc w/encl: Marjan Mashhadi, Senior Attorney
William E. Webster Florida Power & Light Company
Vice President, Nuclear Operations Electronic Mail Distribution
Florida Power & Light Company
Electronic Mail Distribution William A. Passetti
Bureau of Radiation Control
Gordon L. Johnston Department of Health
Site Vice President Electronic Mail Distribution
St. Lucie Nuclear Plant
Florida Power & Light Company Craig Fugate, Director
Electronic Mail Distribution Division of Emergency Preparedness
Department of Community Affairs
Christopher R. Costanzo Electronic Mail Distribution
Plant General Manager
St. Lucie Nuclear Plant J. Kammel
Electronic Mail Distribution Radiological Emergency
Planning Administrator
Bill Parks Department of Public Safety
Operations Manager Electronic Mail Distribution
St. Lucie Nuclear Plant
Electronic Mail Distribution Douglas Anderson
County Administrator
Terry L. Patterson St. Lucie County
Licensing Manager 2300 Virginia Avenue
St. Lucie Nuclear Plant Ft. Pierce, FL 34982
Electronic Mail Distribution
Mark Warner, Vice President
Nuclear Operations Support
Florida Power & Light Company
Electronic Mail Distribution
Rajiv S. Kundalkar
Vice President - Nuclear Engineering
Florida Power & Light Company
Electronic Mail Distribution
Seth B. Duston
Training Manager
St. Lucie Ocean Drive
Florida Power & Light Company
Electronic Mail Distribution
M. S. Ross, Managing Attorney
Florida Power & Light Company
Electronic Mail Distribution
______
OFFICE RII:DRS RII:DRS RII:DRP RII:DRS
SIGNATURE /RA/ /RA/ /RA L.M. Cain for/
NAME RBernhard RMoore MErnstes
DATE 5/31 /2007 5/31 /2007 5/31 /2007
E-MAIL COPY? YES NO YES NO YES NO YESNO YES NO YES NO YES NO
St. Lucie Information Request for CDBI
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM or offsite accessible FTP website. The CDROM should be indexed and hyperlinked to
facilitate ease of use. Lists should contain enough information to be easily understood to
someone who has a knowledge of pressurized water reactor technology.
1. From your most-recent probabilistic safety analysis (PSA) excluding external events and
fires:
a. Two risk rankings of components from your site-specific probabilistic safety analysis
(PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by
Birnbaum Importance.
b. A list of the top 500 cutsets.
2. From your most-recent probabilistic safety analysis (PSA) including external events and
fires:
a. Two risk rankings of components from your site-specific probabilistic safety analysis
(PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by
Birnbaum Importance.
b. A list of the top 500 cutsets..
3. Risk ranking of operator actions from your site specific PSA sorted by RAW. Provide
copies of your human reliability worksheets for these items..
4. Any pre-existing evaluation or list of components and calculations with low design margins
(i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design
required output, heat exchangers close to rated design heat removal, MOV risk-margin
rankings, etc.).
5. A list of station applicability evaluations/reviews performed and documented in the station
corrective action program in the past two years for industry events, critical equipment
failures, and safety related equipment vulnerabilities [as communicated by NRC generic
communications, industry communications, 10 CFR part 21 notifications, etc.]
6. This item deleted. Modification lists will be requested after the component sample is
determined.
7. This item deleted. Corrective action lists will be requested after the component sample is
determined.
8. A list of common-cause failure of components that have occurred at St. Lucie and have
been identified within the last five years.
9. A list of operability evaluations completed within the last two years, sorted by associated
component or system.
10. Contact information for a person to discuss PRA information prior to the information
gathering trip: name, title, phone number, and e-mail address
11. List of equipment currently on the sites Station Equipment Reliability Issues List, including
a description of the reason(s) why each component is on that list and summaries (if
available) of your plans to address those reasons.
12. List of equipment currently in RIS 05-020 (formerly GL 91-18) status.
13. List of equipment currently in MR (a)(1) status.
Enclosure