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Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML22303A0322022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML22303A0162022-10-20020 October 2022 Updated Final Safety Analysis Report and License Renewal 10 CFR 54.37(b) Report ML22303A0262022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System ML22303A0242022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 2, Site and Environment ML22303A0392022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 16, Aging Management Programs and Time-Limited Aging Analyses Activities ML22303A0352022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 13, Initial Tests and Operations ML22303A0332022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 11, Waste Disposal and Radiation Protection System ML22303A0382022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 15, Technical Specifications ML22303A0422022-10-20020 October 2022 Updated Final Safety Analysis Report, Appendix B, Questions and Responses Related to Initial NRC Review of Operating License Application ML22303A0302022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 8, Electrical Systems ML22303A0402022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 17, Aging Management Programs and Time-Limited Aging Analysis Activities ML22303A0252022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 3, Reactor ML22303A0222022-10-20020 October 2022 Updated Final Safety Analysis Report, List of Effective Pages ML22303A0272022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 5, Structures ML22303A0282022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML22303A0292022-10-20020 October 2022 Updated Final Safety Analysis Report, Chapter 7, Instrument and Control ML22303A0372022-10-20020 October 2022 Updated 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Update to Updated Final Safety Analysis Report, Chapter 21, Appendix B ML21145A2812021-05-12012 May 2021 Update to Updated Final Safety Analysis Report ML21145A2732021-05-12012 May 2021 Update to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications ML21145A2822021-05-12012 May 2021 Update to Updated Final Safety Analysis Report, Chapter 3, Reactor ML21145A2692021-05-12012 May 2021 Update to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML21145A2802021-05-12012 May 2021 Update to Updated Final Safety Analysis Report, Chapter 11, Waste Disposal and Radiation Protection System ML21145A2672021-05-12012 May 2021 Update to Updated Final Safety Analysis Report, Chapter 7, Instrument and Control ML21145A2742021-05-12012 May 2021 Update to Updated Final Safety Analysis Report, Chapter 17, Aging Management Programs and Time-Limited Aging Analysis Activities ML21145A2762021-05-12012 May 2021 Update to Updated Final Safety Analysis 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System ML21145A2772021-05-12012 May 2021 Update to Updated Final Safety Analysis Report, Chapter 8, Electrical Systems ML21145A2682021-05-12012 May 2021 Update to Updated Final Safety Analysis Report, Chapter 16, Aging Management Programs and Time-Limited Aging Analysis Activities ML21145A2702021-05-12012 May 2021 Update to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary ML21145A2792021-05-12012 May 2021 Update to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features L-2018-237, Integrated Final Safety Analysis Report Tier 1, Rev. 02018-12-21021 December 2018 Integrated Final Safety Analysis Report Tier 1, Rev. 0 ML18117A1172018-04-26026 April 2018 Updated Final Safety Analysis Report, Chapter 14,Safety Analysis,Appendix 14A Thru Appendix 14G ML18117A1192018-04-26026 April 2018 Updated Final Safety Analysis Report, Chapter 15, Technical Specifications ML18117A1212018-04-26026 April 2018 Updated Final Safety Analysis Report, Chapter 16, Aging Management Programs and Time-Limited Aging Analyses Activities ML18117A1222018-04-26026 April 2018 Updated Final Safety Analysis Report, Appendix a, a Functional Evaluation of the Components of the Systems Which Are Shared by the Two Units 2022-10-20
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TABLE OF CONTENTS
Section Title Page 12 CONDUCT OF OPERATIONS 12-1
12.1 Organization and Responsibility 12-1
12.2 Training 12-1
12.3 Procedures 12-1
12.4 Records 12-1
12.5 Administrative Control 12-1
12.6 Plant Security Plan 12-1
12.7 Deleted 12-2
12.8 Deleted 12-2
12.9 Deleted 12-2
12.10 Process Control Program (PCP) 12-2
12.11 Emergency Planning 12-3
12-i Revised 04/17/2013 C26 12-1 Rev. 17
- 12. CONDUCT OF OPERATIONS 12.1 Organization and Responsibility
This section covered the positions and personnel at the time of initial plant startup and operation. This information can be found in the original
docketed FSAR and this is also addressed in the plant operating license (Technical Specifications).
12.2 Training
This section covered the training program at the time of initial plant startup and operation. This information can be found in the original
docketed FSAR and this is also addressed in the Technical Specifications.
12.3 Procedures
The operating procedures for startup, normal operations, and anticipated emergency operating conditions is addressed in the original docketed FSAR and current requirements indicated in the Technical Specifications and in this chapter. The Emergency Plan in effect for Turkey Point is issued as a separate document.
12.4 Records
The procedure for maintaining plant operating, maintenance, QA, personnel, training, and instrumentation and control record is addressed in the original docketed FSAR and current requirements indicated in the Technical Specifications and in this chapter.
12.5 Administrative Control
The necessary administrative procedures are addressed in the original docketed FSAR and current requirements indicated in the Technical Specifications and in this chapter.
12.6 Plant Security Plan
Turkey Point maintains a Plant Security Plan and is issued as a separate document.
12-2 Revised 10/11/2007 The FPL Quality Assurance Program is described by FPL Quality Assurance Topical Report (QATR) FPL-1. This corporate level document was supplemented by UFSAR Sections 12.7 through 12.10 which contained plant specific details of the FPL QA program related to Administrative Controls. These sections were originally located in the Technical Specifications and were relocated to the UFSAR by Technical Specification Amendment No. 201/195 (NRC Safety Evaluation report related to Amendment No. 201/195, dated October 6, 1999). These sections are subject to the regulatory requirements of 10 CFR 50.54 (a) with respect to changes to the approved QA program description. Sections 12.7, 12.8, and 12.9 were subsequently relocated from the UFSAR and placed into the QATR in accordance with the QATR Change Management Plan, NRC SER dated December 29, 2006, and Condition Report 2006-12055.
12.7 Deleted 12.8 Deleted 12.9 Deleted 12.10 Process Control Program (PCP)
12.10.1 The Process Control Program (PCP) shall contain the current formulas, sampling, analyses, tests and determinations to ensure that processing and
packaging of solid radioactive wastes based on demonstrated processing of
actual or simulated wet solid wastes will be accomplished in such a way as
to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal
of solid radioactive waste.
12.10.2 Licensee-initiated changes to the PCP:
- a. Shall be documented and records of reviews performed shall be retained as required by the QTAR. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable
regulations.
- b. Shall become effective after review and acceptance by the PNSC and the approval of the Plant Manager.
C23C23 12.11 Emergency Planning The Emergency Plan describes Florida Power & Light Company's plans for responding to emergencies that may develop at the Turkey Point Plant. The plan has been prepared to meet the requirements of 10 CFR 50.47(b), 10 CFR 50.72, and 10 CFR50 Appendix E. The purpose of this plan is to define and assign authority and responsibility in order to protect the health and safety of the public and plant personnel.
This plan applies to all plant emergencies which have resulted in, or which increase the risk of the accidental release of radioactive materials.
The Emergency Plan defines emergency conditions and delineates the responsibilities and duties of the FPL Emergency Response Organization.
Associated with this Emergency Plan are implementing procedures which provide a detailed source of pertinent information and data required by the response organization during an emergency.
An Onsite Technical Support Center (TSC), an Onsite Operations Support Center (OSC), and an Offsite Emergency Operations Facility (EOF) have been established. Emergency support facilities meet the requirements of NUREG 0737, Item III.A.1.2 The Offsite Emergency Operations Facility (EOF) is located at the FPL General Office Building (9250 W. Flagler in Miami).
This facility is approximately 25 miles north of Turkey Point station.
The Technical Support Center is located in a separate building at the back of the property near the Circulating Water Inlet Bay. The Operations Support Center is located in the Maintenance Building.
12-3 Revised 04/17/2013 C26