L-2017-023, Updated Final Safety Analysis Report -Unit 4 Cycle 28 Update Chapter 12 Update

Updated Final Safety Analysis Report -Unit 4 Cycle 28 Update Chapter 12 Update

ML17045A521
Person / Time
Site:	Turkey Point
Issue date:	02/14/2017
From:	Summers T Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2017-023
Download: ML17045A521 (7)

Text

10 CFR §50.71(e)

L-2017-023 February 14, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Updated Final Safety Analysis Report - Unit 4 Cycle 28 Update Chapter 12 Update

Reference:

Florida Power & Light Company letter L-2016-198, "Updated Final Safety Analysis Report - Unit 4 Cycle 28 Update and License Renewal 10 CFR 54.37(b) Report,"

October 29, 2016 Florida Power & Light Company submitted the Unit 4 Cycle 28 (4C28) update of the Turkey Point Units 3 and 4 Updated Final Safety Analysis Report (UFSAR) in the above Reference.

This letter submits UFSAR Chapter 12 pages 12-i, 12-3, 12-4 and 12-5 with a corresponding change to page 34 in the list of effective pages (LOEP), and is due to the inadvertent inclusion of an outdated Chapter 12 file on the DVD (012CHAPTER _12.pdf 67 KB) submitted by the Reference.

The attachment to this letter contains the LOEP and Chapter 12 pages identified above.

If you have any questions, please contact Mr. Mitch Guth, Licensing Manager, at 305-246-6698.

Sincerely,

~~r- ers ----

Regional Vice President - Southern Region Turkey Point Nuclear Plant

Attachment:

Updated Final Safety Analysis Report Updated Pages cc: Regional Administrator - USNRC Region II USNRC Senior Resident Inspector - Turkey Point USNRC Project Manager - Turkey Point Florida Power & Light Company 9760 SW 344th Street, Homestead, FL 33035

Florida Power & Light Company L-2017-023 Update to UFSAR Chapter 12 Attachment Attachment Turkey Point Updated Final Safety Analysis Report Updated Pages (5 pages follow)

UPDATED FINAL SAFETY ANALYSIS REPORT TURKEY POINT UNITS 3 & 4 LIST OF EFFECTIVE PAGES PAGE REV PAGE REV CHAPTER 12 Contents Figure 12-i 04/17/2013 14-1 04/17/2013 Text Text 12-1 17 14.1-1 04/17/2013 12-2 10/11/2007 14.1-2 04/17/2013 12-3 06/10/2016 12-4 06/10/2016 14.1.1-1 04/17/2013 12-5 06/10/2016 14.1.1-2 04/17/2013 14.1.1-3 04/17/2013 CHAPTER 13 14.1.1-4 04/17/2013 14.1.1-5 04/17/2013 Text 14.1.1-6 04/17/2013 13-1 03/11/2016 Table CHAPTER 14 14.1.1-1 04/17/2013 Contents Figure 14-i 04/17/2013 14.1.1-1 04/17/2013 14-ii 04/17/2013 14.1.1-2 04/17/2013 14-iii 04/17/2013 14.1.1-3 04/17/2013 14-iv 04/17/2013 14.1.1-4 04/17/2013 14-v 04/17/2013 14-vi 04/17/2013 Text 14-vii 14 14-viii 04/17/2013 14.1.2-1 04/17/2013 14-ix 04/17/2013 14.1.2-2 04/17/2013 14-x 04/17/2013 14.1.2-3 04/17/2013 14-xi 04/17/2013 14.1.2-4 02/09/2016 14-xii 07/28/2016 14.1.2-5 04/17/2013 14-xiii 07/28/2016 14-xiv 04/17/2013 Table 14-xv 04/17/2013 14-xvi 04/17/2013 14.1.2-1 14 14-xvii 04/17/2013 14-xviii 04/17/2013 Figure 14-xix 04/17/2013 14-xx 04/17/2013 14.1.2-1 04/17/2013 14-xxi 10/11/2007 14.1.2-2 04/17/2013 14.1.2-3 04/17/2013 Text 14.1.2-4 04/17/2013 14.1.2-5 04/17/2013 14-1 04/17/2013 14.1.2-6 04/17/2013 14-2 04/17/2013 14.1.2-7 04/17/2013 14-3 04/17/2013 14.1.2-8 04/17/2013 14-4 04/17/2013 14-5 04/17/2013 14-6 04/17/2013 Revised 07/28/2016 LOEP-34

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 12.12 Relocated Technical Specifications C28 Requirements 12-3 12-i Revised 06/10/2016

12.11 Emergency Planning The Emergency Plan describes Florida Power & Light Companys 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.

12.12 Relocated Technical Specifications Requirements This section of the UFSAR contains requirements (limiting conditions for operation, applicability, action statements, and surveillance requirements) that have been relocated from the Technical Specifications.

License amendments approved removal of these requirements from the C28 Technical Specifications on the basis that they do not meet the criteria in 10 CFR 50.36 for inclusion in the Technical Specifications. These relocated requirements are controlled under 10 CFR 50.59. The frequencies of the surveillance requirements included in this section may be extended up to 25% of the specified time interval.

12-3 Revised 06/10/2016

12.12.1 Communications The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.

Limiting Condition for Operation:

Direct communications shall be maintained between the control room and personnel at the refueling station.

Applicability:

During CORE ALERTATIONS Action:

When direct communications between the control room and personnel at the refueling station cannot be maintained, suspend all CORE C28 ALTERATIONS.

Surveillance Requirements:

Direct communications between the control room and personnel at the refueling station shall be demonstrated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to the start of and in accordance with the Surveillance Frequency Control Program during CORE ALTERATIONS.

12.12.2 Manipulator Crane The requirements for the manipulator cranes ensure that: (1) manipulator cranes will be used for movement of drive rods and fuel assemblies, (2) each crane has sufficient load capacity to lift a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

The requirement that the auxiliary hoist load indicator be used to prevent lifting excessive loads will require a manual action. The auxiliary hoist load indicator does not include any automatic mechanical or electrical interlocks that prevent lifting loads in excess of 600 pounds.

12-4 Revised 06/10/2016

Limiting Condition for Operation:

The manipulator crane and auxiliary hoist shall be used for movement of drive rods or fuel assemblies and shall be OPERABLE with:

a. The manipulator crane used for movement of fuel assemblies having:

1) A minimum capacity of 2750 pounds, and

2) An overload cutoff limit less than or equal to 2700 pounds.

b. The auxiliary hoist used for latching and unlatching drive rods having:

1) A minimum capacity of 610 pounds, and

2) A load indicator which shall be used to prevent lifting loads in excess of 600 pounds.

Applicability:

During movement of drive rods or fuel assemblies within the reactor vessel.

C28 Action:

With the requirements for crane and/or hoist OPERABILITY not satisfied, suspend use of any inoperable manipulator crane and/or auxiliary hoist from operations involving the movement of drive rods and fuel assemblies within the reactor vessel.

Surveillance Requirements:

1. At least once each refueling, each manipulator crane used for movement of fuel assemblies within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least 2750 pounds and demonstrating an automatic load cutoff when the crane load exceeds 2700 pounds.

2. At least once each refueling, each auxiliary hoist and associated load indicator used for movement of drive rods within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least 610 pounds.

12-5 Revised 06/10/2016