Text

Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual
	ML20304A403
Person / Time
Site:	Sequoyah
Issue date:	10/28/2020
From:	Hunnewell S; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	EPL-1
	Download: ML20304A403 (157)
	v • d • e

Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 October 28, 2020 10 CFR 50.4 10 CFR 50.71(e)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual

References:

1. NRC Letter to TVA, Issuance of Exemption to 10 CFR [50.] 71(e)(4) for the Sequoyah Nuclear Plant, Units 1 and 2 (TAC Nos. MA0646 and MA0647),

dated March 9, 1998

2. TVA Letter to NRC, Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual, dated May 29, 2019 Pursuant to 10 CFR 50.71(e) and the Reference 1 letter, updates to the Sequoyah Nuclear Plant (SQN) Updated Final Safety Analysis Report (UFSAR) for both Units 1 and 2 are to be submitted within 180 days following each Unit 2 refueling outage, but not to exceed 24 months between successive revisions. The SQN Technical Requirements Manual (TRM) is incorporated by reference into the SQN UFSAR. This letter provides NRC updates to the TRM since the update provided in the Reference 2 letter. The last Unit 2 refueling outage ended on May 4, 2020, and as such these updates are required by November 2, 2020. The enclosure to this letter provides a description of the TRM revisions with attachments of the updated pages.

U.S. Nuclear Regulatory Commission Page 2 October 28, 2020 There are no new regulatory commitments contained in this letter. If you have any questions, please contact Mr. Andrew McNeil, SQN Licensing Manager (Acting), at (423) 843-8098.

I certify that I am duly authorized by TVA, and that, to the best of my knowledge and belief, the information contained herein accurately presents changes made since the previous submittal, necessary to reflect information and analyses submitted to the Commission or prepared pursuant to Commission requirements.

Respectfully,

~unn~lnH1!~"'4v Interim Site Vice President Sequoyah Nuclear Plant

Enclosure:

Description of Revisions for the Sequoyah Nuclear Plant (SQN) Units 1 and 2, Technical Requirements Manual (TRM) cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector- Sequoyah Nuclear Plant

ENCLOSURE DESCRIPTION OF REVISIONS FOR THE SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2, TECHNICAL REQUIREMENTS MANUAL (TRM)

Technical Requirements Manual (TRM) Revisions TRM Revision 62 was approved on July 11, 2019, and implemented on July 26, 2019. The change revised Technical Requirement (TR) 8.6.2, Ice Bed Temperature Monitoring System Contingency Measure, B.4. The Contingency Measure, B.4, was revised for consistency with the Final Safety Analysis Report, Section 6.5.7.2 System Design, 1. Air Handling Units wherein the optimum normal operating temperature of the ice condenser has been demonstrated to be 19 degree Fahrenheit (°F) in order to minimize concrete expansion, floor heaving, and frost buildup. The value of 19°F is the mean value in the range of 18 to 20°F, representing the ice and static air in the ice condenser. The selected upper range value provides a comparative limit to the design parameter of the refrigeration system performance described in UFSAR 6.5.6, Refrigeration System.

Attachment:

Sequoyah Nuclear Plant, Technical Requirements Manual - Changed Pages E1-1

ATTACHMENT SEQUOYAH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CHANGED PAGES TRM Affected Pages EPL-4 EPL-9 8.6.2-1

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL REQUIREMENTS MANUAL

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTING Page Revision Table of Contents page i ................................................................................................... 08/31/16 Table of Contents page ii .................................................................................................. 10/23/15 6.0-1 .................................................................................................................................. 10/23/15 7.1-1 .................................................................................................................................. 10/23/15 7.1-2 .................................................................................................................................. 10/23/15 7.1-3 .................................................................................................................................. 10/23/15 7.2-1 .................................................................................................................................. 10/23/15 7.2-2 .................................................................................................................................. 10/23/15 7.2-3 .................................................................................................................................. 10/23/15 7.3-1 .................................................................................................................................. 10/23/15 7.3-2 .................................................................................................................................. 10/23/15 7.3-3 .................................................................................................................................. 10/23/15 7.3-4 .................................................................................................................................. 10/23/15 7.3-5 .................................................................................................................................. 10/23/15 7.3-6 .................................................................................................................................. 10/23/15 7.4-1 .................................................................................................................................. 10/23/15 7.4-2 .................................................................................................................................. 10/23/15 7.4-3 .................................................................................................................................. 10/23/15 7.4-4 .................................................................................................................................. 10/23/15 7.4-5 .................................................................................................................................. 10/23/15 7.4-6 .................................................................................................................................. 10/23/15 7.5-1 .................................................................................................................................. 10/23/15 7.5-2 .................................................................................................................................. 10/23/15 EPL-1 August 31, 2016

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTING Page Revision 7.6-1 .................................................................................................................................. 10/23/15 8.1.1-1 ............................................................................................................................... 10/23/15 8.1.1-2 ............................................................................................................................... 10/23/15 8.1.1-3 ............................................................................................................................... 04/04/16 8.1.1-4 ............................................................................................................................... 10/23/15 8.1.1-5 .............................................................................................................................08/29/16A 8.1.2-1 ............................................................................................................................... 10/23/15 8.1.2-2 ............................................................................................................................... 10/23/15 8.1.2-3 ............................................................................................................................... 10/23/15 8.1.2-4 ............................................................................................................................... 10/23/15 8.1.2-5 ............................................................................................................................... 08/29/16 8.1.2-6 ............................................................................................................................... 10/23/15 8.1.3-1 ............................................................................................................................... 10/23/15 8.1.3-2 ............................................................................................................................... 10/23/15 8.1.3-3 ............................................................................................................................... 10/23/15 8.3.1-1 ............................................................................................................................... 10/23/15 8.3.1-2 ............................................................................................................................... 10/23/15 8.3.1-3 ............................................................................................................................... 10/23/15 8.3.2-1 ............................................................................................................................... 10/23/15 8.3.2-2 ............................................................................................................................... 10/23/15 8.3.2-3 ............................................................................................................................... 10/23/15 8.3.2-4 ............................................................................................................................... 09/27/16 8.3.2-5 ............................................................................................................................... 10/23/15 8.3.2-6 ............................................................................................................................... 10/23/15 EPL-2 September 27, 2016

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTING Page Revision 8.3.2-7 ............................................................................................................................... 10/23/15 8.3.2-8 ............................................................................................................................... 10/23/15 8.3.2-9 ............................................................................................................................... 10/23/15 8.3.3-1 ............................................................................................................................... 10/23/15 8.3.3-2 ............................................................................................................................... 10/23/15 8.3.3-3 ............................................................................................................................... 10/23/15 8.3.4-1 ............................................................................................................................... 11/25/15 8.3.4-2 ............................................................................................................................... 10/23/15 8.3.4-3 ............................................................................................................................... 08/23/17 8.3.4-4 ............................................................................................................................... 10/23/15 8.3.4-5 ............................................................................................................................... 10/23/15 8.3.4-6 ............................................................................................................................... 10/23/15 8.3.4-7 ............................................................................................................................... 10/23/15 8.3.4-8 ............................................................................................................................... 10/23/15 8.3.5-1 ............................................................................................................................... 10/23/15 8.3.5-2 ............................................................................................................................... 10/23/15 8.3.5-3 ............................................................................................................................... 10/23/15 8.3.6-1 (Deleted) ............................................................................................................... 08/31/16 8.3.6-2 (Deleted) ............................................................................................................... 08/31/16 8.4.1-1 ............................................................................................................................... 10/23/15 8.4.1-2 ............................................................................................................................... 10/23/15 8.4.1-3 ............................................................................................................................... 10/23/15 8.4.1-4 ............................................................................................................................... 10/23/15 8.4.2-1 ............................................................................................................................... 10/23/15 EPL-3 August 23, 2017

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTING Page Revision 8.4.2-2 ............................................................................................................................... 10/23/15 8.4.2-3 ............................................................................................................................... 10/23/15 8.4.2-4 ............................................................................................................................... 10/23/15 8.4.2-5 ............................................................................................................................... 10/23/15 8.4.3-1 ............................................................................................................................... 10/07/16 8.4.3-2 ............................................................................................................................... 10/23/15 8.4.3-3 ............................................................................................................................... 10/07/16 8.6.1-1 ............................................................................................................................... 10/23/15 8.6.1-2 ............................................................................................................................... 10/23/15 8.6.1-3 ............................................................................................................................... 10/23/15 8.6.2-1 ............................................................................................................................... 07/11/19 8.6.2-2 ............................................................................................................................... 10/23/15 8.6.2-3 ............................................................................................................................... 10/23/15 8.6.3-1 ............................................................................................................................... 10/23/15 8.6.3-2 ............................................................................................................................... 10/23/15 8.6.3-3 ............................................................................................................................... 10/23/15 8.6.4-1 ............................................................................................................................... 10/23/15 8.6.4-2 ............................................................................................................................... 10/23/15 8.6.4-3 ............................................................................................................................... 10/23/15 8.7.1-1 ............................................................................................................................... 10/23/15 8.7.1-2 ............................................................................................................................... 10/23/15 8.7.1-3 ............................................................................................................................... 10/23/15 8.7.2-1 ............................................................................................................................... 10/23/15 8.7.2-2 ............................................................................................................................... 10/23/15 EPL-4 July 11, 2019

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTING Page Revision 8.7.2-3 ............................................................................................................................... 10/23/15 8.7.3-1 ............................................................................................................................... 10/23/15 8.7.3-2 ............................................................................................................................... 10/23/15 8.7.3-3 ............................................................................................................................... 10/23/15 8.7.3-4 ............................................................................................................................... 10/23/15 8.7.3-5 ............................................................................................................................... 10/23/15 8.7.3-6 ............................................................................................................................... 10/23/15 8.7.3-7 ............................................................................................................................... 10/23/15 8.7.3-8 ............................................................................................................................... 10/23/15 8.7.3-9 ............................................................................................................................... 10/23/15 8.7.3-10 ............................................................................................................................. 10/23/15 8.7.3-11 ............................................................................................................................. 10/23/15 8.7.3-12 ............................................................................................................................. 10/23/15 8.7.3-13 ............................................................................................................................. 10/23/15 8.7.3-14 ............................................................................................................................. 10/23/15 8.7.4-1 ............................................................................................................................... 10/23/15 8.7.4-2 ............................................................................................................................... 10/23/15 8.7.4-3 ............................................................................................................................... 10/23/15 8.7.5-1 ............................................................................................................................... 10/23/15 8.7.5-2 ............................................................................................................................... 02/21/19 8.7.5-3 ............................................................................................................................... 06/08/18 8.7.5-4 ............................................................................................................................... 02/21/19 8.7.6-1 ............................................................................................................................... 10/23/15 8.7.6-2 ............................................................................................................................... 10/23/15 EPL-5 February 21, 2019

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTING Page Revision 8.7.6-3 ............................................................................................................................... 10/23/15 8.7.7-1 ............................................................................................................................... 10/23/15 8.7.7-2 ............................................................................................................................... 10/23/15 8.7.7-3 ............................................................................................................................... 10/23/15 8.7.8-1 ............................................................................................................................... 10/23/15 8.7.8-2 ............................................................................................................................... 10/23/15 8.7.9-1 ............................................................................................................................... 10/23/15 8.7.9-2 ............................................................................................................................... 10/23/15 8.8.1-1 ............................................................................................................................... 10/23/15 8.8.1-2 ............................................................................................................................... 10/23/15 8.8.1-3 ............................................................................................................................... 04/24/17 8.8.1-4 ............................................................................................................................... 04/24/17 8.8.1-5 ............................................................................................................................... 04/24/17 8.8.2-1 ............................................................................................................................... 10/23/15 8.8.2-2 ............................................................................................................................... 10/23/15 8.8.3-1 ............................................................................................................................... 10/23/15 8.8.3-2 ............................................................................................................................... 04/24/17 8.8.3-3 ............................................................................................................................... 04/24/17 8.8.4-1 ............................................................................................................................... 10/23/15 8.8.4-2 ............................................................................................................................... 01/27/17 8.8.4-3 ............................................................................................................................... 01/27/17 8.9.1-1 ............................................................................................................................... 10/23/15 8.9.1-2 ............................................................................................................................... 10/23/15 8.9.2-1 ............................................................................................................................... 10/23/15 8.9.2-2 ............................................................................................................................... 10/23/15 EPL-6 April 24, 2017

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL REQUIREMENTS MANUAL EFFECTIVE PAGE LISTING Page Revision 8.9.2-3 ............................................................................................................................... 10/23/15 EPL-7 August 31, 2016

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL REQUIREMENTS MANUAL REVISION LISTING Revision Date Initial Issue, Revision 0 ..................................................................................................... 02/02/98 Revision 1 ......................................................................................................................... 10/01/98 Revision 2 ......................................................................................................................... 02/12/99 Revision 3 ......................................................................................................................... 03/18/99 Revision 4 ......................................................................................................................... 09/14/99 Revision 5 ......................................................................................................................... 10/24/99 Revision 6 ......................................................................................................................... 09/29/99 Revision 7 ......................................................................................................................... 12/09/99 Revision 8 ......................................................................................................................... 03/23/00 Revision 9 ......................................................................................................................... 06/02/00 Revision 10 ....................................................................................................................... 06/13/00 Revision 11 ....................................................................................................................... 06/15/00 Revision 12 ....................................................................................................................... 11/09/00 Revision 13 ....................................................................................................................... 01/04/01 Revision 14 ....................................................................................................................... 04/05/01 Revision 15 ....................................................................................................................... 07/11/01 Revision 16 ....................................................................................................................... 04/05/02 Revision 17 ....................................................................................................................... 03/27/02 Revision 18 ....................................................................................................................... 07/19/02 Revision 19 ....................................................................................................................... 07/25/02 Revision 20 ....................................................................................................................... 10/11/02 Revision 21 ....................................................................................................................... 03/06/03 Revision 22 ....................................................................................................................... 08/11/03 Revision 23 ....................................................................................................................... 09/14/03 Revision 24 ....................................................................................................................... 09/28/03 Revision 25 ....................................................................................................................... 10/31/03 Revision 26 ....................................................................................................................... 09/26/03 Revision 27 ....................................................................................................................... 09/26/03 Revision 28 ....................................................................................................................... 05/15/04 Revision 29 ....................................................................................................................... 10/13/04 Revision 30 ....................................................................................................................... 10/13/04 Revision 31 ....................................................................................................................... 04/22/05 Revision 32 ....................................................................................................................... 05/27/05 Revision 33 ....................................................................................................................... 06/20/05 Revision 34 ....................................................................................................................... 06/24/05 Revision 35 ....................................................................................................................... 10/12/05 Revision 36 ....................................................................................................................... 10/19/05 Revision 37 ....................................................................................................................... 01/20/06 Revision 38 ....................................................................................................................... 03/08/06 Revision 39 ....................................................................................................................... 03/17/06 Revision 40 ....................................................................................................................... 04/26/06 Revision 41 ....................................................................................................................... 07/25/06 Revision 42 ....................................................................................................................... 09/15/06 Revision 43 ....................................................................................................................... 10/17/06 Revision 44 ....................................................................................................................... 11/04/06 Revision 45 ....................................................................................................................... 05/18/09 Revision 46 ....................................................................................................................... 11/29/10 Revision 47 ....................................................................................................................... 09/27/12 Revision 48 ....................................................................................................................... 11/05/14 Revision 49 ....................................................................................................................... 10/23/15 EPL-8 October 23, 2015

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL REQUIREMENTS MANUAL REVISION LISTING Revision Date Revision 50 ....................................................................................................................... 11/25/15 Revision 51 ....................................................................................................................... 07/01/16 Revision 52 ....................................................................................................................... 08/29/16 Revision 53 ....................................................................................................................... 08/31/16 Revision 54 ....................................................................................................................... 09/27/16 Revision 55 ....................................................................................................................... 10/07/16 Revision 56 ....................................................................................................................... 04/04/16 Revision 57 ....................................................................................................................... 01/27/17 Revision 58 ....................................................................................................................... 04/24/17 Revision 59 ....................................................................................................................... 08/23/17 Revision 60 ....................................................................................................................... 06/08/18 Revision 61 ....................................................................................................................... 02/21/19 Revision 62 ....................................................................................................................... 07/11/19 EPL-9 July 11, 2019

SEQUOYAH UNITS 1 AND 2 TRM Table of Contents TECHNICAL REQUIREMENTS MANUAL Revision 53 August 31, 2016 Table of Contents SECTION TITLE PAGE

6.0 INTRODUCTION

7.0 USE AND APPLICATION 7.1 Definitions .................................................................................. 7.1-1 7.2 Logical Connectors .................................................................... 7.2-1 7.3 Restoration Times...................................................................... 7.3-1 7.4 Frequency .................................................................................. 7.4-1 7.5 Technical Requirements (TR) Applicability ................................ 7.5-1 7.6 Technical Requirements Verification (TRV) Applicability........... 7.6-1 8.1 REACTIVITY CONTROL SYSTEM 8.1.1 Boration - Operating .................................................................. 8.1.1-1 8.1.2 Boration - Shutdown .................................................................. 8.1.2-1 8.1.3 Position Indication System - Shutdown ..................................... 8.1.3-1 8.2 NOT USED 8.3 INSTRUMENTATION 8.3.1 Movable Incore Detectors Instrumentation ............................... 8.3.1-1 8.3.2 Seismic Monitoring Instrumentation........................................... 8.3.2-1 8.3.3 Meteorological Monitoring Instrumentation ................................ 8.3.3-1 8.3.4 Plant Calorimetic Measurement................................................. 8.3.4-1 8.3.5 Explosive Gas Monitoring System ............................................. 8.3.5-1 8.4 REACTOR COOLANT SYSTEM (RCS) 8.4.1 Chemistry................................................................................... 8.4.1-1 8.4.2 Pressurizer Temperature Limits................................................. 8.4.2-1 8.4.3 Reactor Coolant System Head Vents (RCSHV) ........................ 8.4.3-1 8.5 NOT USED 8.6 CONTAINMENT SYSTEM 8.6.1 Combustible Gas Control Hydrogen Monitors ........................... 8.6.1-1 8.6.2 Ice Bed Temperature Monitoring System .................................. 8.6.2-1 8.6.3 Inlet Door Position Monitoring System....................................... 8.6.3-1 8.6.4 Lower Containment Vent Coolers .............................................. 8.6.4-1 TOC- i

SEQUOYAH UNITS 1 AND 2 TRM Table of Contents TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 Table of Contents SECTION TITLE PAGE 8.7 PLANT SYSTEMS 8.7.1 Steam Generator Pressure/Temperature Limitation ................. 8.7.1-1 8.7.2 Flood Protection ....................................................................... 8.7.2-1 8.7.3 Snubbers .................................................................................. 8.7.3-1 8.7.4 Sealed Source Contamination .................................................. 8.7.4-1 8.7.5 Heating, Ventilating, and Air Conditioning (HVAC)

Maintenance Rule Equipment................................................... 8.7.5-1 8.7.6 Explosive Gas Mixtures ............................................................ 8.7.6-1 8.7.7 Liquid Holdup Tanks ................................................................. 8.7.7-1 8.7.8 Gas Decay Tanks ..................................................................... 8.7.8-1 8.7.9 Ventilation Filter Testing ........................................................... 8.7.9-1 8.8 ELECTRICAL SYSTEM 8.8.1 Containment Penetration Conductor Overcurrent Protective Devices .................................................................................... 8.8.1-1 8.8.2 Motor Operated Valves Thermal Overload Protection............... 8.8.2-1 8.8.3 Isolation Devices ...................................................................... 8.8.3-1 8.8.4 Emergency Diesel Generator Fuel Oil Storage Tanks .............. 8.8.4-1 8.9 REFUELING OPERATIONS 8.9.1 Communications....................................................................... 8.9.1-1 8.9.2 Manipulator Crane .................................................................... 8.9.2-1 TOC- ii

SEQUOYAH UNITS 1 AND 2 TRM 6.0 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015

6.0 INTRODUCTION

BACKGROUND The Technical Requirements Manual (TRM) is a Sequoyah Nuclear Plant (SQN) controlled document. The TRM contains requirements similar to the Technical Specifications, which are not required to be located in the Technical Specifications, because they do not meet the requirements of 10 CFR50.36. Although these requirements are excluded from Technical Specifications, they are still requirements placed upon plant operation due to regulatory issues.

The TRM provides one location for relocated items in a consistent format. The Technical Requirements are formatted in a manner consistent with NRC Inspection Manual Chapter 0326, Operability Determinations & Functionality Assessments for Conditions Adverse to Quality.

Although many of the terms defined in the Technical Specifications apply within the TRM, the TRM contains additional Definitions which are specific to the TRM and not defined in the Technical Specification Definitions.

REGULATORY STATUS/REQUIREMENTS The requirements in the TRM are part of the licensing basis for Sequoyah Units 1 and 2.

Violations of the TRM requirements should be documented in the corrective action program.

Deviations from the TRM will be screened for reportability in accordance with the corrective action program.

CHANGES TO THE TRM Design modifications, procedure changes, license amendments, etc. have the potential to affect the TRM. If this occurs, the initiating department must follow the administrative controls in NPG-SPP-03.12, "Technical Specifications/Licenses and Amendments." This process requires that the TRM's Technical Requirements be considered in a manner similar to the Technical Specifications when evaluating changes. Changes to the TRM will be reported, as a minimum, to the NRC at a frequency consistent with 10 CFR 50.71(e). Related 10 CFR 50.59 evaluations will be reported as part of the 10 CFR 50.59(d) report to the NRC.

6.0 - 1

SEQUOYAH UNITS 1 AND 2 TRM 7.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.0 USE AND APPLICATION 7.1 Definitions

NOTES-----------------------------------------------------------

1. Terms are defined in Section 1.1 of the Technical Specifications and are applicable throughout the Technical Requirements Manual (TRM) and Bases. Definitions specific to the TRM will be defined in this section.

2. The defined terms of this section and the Technical Specifications (TS) appear in capitalized type and are applicable throughout the TRM and the TRM Bases.

Term Definition CHANNEL FUNCTIONAL A CHANNEL FUNCTIONAL TEST consists of:

TEST

a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify FUNCTIONALITY including alarm and/or trip functions.

b. Bistable channels - the injection of a simulated signal into the sensor to verify FUNCTIONALITY including alarm and/or trip functions.

c. Digital channels - the injection of a simulated signal into the channel as close to the sensor input to the process racks as practicable to verify FUNCTIONALITY including alarm and/or trip functions.

FUNCTIONAL FUNCTIONALITY is an attribute of an structures, systems FUNCTIONALITY and components (SSCs) that is not controlled by TSs.

An SSC not controlled by TSs is FUNCTIONAL or has FUNCTIONALITY when it is capable of performing its function(s) as set forth in the current licensing basis (CLB).

These CLB function(s) may include the capability to perform a necessary and related support function for an SSCs controlled by TSs.

7.1 - 1

SEQUOYAH UNITS 1 AND 2 TRM 7.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.1 Definitions MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

Table 1.1-1 MODES REACTIVITY % RATED AVERAGE CONDITION THERMAL REACTOR COOLANT MODE TITLE (k eff ) POWER(a) TEMPERATURE

(°F) 1 Power Operation 0.99 >5 NA 2 Startup 0.99 5 NA 3 Hot Standby < 0.99 NA 350 4 Hot Shutdown(b) < 0.99 NA 350 > T avg > 200 5 Cold Shutdown(b) < 0.99 NA 200 6 Refueling(c) NA NA NA (a) Excluding decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensioned.

OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

7.1 - 2

SEQUOYAH UNITS 1 AND 2 TRM 7.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.1 Definitions TECHNICAL REQUIREMENT TECHNICAL REQUIREMENTS specify minimum (TR) requirements for ensuring safe operation of the unit. The Contingency Measures associated with a TR state Conditions that typically describe the ways in which the requirements of the TR can fail to be met. Specified with each stated condition are Contingency Measures and Restoration Time(s).

TECHNICAL REQUIREMENTS TECHNICAL REQUIREMENTS VERIFICATIONS are VERIFICATION (TRV) requirements relating to test, calibration, or inspection to assure that the necessary FUNCTIONALITY of systems and components is maintained, that facility operation will be maintained within the current licensing bases, and that the TECHNICAL REQUIREMENT (TR) will be met.

7.1 - 3

SEQUOYAH UNITS 1 AND 2 TRM 7.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.0 USE AND APPLICATION 7.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Requirements Manual (TRM) to discriminate between, and yet connect, discrete Conditions, Contingency Measures, Restoration Times, Verifications, and Frequencies. The only logical connectors that appear in the TRM are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Contingency Measures.

These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Contingency Measure.

The first level of logic is identified by the first digit of the number assigned to a Contingency Measure and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Contingency Measure). The successive levels of logic are identified by additional digits of the Contingency Measure number and by successive indentations of the logical connectors.

When logical connectors are used to state a Condition, Restoration Time, Verification, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Restoration Time, Verification, or Frequency.

EXAMPLES The following examples illustrate the use of logical connectors.

7.2 - 1

SEQUOYAH UNITS 1 AND 2 TRM 7.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 7.2-1 CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. TR not met. A.1 Verify . . .

AND A.2 Restore . . .

In this example the logical connector AND is used to indicate that when in Condition A, both Contingency Measures A.1 and A.2 must be completed.

7.2 - 2

SEQUOYAH UNITS 1 AND 2 TRM 7.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 7.2-2 CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. TR not met. A.1 Trip . . .

OR A.2.1 Verify . . .

AND A.2.2.1 Reduce OR A.2.2.2 Perform OR A.3 Align . . .

This example represents a more complicated use of logical connectors.

Contingency Measures A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Contingency Measures may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND.

Contingency Measure A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

7.2 - 3

SEQUOYAH UNITS 1 AND 2 TRM 7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.0 USE AND APPLICATION 7.3 Restoration Times PURPOSE The purpose of this section is to establish the Restoration Time convention and to provide guidance for its use.

BACKGROUND TECHNICAL REQUIREMENTS (TR) specify minimum requirements for ensuring safe operation of the unit. The CONTINGENCY MEASURES associated with a TR state Conditions that typically describe the ways in which the requirements of the TR can fail to be met. Specified with each stated Condition are Contingency Measure(s) and Restoration Time(s).

DESCRIPTION The Restoration Time is the amount of time allowed for completing a Contingency Measure. It is referenced to the time of discovery of a situation (e.g., nonfunctional equipment or variable not within limits) that requires entering a CONTINGENCY MEASURES Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the TR. Contingency Measures must be completed prior to the expiration of the specified Restoration Time. A CONTINGENCY MEASURE Condition remains in effect and the Contingency Measures apply until the Condition no longer exists or the unit is not within the TR Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single TR (multiple Conditions), the Contingency Measures for each Condition must be performed within the associated Restoration Time. When in multiple Conditions, separate Restoration Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be nonfunctional or not within limits, will not result in separate entry into the Condition, unless specifically stated. The Contingency Measures of the Condition continue to apply to each additional failure, with Restoration Times based on initial entry into the Condition.

However, when a subsequent train, subsystem, component, or variable expressed in the Condition is discovered to be nonfunctional or not within limits, the Restoration Time(s) may be extended. To apply this Restoration Time extension, two criteria must first be met. The subsequent nonfunctionality:

a. Must exist concurrent with the first nonfunctionality and 7.3 - 1

SEQUOYAH UNITS 1 AND 2 TRM 7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.3 Restoration Times DESCRIPTION (continued)

b. Must remain nonfunctional or not within limits after the first nonfunctionality is resolved.

The total Restoration Time allowed for completing a Contingency Measure to address the subsequent nonfunctionality shall be limited to the more restrictive of either:

a. The stated Restoration Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or

b. The stated Restoration Time as measured from discovery of the subsequent nonfunctionality.

The above Restoration Time extensions do not apply to those TRM Sections that have exceptions that allow completely separate re-entry into the Condition (for each train, subsystem, component, or variable expressed in the Condition) and separate tracking of Restoration Times based on this re-entry. These exceptions are stated in individual TRM Sections.

The above Restoration Time extension does not apply to a Restoration Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Restoration Time is referenced from a previous completion of the Contingency Measure versus the time of Condition entry) or as a time modified by the phrase "from discovery . . ."

EXAMPLES The following examples illustrate the use of Restoration Times with different types of Conditions and changing Conditions.

EXAMPLE 7.3-1 CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME B. Contingency B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Measure and associated AND Restoration Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 7.3 - 2

SEQUOYAH UNITS 1 AND 2 TRM 7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.3 Restoration Times EXAMPLES (continued)

Condition B has two Contingency Measures. Each Contingency Measure has its own separate Restoration Time. Each Restoration Time is referenced to the time that Condition B is entered.

The Contingency Measures of Condition B are to be in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND in MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months ) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , the time allowed for reaching MODE 5 is the next 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months because the total time allowed for reaching MODE 5 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 5 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

EXAMPLE 7.3-2 CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One pump Nonfunctional. A.1 Restore pump to 7 days FUNCTIONAL status.

B. Contingency Measure and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Restoration Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a pump is declared Nonfunctional, Condition A is entered. If the pump is not restored to FUNCTIONAL status within 7 days, Condition B is also entered and the Restoration Time clocks for Contingency Measures B.1 and B.2 start. If the Nonfunctional pump is restored to FUNCTIONAL status after Condition B is entered, Conditions A and B are exited, and therefore, the Contingency Measures of Condition B may be terminated.

7.3 - 3

SEQUOYAH UNITS 1 AND 2 TRM 7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.3 Restoration Times EXAMPLES (continued)

When a second pump is declared Nonfunctional while the first pump is still Nonfunctional, Condition A is not re-entered for the second pump. TR 7.5.3 is entered, since the CONTINGENCY MEASURES do not include a Condition for more than one Nonfunctional pump. The Restoration Time clock for Condition A does not stop after TR 7.5.3 is entered, but continues to be tracked from the time Condition A was initially entered.

While in TR 7.5.3, if one of the Nonfunctional pumps is restored to FUNCTIONAL status and the Restoration Time for Condition A has not expired, TR 7.5.3 may be exited and operation continued in accordance with Condition A.

While in TR 7.5.3, if one of the Nonfunctional pumps is restored to FUNCTIONAL status and the Restoration Time for Condition A has expired, TR 7.5.3 may be exited and operation continued in accordance with Condition B. The Restoration Time for Condition B is tracked from the time the Condition A Restoration Time expired.

On restoring one of the pumps to FUNCTIONAL status, the Condition A Restoration Time is not reset, but continues from the time the first pump was declared Nonfunctional. This Restoration Time may be extended if the pump restored to FUNCTIONAL status was the first Nonfunctional pump. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second pump being nonfunctional for > 7 days.

7.3 - 4

SEQUOYAH UNITS 1 AND 2 TRM 7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.3 Restoration Times EXAMPLES (continued)

EXAMPLE 7.3-3 CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One Function X train A.1 Restore Function X train to 7 days Nonfunctional. FUNCTIONAL status.

B. One Function Y train B.1 Restore Function Y train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Nonfunctional. FUNCTIONAL status.

C. One Function X train C.1 Restore Function X train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Nonfunctional. FUNCTIONAL status.

AND OR One Function Y train C.2 Restore Function Y train to Nonfunctional. FUNCTIONAL status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months When one Function X train and one Function Y train are Nonfunctional, Condition A and Condition B are concurrently applicable. The Restoration Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared nonfunctional and the Condition was entered. A separate Restoration Time is established for Condition C and tracked from the time the second train was declared Nonfunctional (i.e., the time the situation described in Condition C was discovered).

7.3 - 5

SEQUOYAH UNITS 1 AND 2 TRM 7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.3 Restoration Times EXAMPLES (continued)

If Contingency Measure C.2 is completed within the specified Restoration Time, Conditions B and C are exited. If the Restoration Time for Contingency Measure A.1 has not expired, operation may continue in accordance with Condition A. The remaining Restoration Time in Condition A is measured from the time the affected train was declared nonfunctional (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the TR.

However, doing so would be inconsistent with the basis of the Restoration Times.

Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the TR. These administrative controls shall ensure that the Restoration Times for those Conditions are not inappropriately extended.

IMMEDIATE When "Immediately" is used as a Restoration Time, The Contingency RESTORATION Measure should be pursued without delay and in a controlled manner.

TIME 7.3 - 6

SEQUOYAH UNITS 1 AND 2 TRM 7.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.0 USE AND APPLICATION 7.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each TECHNICAL REQUIREMENTS VERIFICATION (TRV) has a specified Frequency in which the TRV must be met in order to meet the associated TR. An understanding of the correct application of the specified Frequency is necessary for compliance with the TRV.

The "specified Frequency" is referred to throughout this section and each of the TR Section TRV Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each TRV as well as certain Notes in the Verification column that modify performance requirements.

Sometimes special situations dictate when the requirements of a TRV are to be met. They are "otherwise stated" conditions allowed by TRV 7.6.1.

They may be stated as clarifying Notes in the TRV, as part of the TRV or both.

Situations where a TRV could be required (i.e., its frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated TR is within its Applicability, represent potential conflicts. To avoid these conflicts, the TRV (i.e., the TRV or the Frequency) is stated such that it is only "required" when it can be and should be performed.

The use of "met" or "performed" in these instances conveys specific meanings. A TRV is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a TRV, even without a TRV specifically being "performed," constitutes a TRV not "met."

"Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria.

Some TRVs contain notes that modify the Frequency of performance or the conditions during which the acceptance criteria must be satisfied. For these TRVs, the MODE entry restrictions may not apply. Such a TRV is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated TR if any of the following three conditions are satisfied:

7.4 - 1

SEQUOYAH UNITS 1 AND 2 TRM 7.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.4 Frequency DESCRIPTION (continued)

a. The TRV is not required to be met in the MODE or other specified condition to be entered, or

b. The TRV is required to be met in the MODE or other specified condition to be entered, but has been performed within the specified Frequency (i.e., it is current) and is known not to be failed, or

c. The TRV is required to be met, but not performed, in the MODE or other specified condition to be entered, and is known not to be failed.

Examples 7.4-3 and 7.4-4 discuss these special situations.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the TR (TR not shown) is MODES 1, 2, and 3.

7.4 - 2

SEQUOYAH UNITS 1 AND 2 TRM 7.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.4 Frequency EXAMPLES (continued)

EXAMPLE 7.4-1 TECHNICAL REQUIREMENTS VERIFICATION VERIFICATION FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 7.4-1 contains the type of TRV most often encountered in the Technical Requirements Manual (TRM). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated TRV must be performed at least one time. Performance of the TRV initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the stated Frequency is allowed by TRV 7.6.2 for operational flexibility. The measurement of this interval continues at all times, even when the TRV is not required to be met per TRV 7.6.1 (such as when the equipment is nonfunctional, a variable is outside specified limits, or the unit is outside the Applicability of the TR).

If the interval specified by TRV 7.6.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the TR, and the performance of the TRV is not otherwise modified (refer to Example 7.4-3), then TRV 7.6.3 becomes applicable.

7.4 - 3

SEQUOYAH UNITS 1 AND 2 TRM 7.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.4 Frequency EXAMPLES (continued)

EXAMPLE 7.4-2 TECHNICAL REQUIREMENTS VERIFICATION VERIFICATION FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 7.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 7.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

< 25% RTP to 25% RTP, the TRV must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").

7.4 - 4

SEQUOYAH UNITS 1 AND 2 TRM 7.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.4 Frequency EXAMPLES (continued)

EXAMPLE 7.4-3 TECHNICAL REQUIREMENTS VERIFICATION VERIFICATION FREQUENCY

NOTE---------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP.

Perform channel adjustment. 7 days The interval continues, whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the TRV, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches 25% RTP to perform the TRV. The TRV is still considered to be performed within the "specified Frequency." Therefore, if the TRV were not performed within the 7 day (plus the extension allowed by TRV 7.6.2) interval, but operation was < 25% RTP, it would not constitute a failure of the TRV or failure to meet the TR.

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the TRV. If the TRV were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval (plus the extension allowed by TRV 7.6.2), there would then be a failure to perform a TRV within the specified Frequency.

7.4 - 5

SEQUOYAH UNITS 1 AND 2 TRM 7.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.4 Frequency EXAMPLES (continued)

EXAMPLE 7.4-4 TECHNICAL REQUIREMENTS VERIFICATION VERIFICATION FREQUENCY

NOTE---------------------------

Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 7.4-4 specifies that the requirements of this TRV do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this TRV continues at all times, as described in Example 7.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this TRV. Therefore, if the TRV were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by TRV 7.6.2), but the unit was not in MODE 1, there would be no failure of the TRV nor failure to meet the TR. Therefore, no violation occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1.

7.4 - 6

SEQUOYAH UNITS 1 AND 2 TRM 7.5 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.0 USE AND APPLICATION 7.5 TECHNICAL REQUIREMENT (TR) Applicability TR 7.5.1 TRs shall be met during the MODES or other specified conditions in the Applicability.

TR 7.5.2 Upon discovery of a failure to meet a TR, the Contingency Measures of the associated Conditions shall be met.

TR 7.5.3 When a TR is not met and the associated Contingency Measures are not satisfied (or an associated Contingency Measure is not provided), the equipment subject to the TR is in a nonconforming condition. In this situation, appropriate actions shall be taken as necessary to provide assurance of continued safe plant operations. In addition, a Condition Report shall be initiated and an assessment of reasonable assurance of safety shall be conducted. Items to be considered for this assessment include the following:

Availability of redundant or backup equipment;

Compensatory measures, including limited administrative controls;

Safety function and events protected against;

Probability of needing the safety function;

Conservatism and margins; and

Probabilistic Risk Assessment or Individual Plant Evaluation results that determine how operating the plant in the manner proposed will impact core damage frequency.

If this assessment concludes that safety is sufficiently assured, the facility may continue to operate while prompt corrective action is taken.

TR 7.5.4 When a TR is not met entry into a MODE or other specified condition in the Applicability shall only be made:

a. When the associated Contingency Measures to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing Nonfunctional systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this TR are stated in the individual TR; or

c. When an allowance is stated in the individual value, parameter, or other TR.

This TR shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with Contingency Measures or that are part of a shutdown of the unit.

7.5 - 1

SEQUOYAH UNITS 1 AND 2 TRM 7.5 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.5 TECHNICAL REQUIREMENT (TR) Applicability TR 7.5.5 Equipment removed from service or declared Nonfunctional to comply with Contingency Measures may be returned to service under administrative control solely to perform testing required to demonstrate its FUNCTIONALITY or the FUNCTIONALITY of other equipment. This is an exception to TR 7.5.2 for the system returned to service under administrative control to perform the testing required to demonstrate FUNCTIONALITY.

7.5 - 2

SEQUOYAH UNITS 1 AND 2 TRM 7.6 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 7.0 USE AND APPLICATION 7.6 TECHNICAL REQUIREMENTS VERIFICATION (TRV) Applicability TRV 7.6.1 TRVs shall be met during the MODES or other specified conditions in the Applicability for individual TRs, unless otherwise stated in the TRV. Failure to meet a TRV, whether such failure is experienced during the performance of the TRV or between performances of the TRV, shall be failure to meet the TR.

Failure to perform a TRV within the specified Frequency shall be failure to meet the TR. TRVs do not have to be performed on nonfunctional equipment or variables outside specified limits.

TRV 7.6.2 Each TRV shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified TRV interval.

TRV 7.6.3 When it is discovered that a TRV Frequency (including the 25% extension) has not been met, the equipment subject to the TRV is Nonfunctional.

7.6 - 1

SEQUOYAH UNITS 1 AND 2 TRM 8.1.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.1 REACTIVITY CONTROL SYSTEMS 8.1.1 Boration Systems - Operating TECHNICAL REQUIREMENT (TR)

TR 8.1.1 The Boration System shall be FUNCTIONAL consisting of at least two of the following three flow paths:

a. The flow path from a boric acid tank via a FUNCTIONAL boric acid transfer pump and a FUNCTIONAL charging pump to the Reactor Coolant System (RCS).

b. Two flow paths from the OPERABLE refueling water storage tank via two FUNCTIONAL charging pumps to the RCS.

NOTE---------------------------------------------------------------

In MODE 3, one charging pump may be made incapable of injecting to support transition into or from the Applicability of Technical Specification LCO 3.4.12, Low Temperature Overpressure Protection (LTOP) System, for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or until the temperature of all RCS cold legs exceeds LTOP arming temperature (350°F) specified in the Pressure and Temperature Limits Report (PTLR) plus 25°F, whichever comes first.

APPLICABILITY: MODES 1, 2, and 3.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A One required boron A.1 Restore the required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months injection flow path Nonfunctional flow path to Nonfunctional. FUNCTIONAL status.

B. Required Contingency B.1 Evaluate in accordance Immediately Measures and associated with TR 7.5.3.

Restoration Time of Condition A not met.

OR Two required boron injection flow paths Nonfunctional.

8.1.1-1

SEQUOYAH UNITS 1 AND 2 TRM 8.1.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.1.1.1 -----------------------------NOTE------------------------------------

Only required to be met if a boric acid tank is a required water source.

Verify the temperature of the boric acid tank area, and 7 days areas containing flow path components from the boric acid tanks to the blending tee is greater than or equal AND to 63°F.

Once within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after area temperature is less than 63°F AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter until area temperature is greater than or equal to 63°F.

8.1.1.2 -----------------------------NOTE------------------------------------

Only required to be met if a boric acid tank is a required water source.

Verify the boron concentration in the boric acid tank is 7 days in accordance with Figure 8.1.1-1.

8.1.1.3 -----------------------------NOTE------------------------------------

Only required to be met if a boric acid tank is a required water source.

Verify the borated water volume in the boric acid tank is 7 days in accordance with Figure 8.1.1-1.

8.1.1-2

SEQUOYAH UNITS 1 AND 2 TRM 8.1.1 TECHNICAL REQUIREMENTS MANUAL Revision 56 April 4, 2016 TECHNICAL REQUIREMENTS VERIFICATION (continued)

TRV VERIFICATION FREQUENCY 8.1.1.4 Verify each manual, power operated, or automatic 31 days valve in the boron injection flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

8.1.1.5 Verify each automatic valve in the boron injection flow 18 months path actuates to its correct position on a safety injection test signal.

8.1.1.6 Verify the flow path from the boric acid tanks via a boric 18 months acid transfer pump and a charging pump to the RCS delivers greater than or equal to 40 gpm.

8.1.1.7 Verify each charging pump develops a discharge In accordance with the pressure of greater than or equal to 2400 psig during Inservice Testing recirculation flow. Program 8.1.1-3

SEQUOYAH UNITS 1 AND 2 TRM 8.1.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TRM FIGURE 8.1.1-1 (Units 1 & 2)

BORIC ACID TANK LIMITS BASED ON RWST BORON CONCENTRATION 11000 REGION OF ACCEPTABLE OPERATION 10500 RWST = 2500 ppm B RWST = 2550 ppm B RWST = 2600 ppm B 10000 RWST = 2650 ppm B INDICATED BORIC ACID TANK VOLUME - GALLONS RWST = 2700 ppm B 9500 9000 6120 ppm (Minimum) 8500 6990 ppm (Maximum) 8000 7500 REGION OF UNACCEPTABLE OPERATION 7000 Indicated values include 1140 gal unusable volume and 800 gal for instrument error.

6500 6000 6100 6200 6300 6400 6500 6600 6700 6800 6900 7000 7100 BORIC ACID TANK CONCENTRATION - PPM BORON RWST Concentration 2500 PPM 2550 PPM 2600 PPM 2650 PPM 2700 PPM 8.1.1-4

SEQUOYAH UNITS 1 AND 2 TRM 8.1.1 TECHNICAL REQUIREMENTS MANUAL Revision 52 August 29, 2016A BASES 8.1.1 Boration Systems - Operating The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include 1) borated water sources, 2) charging pumps, 3) separate flow paths, 4) boric acid transfer pumps, and 5) offsite power supply or an emergency power supply from OPERABLE diesel generators.

With the RCS average temperature above 350°F, a minimum of two boron injection systems (involving two charging pumps,) are required to ensure single functional capability in the event an assumed failure renders one of the flow paths nonfunctional. The boration capability of either flow path is sufficient to provide a SHUTDOWN MARGIN (SDM) from expected operating conditions of 1.6% k/k after xenon decay and cooldown to 200°F. The maximum expected boration capability requirement occurs at near EOL from full power peak xenon conditions and requires borated water from a boric acid tank in accordance with Figure 8.1.1-1 and additional makeup water from either: (1) the common boric acid tank and/or batching, or (2) a minimum of 26,000 gallons of 2500 ppm borated water from the refueling water storage tank. With the refueling water storage tank as the only borated water source, a minimum of 57,000 gallons of 2500 ppm borated water is required.

TR 8.1.1 is modified by a Note. Operation in MODE 3 with one charging pump made incapable of injecting, in order to facilitate entry into or exit from the Applicability of Technical Specification LCO 3.4.12, Low Temperature Overpressure Protection (LTOP) System, is necessary for plants with an LTOP arming temperature at or near the MODE 3 boundary temperature of 350°F. Technical Specifications LCO 3.4.12 requires that certain pumps be rendered incapable of injecting at and below the LTOP arming temperature. When this temperature is at or near the MODE 3 boundary temperature, time is needed to make a pump incapable of injecting prior to entering the LTOP Applicability, and provide time to restore the nonfunctional pump to FUNCTIONAL status on exiting the LTOP Applicability.

The boric acid tanks, pumps, valves, and piping contain a boric acid solution concentration of between 3.5% and 4.0% by weight. To ensure that the boric acid remains in solution, the air temperature is monitored in strategic locations. By ensuring the air temperature remains at 63°F or above, a 5°F margin is provided to ensure the boron will not precipitate out. To provide operational flexibility, if the area temperature should fall below the required value, the solution temperature (as determined by the pipe or tank wall temperature) will be monitored at an increased frequency to compensate for the lack of solution temperature alarm in the main control room.

8.1.1-5

SEQUOYAH UNITS 1 AND 2 TRM 8.1.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.1 REACTIVITY CONTROL SYSTEMS 8.1.2 Boration Systems - Shutdown TECHNICAL REQUIREMENT (TR)

TR 8.1.2 The Boration System shall be FUNCTIONAL consisting of the following:

a. A flow path from a boric acid tank via a FUNCTIONAL boric acid transfer pump and a FUNCTIONAL charging pump to the Reactor Coolant System (RCS), OR

b. A flow path from the FUNCTIONAL refueling water storage tank (RWST) via a FUNCTIONAL charging pump to the RCS.

APPLICABILITY: MODES 4, 5, and 6.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. -------------NOTE----------- A.1 Suspend operations that Immediately Only applicable in MODE would cause introduction of 4 and 5. coolant into the RCS with

boron concentration less than required to meet the Required boron injection SDM of Technical flow path Nonfunctional. Specification 3.1.1.

AND A.2 Restore the Nonfunctional Immediately flow path to FUNCTIONAL status.

B. -------------NOTE----------- B.1 Suspend CORE Immediately Only applicable in ALTERATIONS.

MODE 6.

AND Required boron injection B.2 Suspend operations that Immediately flow path Nonfunctional. would cause introduction of coolant into the RCS with boron concentration less than required to meet Technical Specification 3.9.1.

8.1.2-1

SEQUOYAH UNITS 1 AND 2 TRM 8.1.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 CONDITION CONTINGENCY MEASURES RESTORATION TIME C. Required Contingency C.1 Evaluate in accordance Immediately Measures and with TR 7.5.3.

associated Restoration Time of Condition A or B not met.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.1.2.1 -----------------------------NOTE------------------------------------

Only required to be met if the RWST is the required water source.

Verify the temperature of the RWST solution is greater 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months than or equal to 60°F.

8.1.2.2 -----------------------------NOTE------------------------------------

Only required to be met if a boric acid tank is the required water source.

Verify the temperature of the boric acid tank area, and 7 days areas containing flow path components from the boric acid tanks to the blending tee is greater than or equal AND to 63°F.

Once within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after area temperature is less than 63°F AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter until area temperature is greater than or equal to 63°F.

8.1.2-2

SEQUOYAH UNITS 1 AND 2 TRM 8.1.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TRV VERIFICATION FREQUENCY 8.1.2.3 -----------------------------NOTE------------------------------------

Only required to be met if a boric acid tank is the required water source.

Verify the boron concentration in the boric acid tank is 7 days greater than 6120 ppm and less than 6990 ppm.

8.1.2.4 -----------------------------NOTE------------------------------------

Only required to be met if a boric acid tank is the required water source.

Verify the borated water volume in the boric acid tank is 7 days greater than or equal to 6400 gallons.

8.1.2.5 -----------------------------NOTE------------------------------------

Only required to be met if the RWST is the required water source.

Verify the RWST boron concentration is greater than or 7 days equal to 2500 ppm.

8.1.2.6 -----------------------------NOTE------------------------------------

Only required to be met if the RWST is the required water source.

Verify the borated water volume in the RWST is greater 7 days than or equal to 55,000 gallons.

8.1.2.7 Verify each manual, power operated, or automatic 31 days valve in the required boron injection flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

8.1.2-3

SEQUOYAH UNITS 1 AND 2 TRM 8.1.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TRV VERIFICATION FREQUENCY 8.1.2.8 Verify the charging pump develops a discharge In accordance with the pressure of greater than or equal to 2400 psig during Inservice Testing recirculation flow. Program 8.1.2-4

SEQUOYAH UNITS 1 AND 2 TRM 8.1.2 TECHNICAL REQUIREMENTS MANUAL Revision 52 August 29, 2016 8.1 REACTIVITY CONTROL SYSTEMS 8.1.2 Boration Systems - Shutdown BASES The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include 1) borated water sources, 2) charging pumps, 3) separate flow paths, 4) boric acid transfer pumps, and

5) offsite power supply or an emergency power supply from OPERABLE diesel generators.

The boric acid tanks, pumps, valves, and piping contain a boric acid solution concentration of between 3.5% and 4.0% by weight. To ensure that the boric acid remains in solution, the air temperature is monitored in strategic locations. By ensuring the air temperature remains at 63°F or above, a 5°F margin is provided to ensure the boron will not precipitate out. To provide operational flexibility, if the area temperature should fall below the required value, the solution temperature (as determined by the pipe or tank wall temperature) will be monitored at an increased frequency to compensate for the lack of solution temperature alarm in the main control room.

With the RCS temperature below 350°F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and operations involving positive reactivity additions that could result in loss of required shutdown margin (SDM) (MODE 4 or 5) or boron concentration (MODE 6) in the event the single injection system becomes nonfunctional. Suspending positive reactivity additions that could result in failure to meet minimum SDM or boron concentration limit is required to assure continued safe operation.

Introduction of coolant inventory must be from sources that have a boron concentration greater than or equal to that required in the RCS for minimum SDM or refueling boron concentration.

This may result in an overall reduction in RCS boron concentration but provides acceptable margin to maintaining subcritical operation. Introduction of temperature changes including temperature increases when operating with positive MTC must be evaluated to ensure they do not result in a loss of required SDM.

The boron capability required below 350°F is sufficient to provide a SDM of 1.6% k/k after xenon decay and cooldown from 350°F to 200°F, and a SDM of 1% k/k after xenon decay and cooldown from 200°F to 140°F. This condition requires either 6400 gallons of 6120 ppm borated water from the boric acid storage tanks or 13,400 gallons of 2500 ppm borated water from the refueling water storage tank (RWST).

The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics. The 6400 gallon limit in the boric acid tank for Modes 4, 5, and 6 is based on 4,431 gallons required for SDM, 1,140 gallons for the unusable volume in the heel of the tank, 800 gallons for instrument error, and an additional 29 gallons due to rounding up. The 55,000 gallon limit in the refueling water storage tank for modes 4, 5, and 6 is based upon 22,182 gallons that is undetectable due to lower tap location, 19,197 gallons for instrument error, 13,400 gallons required for SDM, and an additional 221 gallons due to rounding up.

8.1.2-5

SEQUOYAH UNITS 1 AND 2 TRM 8.1.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES 8.1.2 Boration Systems - Shutdown (continued)

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.5 and 9.5 for the solution recirculated within containment after a loss of coolant accident. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

The FUNCTIONALITY of one boron injection system during refueling ensures that this system is available for reactivity control while in MODE 6.

8.1.2-6

SEQUOYAH UNITS 1 AND 2 TRM 8.1.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.1 REACTIVITY CONTROL SYSTEMS 8.1.3 Position Indication System - Shutdown TECHNICAL REQUIREMENT (TR)

TR 8.1.3 The group demand position indicator shall be FUNCTIONAL and capable of determining within +/- 2 steps, the demand position for each shutdown or control rod not fully inserted.

APPLICABILITY: MODES 3, 4 and 5 with the reactor trip breakers in the closed position.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. Less than required A.1 Open the reactor trip Immediately group demand position breakers.

indicator(s)

FUNCTIONAL.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.1.3.1 Verify each required group demand position indicator(s) 31 days is FUNCTIONAL by movement of the associated control rod at least 10 steps in any one direction.

8.1.3-1

SEQUOYAH UNITS 1 AND 2 TRM 8.1.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.1 REACTIVITY CONTROL SYSTEMS 8.1.3 Position Indication System - Shutdown BASES BACKGROUND Instrumentation to monitor variables and systems over their operating ranges during normal operation, anticipated operational occurrences, and accident conditions must be FUNCTIONAL. TR 8.1.3 is required to ensure FUNCTIONALITY of the control rod group demand position indicators to determine control rod positions of rod groups not fully inserted with the Reactor Trip System breakers in the closed position.

The OPERABILITY, including group demand position indication, of the shutdown and control rods are initial assumptions in all safety analyses that assume rod insertion upon reactor trip. Rod position indication is required to assess control and shutdown rod OPERABILITY and misalignment. These safety analyses are not applicable to shutdown conditions. Rod Drop Times and other tests requiring control rod OPERABILITY, however, are performed at shutdown. Additionally, positive reactivity addition due to rod withdrawal must be compensated for by boron addition. Rod positions are monitored and controlled when withdrawn during shutdown conditions to ensure SHUTDOWN MARGIN is maintained. The axial position of shutdown rods and control rods is determined by the group demand position indicators.

The group demand position indicators count the pulses generated in the Rod Control System to provide a readout of the demand bank position.

There is one step counter for each group of rods. Individual rods in a group all receive the same signal to move and should, therefore, all be at the same position indicated by the group step counter for that group. The group demand position indicators are considered highly precise (+/- 1 step or +/- 5/8 inch). If a rod does not move 1 step for each demand pulse, the step counter will still count the pulse and incorrectly reflect the position of the rod.

APPLICABLE The Rod Position Indication System is a system which provides SAFETY information to the operator which could be used to initiate operator action.

ANALYSES However, no design basis accident (DBA) or transient assumes operator action to manually trip the reactor, or to take some alternative action if an automatic reactor trip does not occur. Hence, the shutdown and control rods, including position indication, are not assumed to be FUNCTIONAL to mitigate the consequences of a DBA or transient during shutdown conditions. Positive reactivity addition due to withdrawal of control rods is compensated for by boron concentration.

8.1.3-2

SEQUOYAH UNITS 1 AND 2 TRM 8.1.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES TECHNICAL TR 8.1.3 specifies that the group demand position indicators be REQUIREMENT FUNCTIONAL and capable of determining within +/- 2 steps the demand position for each shutdown or control rod not fully inserted. For the control rod position indicators to be FUNCTIONAL requires meeting the verification requirement of the TR. This requirement provides adequate assurance that control rod position indication during shutdown conditions and rod testing is accurate, and that design assumptions are not challenged. FUNCTIONALITY of the required position indicators ensures that nonfuctional, misaligned, or mispositioned control rods can be detected.

APPLICABILITY TR 8.1.3 covers only the requirements on Rod Position Indication during MODES 3, 4, and 5 with the reactor trip breakers closed. Rod Position Indication during MODES 1 and 2 are covered by Technical Specification 3.1.7. In MODE 6 and in MODES 3, 4, and 5 with trip breakers open or all rods on the bottom, Rod Position Indication is not required to be FUNCTIONAL. Rod Position Indication FUNCTIONALITY is required only when rods are withdrawn from fully inserted.

CONTINGENCY A.1 MEASURES With one or more group demand position indicators nonfunctional, the plant must be placed in a condition where the demand position indicators are not required. This is accomplished by opening the reactor trip breakers immediately.

The immediate Restoration Time is consistent with the required time for Contingency Measures to be pursued without delay and in a controlled manner.

TECHNICAL TRV 8.1.3.1 REQUIREMENTS VERIFICATION Exercising rods at a Frequency of 31 days allows the operator to determine that all withdrawn rods, including the group step counter demand position indicator, continue to be FUNCTIONAL. A movement of 10 steps is adequate to demonstrate motion and verify a corresponding step change in the group step counter demand position indicator. The 31-day Frequency takes into consideration other information available to the operator in the control room and the remote likelihood that rods would be withdrawn from fully inserted for extended periods of time during shutdown conditions.

8.1.3-3

SEQUOYAH UNITS 1 AND 2 TRM 8.3.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.3 INSTRUMENTATION 8.3.1 Movable Incore Detectors TECHNICAL REQUIREMENT (TR)

TR 8.3.1 The Movable Incore Detection System shall be FUNCTIONAL with:

a. 75% of the detector thimbles,

b. 2 detector thimbles per core quadrant, and

c. Sufficient movable detectors, drive, and readout equipment to map these thimbles.

APPLICABILITY: When the Movable Incore Detection System is used for:

a. Recailbration of the excore neutron flux detection system,

b. Monitoring the QUADRANT POWER TILT RATIO, or N

c. Measurement of F and F (Z).

H Q CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A Less than the specified A.1 Do not use the Movable Immediately number of incore Incore Monitoring System detectors for the above applicable FUNCTIONAL. monitoring or calibrations.

AND A.2 Evaluate in accordance Immediately with TR 7.5.3.

8.3.1-1

SEQUOYAH UNITS 1 AND 2 TRM 8.3.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.3.1.1 Verify the normalization of each required detector Prior to use for the output. following:

Recalibration of the excore neutron flux detection system, OR Monitoring the QUADRANT POWER TILT RATIO, OR Measurement of N

F and F (Z)

H Q 8.3.1-2

SEQUOYAH UNITS 1 AND 2 TRM 8.3.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.3 INSTRUMENTATION 8.3.1 Movable Incore Detectors BASES BACKGROUND The FUNCTIONALITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The FUNCTIONALITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.

For the purpose of measuring F Q (X,Y,Z) or F H (X,Y) a full incore flux map is used. Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.

8.3.1-3

SEQUOYAH UNITS 1 AND 2 TRM 8.3.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.3 INSTRUMENTATION 8.3.2 Seismic Monitoring Instrumentation TECHNICAL REQUIREMENT (TR)

TR 8.3.2 The seismic monitoring instrumentation in Table 8.3.2-1 shall be FUNCTIONAL.

APPLICABILITY: At all times.

CONTINGENCY MEASURES

NOTE------------------------------------------------------------------

Separate Condition entry is allowed for each instrument.

CONDITION CONTINGENCY MEASURES RESTORATION TIME A. -----------NOTE------------- A.1 Retrieve and analyze data 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Contingency Measure from actuated instrument(s)

A.4 shall be completed and 0-XT-52-75B to whenever this Condition determine the magnitude of is entered. the vibratory ground motion.

AND One or more seismic monitoring instrument(s) A.2 Perform plant walkdown of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Nonfunctional due to accessible plant areas.

being actuated during a seismic event. AND A.3 Restore instrument(s) to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months FUNCTIONAL status.

AND A.4 Perform TRV 8.3.2.3. 10 days B. 0-XT-52-75B or panel B.1 Restore instrument to 30 days 0-R-113 Nonfunctional FUNCTIONAL status.

for reasons other than Condition A.

8.3.2-1

SEQUOYAH UNITS 1 AND 2 TRM 8.3.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 CONDITION CONTINGENCY MEASURES RESTORATION TIME C. One or more seismic C.1 Restore instrument to 60 days monitoring instrument(s) FUNCTIONAL status.

Nonfunctional for other than Condition A or B.

D. Required Contingency D.1 Evaluate in accordance with Immediately Measures and TR 7.5.3.

associated Restoration Time of Condition A, B, or C not met.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.3.2.1 -----------------------------NOTE------------------------------------

CHANNEL CHECK does not include acceleration trigger.

Perform CHANNEL CHECK. 31 days 8.3.2.2 -----------------------------NOTE-------------------------------------

CHANNEL FUNCTIONAL TEST does not include setpoint verification.

Perform CHANNEL FUNCTIONAL TEST. 184 days 8.3.2.3 -----------------------------NOTE-------------------------------------

CHANNEL CALIBRATION includes acceleration trigger.

Perform CHANNEL CALIBRATION. Within 10 days of a seismic actuation AND 18 months 8.3.2-2

SEQUOYAH UNITS 1 AND 2 TRM 8.3.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 Table 8.3.2-1 Seismic Monitoring Instrumentation (Page 1 of 1)

INSTRUMENTS MINIMUM MEASUREMENT AND INSTRUMENTS RANGE SENSOR LOCATIONS FUNCTIONAL Triaxial Time History Accelerographs

1. 0-XT-52-75B, Annulus, Elev. 680** 1* 0 - 1.0g

2. 0-XT-52-75A, Containment, Elev. 734** 1 0 - 1.0g

3. 0-XR-52-77, Diesel Building, Elev. 722 1 0 - 2.0g

4. 0-XR-52-92, Auxiliary Building, Elev. 734 1 0 - 2.0g

With reactor control room indication.

- With associated acceleration triggers and indication on 0-XR-52-75 and recording and analyzing components on 0-R-113.

8.3.2-3

SEQUOYAH UNITS 1 AND 2 TRM 8.3.2 TECHNICAL REQUIREMENTS MANUAL Revision 54 September 27, 2016 8.3 INSTRUMENTATION 8.3.2 Seismic Monitoring Instrumentation BASES BACKGROUND The seismic instrumentation is made up of several instruments such as accelerometers, accelerographs, recorders, etc. These instruments are placed in several appropriate locations throughout the plant in order to provide 1) data on the seismic input to containment, 2) data on the frequency, amplitude and phase relationship of the seismic response of the containment structure, and 3) data on the seismic input to and response of other Seismic Category I structures (Ref 1).

This instrumentation is consistent with the intent of Regulatory Guide 1.12, Revision 1.

The original seismic instrumentation was replaced with state of the art digital instrumentation in order to facilitate application of EPRI OBE (i.e.,

1/2 safe shutdown earthquake (SSE) for Sequoyah) Exceedance Criteria, as delineated in References 2 and 5. The replacement instrumentation is capable of recording a seismic event and performing appropriate analyses of the recorded data to provide a timely basis for determining whether a potentially damaging operating basis earthquake (OBE) exceedance has occurred. This information must be evaluated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after an event and a walkdown of accessible plant features must be accomplished within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after an event.

The determination as to whether an 1/2 SSE Exceedance has occurred is made by comparing the calculated spectra for the event with the applicable site design basis spectra, which is defined at top of rock for Sequoyah (Ref. 4). Therefore, the exceedance determination for SQN will be made using uncorrected event data from accelerometer 0-XT 75B in the containment annulus. The use of uncorrected event data is known to be conservative because of the inherent response characteristics of the accelerometer. Data from this instrument is recorded at the top of the containment foundation, which is rock-supported. The recorder for this accelerometer is located in panel 0-R-113. As noted above, this accelerometer and recorder are the key components used to detect and record the event in order to make a shutdown decision. The recorder can function for minimum 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from internal rechargeable batteries, which are constantly recharged from 120 VAC Instrument Power. Panel 0-R-113 also contains the computer, LCD display, and printer used to calculate and display the spectral content of the event, and the alarm panel used to annunciate in the control room.

These devices are also powered by 120 VAC Instrument Power, but have no backup battery power. Power to these devices may be manually restored in the unlikely event of loss of AC power.

8.3.2-4

SEQUOYAH UNITS 1 AND 2 TRM 8.3.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES APPLICABLE The FUNCTIONALITY of the seismic instrumentation ensures that SAFETY sufficient capability is available to promptly determine the magnitude of a ANALYSES seismic event and to determine the impact on those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the unit to determine if plant equipment inspection is required pursuant to Appendix A of 10 CFR 100 prior to restart. Seismic risks which appear as dominant sequences in probabilistic risk assessment (PRAs) occur for very severe earthquakes with magnitudes which are a factor of two or three above the Safe Shutdown Earthquake and Design Basis Earthquake. The Seismic Instrumentation System was not designed to function or to provide comparative information for such severe earthquakes. This instrumentation is more pertinent to determining the need to shut down following a seismic event and the ability to restart the plant after seismic events which are not risk contributors, and is therefore not of prime importance in risk dominant sequences (Ref. 2).

TECHNICAL The seismic monitoring instrumentation shown in Table 8.3.2-1 shall be REQUIREMENT FUNCTIONAL. This requirement ensures that an assessment can be made of the effects on the plant of earthquakes which may occur that exceed the design basis spectra for the Operating Basis Earthquake (Ref. 4).

APPLICABILITY Since the possibility of earthquakes is not MODE dependent, FUNCTIONALITY of the seismic instrumentation is required at all times.

CONTINGENCY The determination as to whether an OBE exceedance has occurred is MEASURES made by comparing the calculated spectra for the event with the applicable design basis spectra for that building and location. For Sequoyah, this determination is to be made considering the data from instruments located on the containment foundation. Therefore, the exceedance determination for Sequoyah will be made using event data from 0-XT-52-75B in the containment annulus. Data from this instrument is recorded at panel 0-R-113, which also contains the computer used to calculate the spectral content and the alarm panel used to annunciate in the control room. These devices are the key components used to detect the event and make a shutdown determination.

8.3.2-5

SEQUOYAH UNITS 1 AND 2 TRM 8.3.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES CONTINGENCY MEASURES (continued)

A.1, A.2, A.3, and A.4 When one or more seismic monitoring instruments actuate during a seismic event with greater than or equal to 0.01g ground acceleration, the data retrieved from the actuated instruments must be analyzed to determine the magnitude of the vibratory ground motion.

The replacement digital instrumentation provides the capability to analyze the event data onsite and generate event spectra to be used in determining whether an 1/2 SSE exceedance has occurred.

References 2 and 5 direct that this evaluation should occur within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the event. Reference 5 also requires performance of a limited scope walkdown to determine the extent of actual damage within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following the event. The information provided by this walkdown and the spectral analysis are to be used in making a determination as to whether to proceed with plant shutdown, if a shutdown has not already occurred.

Each actuated monitoring instrument must be restored to FUNCTIONAL status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Within 10 days of the actuation, a CHANNEL CALIBRATION must be performed on each actuated monitoring instrument. The completion time of 10 days to perform CHANNEL CALIBRATION is reasonable and is based on engineering judgment.

Subsequent analysis must then be performed using data from the remaining seismic monitoring instruments to evaluate the plant response in comparison with previously generated design basis spectra at the locations of those instruments.

B.1 With accelerometer 0-XT-52-75B or panel 0-R-113 Nonfunctional, 30 days are allowed to restore the instrument(s) to FUNCTIONAL status.

C.1 With one or more of the remaining seismic instruments in Table 8.3.2-1 Nonfunctional, 60 days are allowed to restore the instrument(s) to FUNCTIONAL status. A longer period of nonfunctionality is allowed for these instruments since they are used only for evaluating plant condition following an event and not for input to the shutdown decision.

8.3.2-6

SEQUOYAH UNITS 1 AND 2 TRM 8.3.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES CONTINGNECY MEASURES (continued)

D.1 If Condition A, B or C is not met, then the associated Nonfunctional instrument(s) are evaluated per TR 7.5.3 and a service request is generated in accordance with the Corrective Action Program.

TECHNICAL TRV 8.3.2.1 REQUIREMENTS VERIFICATION A CHANNEL CHECK on seismic instrumentation once every 31 days ensues that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or of even something more serious.

CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying that the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

The Verification Frequency of 31 days is based on operating experience related to channel FUNCTIONALITY and drift, which demonstrates that failure of more than one channel of a given function in any 31 day interval is a rare event.

TRV 8.3.2.1 is modified by a Note stating that this test does not include the acceleration trigger.

TRV 8.3.2.2 A CHANNEL FUNCTIONAL TEST is to be performed on each required channel to ensure the entire channel will perform the intended function. A CHANNEL FUNCTIONAL TEST is the comparison of the response of the instrumentation, including all components of the instrument except the sensor, to a known signal. The Verification Frequency of 184 days is based upon the known reliability of the monitoring instrumentation and has been shown to be acceptable through operating experience.

TRV 8.3.2.2 is modified by a Note stating that this test does not include setpoint verification.

8.3.2-7

SEQUOYAH UNITS 1 AND 2 TRM 8.3.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION (continued)

TRV 8.3.2.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor by comparing the response of the instrument to a known input on the sensor. This test verifies the capability of the seismic instrumentation to correctly determine the magnitude of a seismic event and evaluate the response of those features important to safety. The Verification Frequency of 18 months is based upon operating experience and consistency with the typical industry refueling cycle.

TRV 8.3.2.3 is modified by a Note stating that this test does include the acceleration trigger.

8.3.2-8

SEQUOYAH UNITS 1 AND 2 TRM 8.3.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES REFERENCES 1. Regulatory Guide 1.12, "Instrumentation for Earthquakes,"

Revision 1, April 1974.

2. EPRI NP-5930, July 1988, "A Criterion for Determining Exceedance of the Operating Basis Earthquake."

3. EPRI TR-104239, June 1994, "Seismic Instrumentation in Nuclear Power Plants for Response to OBE Exceedance: Guideline for Implementation."

4. Sequoyah UFSAR, Sections 2.5 and 3.7.1.

5. EPRI NP-6695, December 1989, "Guidelines for Nuclear Plant Response to an Earthquake."

6. 10 CFR 100, Appendix A.

8.3.2-9

SEQUOYAH UNITS 1 AND 2 TRM 8.3.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.3 INSTRUMENTATION 8.3.3 Meteorological Monitoring Instrumentation TECHNICAL REQUIREMENT (TR)

TR 8.3.3 The meteorological monitoring instrumentation channels for each function shown in Table 8.3.3-1 shall be FUNCTIONAL.

APPLICABILITY: At all times.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. With less than the A.1 Restore channel(s) to Immediately required FUNCTIONAL FUNCTIONAL status.

meteorological monitoring AND instrumentation channels available. A.2 Evaluate in accordance with Immediately TR 7.5.3.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.3.3.1 Perform CHANNEL CHECK for each required channel. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 8.3.3.2 Perform CHANNEL CALIBRATION for each required 184 days channel.

8.3.3-1

SEQUOYAH UNITS 1 AND 2 TRM 8.3.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 Table 8.3.3-1 Meteorological Monitoring Instrumentation FUNCTION LOCATION REQUIRED (Nominal Elev.) CHANNELS

1. Wind Speed

a. Channel 1 780 MSL Any two channels of the three Wind

b. Channel 2 897 MSL Speed Channels

c. Channel 3 1047 MSL

2. Wind Direction

a. Channel 1 780 MSL Any two channels

b. Channel 2 897 MSL of the three Wind Direction Channels

c. Channel 3 1047 MSL

3. Air Temperature - Delta T

a. Channel 1 780 to 897 MSL Any channel of the three Air

b. Channel 2 780 to 1047 MSL Temperature -

c. Channel 3 897 to 1047 MSL Delta T Channels 8.3.3-2

SEQUOYAH UNITS 1 AND 2 TRM 8.3.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.3 INSTRUMENTATION 8.3.3 Meteorological Instrumentation BASES BACKGROUND The FUNCTIONALITY of the meteorological monitoring instrumentation channels ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.

8.3.3-3

SEQUOYAH UNITS 1 AND 2 TRM 8.3.4 TECHNICAL REQUIREMENTS MANUAL Revision 50 November 25, 2015 8.3 INSTRUMENTATION 8.3.4 Plant Calorimetric Measurement TECHNICAL REQUIREMENT (TR)

TR 8.3.4 Leading Edge Flow Meter (LEFM) shall be FUNCTIONAL for the performance of Technical Specification SR 3.3.1.2.

APPLICABILITY: MODE 1 > 15% RTP CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. With the LEFM A.1 Restore LEFM to Prior to the Nonfunctional. FUNCTIONAL status. performance of Technical Specification AND SR 3.3.1.2 A.2 Refer to COLR for AFD and Immediately control rod insertion limits.

B. -----------NOTE------------- B.1 Reduce thermal power to Immediately Contingency Measure 98.7% RTP.

B.4 shall be completed whenever this Condition AND is entered.

B.2 Refer to COLR for AFD and Immediately control rod insertion limits.

Required Contingency Measures and AND associated Restoration Time of Condition A not B.3 Perform Technical Immediately met. Specification SR 3.3.1.2 using alternate method.

AND B.4 Perform Technical Prior to raising Specification SR 3.3.1.2 THERMAL POWER using the FUNCTIONAL > 98.7% RTP LEFM.

8.3.4-1

SEQUOYAH UNITS 1 AND 2 TRM 8.3.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.3.4.1 Verify LEFM Normal/Fail status indication is not in the Prior to the Fail status and feedwater temperature is 250°F. performance of Technical Specification SR 3.3.1.2 8.3.4-2

SEQUOYAH UNITS 1 AND 2 TRM 8.3.4 TECHNICAL REQUIREMENTS MANUAL Revision 59 August 23, 2017 8.3 INSTRUMENTATION 8.3.4 Plant Calorimetric Measurement BASES BACKGROUND The predominant contribution to the secondary plant calorimetric measurement uncertainty is the uncertainty associated with the feedwater flow measurement. Traditionally, a differential pressure (P) transmitter across a venturi in each main feedwater line has been used to provide the feedwater flow. However, the venturis are subject to fouling and the uncertainty associated with the flow derived from the P indication can be large and increase as the flow deviates from the "optimum" conditions for which the P transmitter was calibrated.

More recently, Leading Edge Flow Meters (LEFM) have been used to provide the feedwater flow input to the secondary plant calorimetric measurement. The uncertainty associated with the LEFM is relatively small and is independent of the actual feedwater flow.

Most of the original safety analyses supporting plant operation (including loss of coolant accident analyses required by 10 CFR 50 Appendix K) were performed at a maximum power level of 3411 MWt plus an allowance for the secondary plant calorimetric uncertainty assumed to be 2% above RATED THERMAL POWER. Hence, it is possible to support operation at a higher power level while remaining within the original analyses.

The RATED THERMAL POWER (RTP) for Units 1 and 2 is 3455 MWt which represents the increase of 1.3% RTP from the originally licensed value of 3411 MWt. This uprate is based on reduced uncertainties associated with the secondary plant calorimetric measurement that is attained through the use of the LEFM Check. Many of the accident analyses are performed at 102% of 3411 MWt, or 3479 MWt, where the 2% RTP is an allowance for the uncertainty associated with the power calorimetric measurement. With the LEFM Check, the power calorimetric measurement uncertainty is less than 0.7% RTP. Without performing new Appendix K accident analyses, the LEFM Check can be used to allow the plant to be operated at a redefined 100% RTP of 3455 MWt.

However, this allowance is predicated on the availability of the LEFM Check for performance of the calorimetric measurement. When the LEFM Check is unavailable, the uncertainties associated with the feedwater venturi-based measurement (2% RTP) must be used to ensure compliance with the safety analyses value of the core power of 3479 MWt.

Technical Specification (TS) Surveillance Requirement (SR) 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance 8.3.4-3

SEQUOYAH UNITS 1 AND 2 TRM 8.3.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES BACKGROUND (continued) comparison requires the performance of a comparison of the results of the calorimetric heat balance calculation to Nuclear Instrumentation System (NIS) channel output. The TS SR requires that the NIS channels be adjusted if the absolute difference is greater than 2% RTP.

TS SR 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance comparison is required to be performed every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (daily).

At that time, the NIS indication must be normalized to indicate within at least +/- 2% RTP of the calorimetric measurement. The plant may then be run for the next 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period using this normalized NIS indication, such that the calorimetric power does not exceed 100% RTP. Although the calorimetric power indication may be monitored continuously for control of the unit power, the calorimetric power indication is not required to be consulted again until the daily calorimetric comparisons of the NIS indication are performed.

The following general guidance is provided for operation of SQN Units 1 and 2:

1) When the LEFM Check is available, the plant should be operated in a manner consistent with the LEFM Check based calorimetric measurement and at 3455 MWt (100% RTP).

2) If the LEFM Check is unavailable, the plant may be operated at 3455 MWt (100% RTP) using the NIS indication until the next performance of TS SR 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance comparison is due.

3) If the LEFM Check based calorimetric measurement is unavailable at the time TS SR 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance comparison is due, the feedwater venturi-based calorimetric measurement or other acceptable method should be used for the performance of the TS SR. However, to maintain consistency with the uncertainty analysis, the maximum allowable power shall be reduced to 3411 MWt or 98.7% RTP. The NIS indication or other valid power indication such as feedwater venturi or RCS delta-T may be used to control the unit power.

4) If the LEFM-based calorimetric calculation is unavailable to provide the power calorimetric measurement displayed by plant computer PID U2118, the Axial Flux Difference (AFD) Limits will automatically be made more restrictive by 1.0% AFD in the plant computer AFD monitor.

5) If the LEFM-based calorimetric calculation is unavailable to provide the power calorimetric measurement displayed by plant computer PID 8.3.4-4

SEQUOYAH UNITS 1 AND 2 TRM 8.3.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES BACKGROUND (continued)

U2118, the Rod Insertion Limits will automatically be increased by 3 steps in the plant computer Rod Insertion Limit monitor.

APPLICABLE Each of the analyzed accidents are evaluated for the range of power SAFETY levels over which the reactor is allowed to be operated. Typically, the ANALYSES analyses are most limiting when initiated from a higher power level. For SQN, the majority of the original analyses were performed for a core power of at least 3411 MWt, plus an allowance for the secondary power calorimetric measurement of 2% RTP. In general, these same analyses are used to support the revised RATED THERMAL POWER definition of a core power of 3455 MWt. With the application of a 0.7% RTP uncertainty (based on the use of the LEFM Check feedwater flow and feedwater temperature input into the secondary calorimetric measurement), the analyses are evaluated at a power level of 3479 MWt.

Analyses that use statistical methods, such as the analysis of the dropped reactor rod cluster control assembly (RCCA) event, are explicitly evaluated for operation at 3411 MWt with a 2% RTP uncertainty allowance and for operation at 3455 MWt with a 0.7% RTP uncertainty allowance.

The Axial Flux Difference (AFD) limits are based on Loss Of Coolant Accident (LOCA) and initial condition Departure from Nucleate Boiling (DNB) peaking margins. The LOCA margins at 3411 MWt with 2.0%

calorimetric uncertainty and 3455 MWt with 0.7% calorimetric uncertainty will be the same for the same power distribution. There is no change in the F Q limit, therefore the LOCA Linear Heat Rate (LHR) limit is increased by the increase in core average linear heat rate. Since the calculated linear heat rate is increased by the same amount due to the uprate, the effect cancels, and the margin is the same. Thus, the axial offset limit at 98.7% of 3455 MWt should be maintained at the same value as 100% of 3455 MWt when the LEFM is not being used. This preserves the margin at the same assumed actual core thermal power (0.987 X 3455 X 1.02 =

1.00 X 3455 X 1.007 = 3479 MWt). This means that each point on the AFD limit lines (in terms of offset) should be reduced by the difference between 100% and 98.7% power (1.3%) when LEFM is not operable.

Reducing the allowable power level by 1.3% and making the AFD limit lines more restrictive by 1.0% in AFD bounds the required changes.

When the LEFM-based power calorimetric measurement is not available as indicated by computer point ID U2118 being NCal (or unreliable) this 1% reduction in the AFD limit line is automatically applied in the integrated computer system (ICS).

8.3.4-5

SEQUOYAH UNITS 1 AND 2 TRM 8.3.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES APPLICABLE SAFETY ANALYSES (continued)

The control rod insertion limits in the Core Operating Limits Report (COLR) preserve power peaking criteria and minimum required shutdown margin. Upon loss of the LEFM function, the allowable power at each point along the insertion limit would be reduced by approximately 1.3%.

Reducing the allowable power level by 1.3% and increasing the rod insertion limit lines by 3 steps withdrawn will bound the required changes.

When the LEFM-based power calorimetric measurement is not available as indicated by computer PID U2118 being Ncal (or unreliable), this adjustment in the rod insertion limit line is automatically applied in the ICS.

The setpoints for those functions of the Reactor Protection System that are based on percentage of power (i.e., the NIS) have been calculated based on analytical margins available at the 3455 MWt definition of 100%

RTP. Operation back at 3411 MWt does not require these setpoints to be adjusted.

TECHNICAL The TR requires the LEFM to be FUNCTIONAL for the completion of the REQUIREMENT daily secondary plant calorimetric measurement required in TS SR 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance comparison. The use of the LEFM Check ensures that the basis for operation at the RATED THERMAL POWER of 3455 MWt is maintained.

FUNCTIONALITY of the LEFM is dependent on feedwater temperatures of 250 degrees F or greater to ensure design basis accuracy. Below this temperature the ICS computer will show PID U2118 as not available or unreliable.

APPLICABILITY The requirement to use the LEFM Check for the performance of the secondary plant calorimetric measurement required by TS SR 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance comparison is applicable to the unit in Mode 1 and above 15% RTP, consistent with the applicability of TS SR 3.3.1.2. The greater than 15%

RTP level threshold is chosen to ensure that the LEFM is within its specified operating range.

CONTINGENCY A.1 and A.2 MEASURES If the LEFM becomes Nonfunctional during the intervals between performance of TS SR 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance comparison plant operation may continue using the power indications from the NIS system. However, in order to remain in compliance with the bases for operation at a RATED THERMAL POWER of 3455 MWt, the LEFM must be returned to service prior to 8.3.4-6

SEQUOYAH UNITS 1 AND 2 TRM 8.3.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES CONTINGENCY MEASURES (continued) performance of TS SR 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance comparison.

B.1 and B.2 If the Contingency Measure or Restoration Time of Condition A is not met (i.e., the LEFM is not FUNCTIONAL prior to the next performance of TS SR 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance comparison), Condition B is entered. Required Contingency Measure B.1 requires that the reactor power be reduced to, or maintained at, a power level 98.7% RTP (3411 MWt). This power reduction is performed prior to TS SR 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance comparison in order to remain within the plant's design bases immediately upon performance of TS SR 3.3.1.2.

B.3 The performance of TS SR 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance comparison using acceptable alternate methods. At lower power levels this could include the use of RCS delta temperature indications. At higher power levels the feedwater venturi indications for feedwater flow are used to perform the calorimetric comparison. Once TS SR 3.3.1.2 is performed using the feedwater venturi indications of feedwater flow, the required power uncertainty is 2%

RTP. In order to maintain compliance with the safety analyses, it is necessary to operate the plant at a maximum core thermal power of 3411 MWt.

B.4 That the core power be maintained at a value less than or equal to 3411 MWt until the LEFM is returned to service and TS SR 3.3.1.2 for Power Range Neutron Flux Channel calibration by heat balance comparison, has been performed using the LEFM indication of feedwater flow. Once TS SR 3.3.1.2 has been performed using the LEFM, then the plant can again be operated at 3455 MWt.

TECHNICAL TRV 8.3.4.1 requires that the availability of the LEFM be verified prior to REQUIREMENTS it's use for the performance of TS SR 3.3.1.2 for Power Range Neutron VERIFICATION Flux Channel calibration by heat balance comparison. The self diagnostics features of the LEFM Check is used for this verification along with feedwater temperature indications. If the LEFM Normal/Fail status indication is not in Fail status, it is considered FUNCTIONAL provided feedwater temperature is greater than or equal to 250 degrees F. The 8.3.4-7

SEQUOYAH UNITS 1 AND 2 TRM 8.3.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES TECHNICAL REQUIREMENTS VERIFICATION (continued)

LEFM status indication is displayed on the plant computer system and also may be verified on the local touch screen monitor.

REFERENCES 1. License Amendment Request TVA-SQN-TS-01-08, increases the licensed power for operation of SQN Units 1 & 2 to 3455 MWt, Docket No. 50-327/50-328.

8.3.4-8

SEQUOYAH UNITS 1 AND 2 TRM 8.3.5 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.3 INSTRUMENTATION 8.3.5 Explosive Gas Monitoring System TECHNICAL REQUIREMENT (TR)

TR 8.3.5 The Explosive Gas Monitoring System with one hydrogen monitor and one oxygen monitor channel shall be FUNCTIONAL with alarm/setpoints set to ensure the concentration limits of TR 8.7.6 are not exceeded.

APPLICABILITY: During waste gas compressor operation.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One or more explosive gas A.1 Operation of the waste Every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during monitoring channel(s) gas disposal system may degassing operations Nonfunctional. continued provided grab of the reactor coolant samples are taken and system analyzed.

AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations AND A.2 Restore explosive gas 30 days monitoring channel(s) to FUNCTIONAL status.

B. Required Contingency B.1 Prepare and submit a In accordance with Measures and associated Special Report to the ODCM Section 5.4.

Restoration Time of Commission and explain Condition A not met. why the Nonfunctionality was not corrected in a timely manner.

8.3.5 -1

SEQUOYAH UNITS 1 AND 2 TRM 8.3.5 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.3.5.1 Perform a CHANNEL CHECK on Hydrogen Monitor. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 8.3.5.2 Perform a CHANNEL CHECK on Oxygen Monitor. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 8.3.5.3 Perform a CHANNEL FUNCTIONAL TEST on 31 days Hydrogen Monitor.

8.3.5.4 Perform CHANNEL FUNCTIONAL TEST on Oxygen 31 days Monitor.

8.3.5.5 Perform CHANNEL CALIBRATION on Hydrogen 92 days Monitor using standard gas samples containing a nominal:

a. 1 volume % hydrogen, balance nitrogen; and

b. 4 volume % hydrogen, balance nitrogen.

8.3.5.6 Perform CHANNEL CALIBRATION on Oxygen Monitor 92 days using standard gas samples containing a nominal:

a. 1 volume % oxygen, balance nitrogen; and

b. 4 volume % oxygen, balance nitrogen.

8.3.5 -2

SEQUOYAH UNITS 1 AND 2 TRM 8.3.5 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.3 INSTRUMENTATION 8.3.5 Explosive Gas Monitoring System BASES BACKGROUND The instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements for monitoring potentially explosive gas mixtures.

8.3.5 - 3

SEQUOYAH UNITS 1 AND 2 TRM 8.4.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.4 REACTOR COOLANT SYSTEM (RCS) 8.4.1 Chemistry TECHNICAL REQUIREMENT (TR)

TR 8.4.1 The RCS chemistry shall be maintained within the limits specified in Table 8.4.1-1.

APPLICABILITY: At all times.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. -------------NOTE----------- A.1 Restore the parameter(s) to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Only applicable in within its Steady State Limit.

MODES 1, 2, 3, and 4.

One or more chemistry parameter(s) in excess of its Steady State Limit but within its Transient Limit.

B. -------------NOTE----------- B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Only applicable in MODES 1, 2, 3, and 4. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Contingency Measure and associated Restoration Time of Condition A not met.

OR One or more chemistry parameter(s) in excess of its Transient Limit.

8.4.1-1

SEQUOYAH UNITS 1 AND 2 TRM 8.4.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 CONDITION CONTINGENCY MEASURES RESTORATION TIME C. -------------NOTE----------- C.1 Reduce the Pressurizer Immediately Only applicable in pressure to 500 psig, if MODES 5 and 6. applicable.

With the concentration AND of either chloride or fluoride in the Reactor C.2 Perform an engineering Immediately Coolant System in evaluation to determine the excess of its Steady effects of the out-of-limit State Limit for more than condition on the structural 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or in excess of integrity of the Reactor its Transient Limit. Coolant System.

AND C.3 Determine that the Reactor Prior to increasing the Coolant System remains pressurizer pressure acceptable for continued above 500 psig or operation. prior to proceeding to MODE 4.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.4.1.1 Determine by analysis, the parameters listed in Table 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 8.4.1-1 are within their specified limits.

8.4.1-2

SEQUOYAH UNITS 1 AND 2 TRM 8.4.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TABLE 8.4.1-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS PARAMETER STEADY STATE TRANSIENT LIMIT LIMIT Dissolved Oxygen(1) 0.10 ppm 1.00 ppm Chloride 0.15 ppm 1.50 ppm Fluoride 0.15 ppm 1.50 ppm (1)

Limit not applicable with T avg 250° F.

8.4.1-3

SEQUOYAH UNITS 1 AND 2 TRM 8.4.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.4 REACTOR COOLANT SYSTEM (RCS) 8.4.1 Chemistry BASES BACKGROUND The limitations on Reactor Coolant System (RCS) chemistry ensure that corrosion of the RCS is minimized and reduces the potential for RCS leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the RCS over the life of the plant. The associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with containment concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the RCS. The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the containment concentrations to within the Steady State Limits.

The verification requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

8.4.1-4

SEQUOYAH UNITS 1 AND 2 TRM 8.4.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.4 REACTOR COOLANT SYSTEM (RCS) 8.4.2 Pressurizer Temperature Limits TECHNICAL REQUIREMENT (TR)

TR 8.4.2 The pressurizer temperature shall be limited to:

a. A maximum heatup of 100°F in any one hour period,

b. A maximum cooldown of 200°F in any one hour period, and

c. A maximum spray water temperature differential of 560°F.

APPLICABILITY: At all times.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. -----------NOTE------------- A.1 Restore the temperature to 30 minutes Contingency Measure within limits.

A.2 shall be completed whenever this Condition AND is entered.

A.2 Perform an engineering Immediately evaluation to determine the Pressurizer temperature effects of the out-of-limit limits in excess of any of condition on the fracture the above limits. toughness properties of the pressurizer.

B. Contingency Measure B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated Restoration Time of AND Condition A not met.

B.2 Reduce pressurizer pressure 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR to less than 500 psig.

Pressurizer not acceptable for continued operation.

8.4.2-1

SEQUOYAH UNITS 1 AND 2 TRM 8.4.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.4.2.1 ------------------------------NOTE-----------------------------------

Only required to be performed during heatup or cooldown operation.

Determine pressurizer temperature within limits. 30 minutes 8.4.2.2 Record and evaluate if cyclic limits have been Whenever spray exceeded per Component Cyclic and Transient Limit operation differential Program. temperature is > 320°F 8.4.2-2

SEQUOYAH UNITS 1 AND 2 TRM 8.4.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.4 REACTOR COOLANT SYSTEM (RCS) 8.4.2 Pressurizer Temperature Limits BASES BACKGROUND The pressurizer is an ASME Section III, vertical vessel with hemispherical top and bottom heads constructed of carbon steel. The vessel is clad with austenitic stainless steel on all surfaces exposed to the reactor coolant. A stainless steel liner or tube may be used in lieu of cladding in some nozzles. The surge line nozzle and removable electric heaters are installed in the bottom head. Spray line nozzles, relief and safety valves are located in the top head of the vessel. A small continuous spray is provided through a manual bypass valve around the power-operated spray valves. The temperature, and hence the pressure are controlled by varying the power input to selected heater elements. The pressurizer is designed to withstand the effects of cyclic loads due to pressure and temperature changes. These loads are introduced by startup and shutdown operations, power transients and reactor trips. During startup and shutdown, the rate of temperature change is controlled by the operator. Heatup rate is controlled by the input to the heater elements, and cooldown is controlled by spray. When the pressurizer is filled with water, i.e., during initial system heatup, and near the end of the second phase of plant cooldown, RCS pressure is maintained by the letdown flow rate via the Residual Heat Removal System.

These Bases address the control of the rate of change of temperature and the effect of the thermal cycling on critical areas of the pressure boundary of the pressurizer. The Reactor Coolant Pressure Boundary, which includes the pressurizer, is defined in 10 CFR 50, section 50.2 (Ref.1). General rules for design and fabrication are provided in 10 CFR 50, section 50.55a (Ref. 2). These design and fabrication rules are based on the ASME Boiler and Pressure Vessel Code.

APPLICABLE The limits on the rate of change of temperature for the heatup and SAFETY cooldown of the pressurizer and the temperature differential associated ANALYSES with pressurizer spray are not derived from Design Basis Accident analyses (Ref. 3). The limits are prescribed during normal operation to limit the cyclic, thermal loading on critical areas in the pressure boundary.

The temperature limits have been established, using approved methodology, to preclude operation in an unanalyzed condition (Ref. 5).

8.4.2-3

SEQUOYAH UNITS 1 AND 2 TRM 8.4.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES TECHNICAL TR 8.4.2 specifies the acceptable rates of heatup and cooldown of the REQUIREMENT pressurizer and a maximum differential temperature allowed across the pressurizer spray nozzle. These limits define allowable operating regions and permit a large number of operating cycles while providing a wide margin to cyclic induced failure in the pressure boundary of the pressurizer.

APPLICABILITY The pressurizer temperature limits provide a definition of acceptable operation to limit cyclic temperature loading to analyzed conditions.

Although these limits were developed to provide rules for operation during heatup and cooldown (MODES 3, 4, and 5), they are applicable at all times.

CONTINGNECY If the rate of change of temperature or temperature differential is outside MEASURES the limits, the out-of-limit condition must be restored to within limits in 30 minutes. The 30-minute Restoration Time reflects the urgency of restoring the parameters to within the analyzed range. Most violations will not be severe, and the corrective actions can be accomplished in this time in a controlled manner. In addition to restoring operation to within limits, an evaluation is required to determine if operation may continue. This may require event-specific stress analyses or inspections. A favorable evaluation must be completed before continuing operation.

If the pressurizer temperature limits are not restored within 30 minutes, the plant must be placed in a lower MODE and the pressure reduced.

This will allow a more careful examination of the event. The 6-hour shutdown time is reasonable, considering operating experience, to reach MODE 3 from full power. The additional 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months to reduce the pressure to 500 psig in an orderly manner also considers operating experience.

This reduction in pressure is possible without challenging the plant systems or violating any operating limits.

8.4.2-4

SEQUOYAH UNITS 1 AND 2 TRM 8.4.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 BASES TECHNICAL TRV 8.4.2.1 REQUIREMENTS VERIFICATION Verifies that the rate of heatup and the rate of cooldown are within limits.

"Step wise" cooling must be avoided as discussed in Reference 4. The 30-minute Frequency is considered reasonable in view of the instrumentation available in the control room to monitor the status of the RCS.

TRV 8.4.2.2 Verifies that any spray operation with a differential temperature greater than 320°F be recorded for evaluation of the cyclic limits in accordance with Component Cyclic and Transient Limit Program. The number of high temperature differential spray actuations must be maintained within the cyclic or transient limits in accordance with Component Cyclic and Transient Limit Program.

REFERENCES 1. 10 CFR 50.2, "Definitions."

2. 10 CFR 50.55a, "Codes and Standards."

3. WCAP-11618, "MERITS Program-Phase II, Task 5, Criteria Application," including Addendum 1 dated April, 1989.

4. Westinghouse letter TVA-90-1130, "Reactor Coolant System Accelerated Cooldown," dated November 5, 1990.

5. Westinghouse Equipment Specification 677234, Revision No. 4, dated January 10 1975.

8.4.2-5

SEQUOYAH UNITS 1 AND 2 TRM 8.4.3 TECHNICAL REQUIREMENTS MANUAL Revision 55 October 7, 2016 8.4 REACTOR COOLANT SYSTEM (RCS) 8.4.3 Reactor Coolant System Head Vents (RCSHVs)

TECHNICAL REQUIREMENT (TR)

TR 8.4.3 Two RCSHV paths shall be FUNCTIONAL.

APPLICABILITY: MODES 1, 2, and 3.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One RCSHV path A.1 Verify Nonfunctional RCSHV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Nonfunctional. path isolated with power removed from the associated RCSHV valve actuators.

B. With no RCSHV path B.1 Verify RCSHV paths isolated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months FUNCTIONAL. with power removed from the associated RCSHV valve actuators.

AND B.2 Restore at least one RCSHV 30 days path to FUNCTIONAL status.

C. Required Contingency C.1 Evaluate in accordance with Immediately Measures and associated TR 7.5.3.

Restoration Time of Condition A or B not met.

8.4.3-1

SEQUOYAH UNITS 1 AND 2 TRM 8.4.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.4.3.1 Verify the upstream manual isolation valves of each 18 months RCSHV path are locked in the open position.

8.4.3.2 Cycle each remotely operated valve in each RCSHV 18 months path through at least one complete cycle of full travel from the Control Room.

8.4.3.3 Verify flow through each RCSHV path. 18 months 8.4.3-2

SEQUOYAH UNITS 1 AND 2 TRM 8.4.3 TECHNICAL REQUIREMENTS MANUAL Revision 55 October 7, 2016 8.4 REACTOR COOLANT SYSTEM (RCS) 8.4.3 Reactor Coolant System Head Vents (RCSHVs)

BASES BACKGROUND The function of the RCSHVs is to remove non-condensables or steam from the reactor vessel head. This system is designed to mitigate a possible condition of inadequate core cooling, inadequate natural circulation, or inability to depressurize the RHR System initiated conditions resulting from the accumulation of non-condensable gases in the RCS. The RCSHV is designed with redundant safety grade vent paths.

8.4.3-3

SEQUOYAH UNITS 1 AND 2 TRM 8.6.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.6 CONTAINMENT SYSTEM 8.6.1 Combustible Gas Control Hydrogen Monitors TECHNICAL REQUIREMENT (TR)

TR 8.6.1 Two independent containment hydrogen monitors shall be FUNCTIONAL.

APPLICABILITY: MODES 1 and 2.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One hydrogen monitor A.1 Restore hydrogen monitor to 30 days Nonfunctional. FUNCTIONAL status.

B. Both hydrogen monitors B.1 Restore at least one 7 days Nonfunctional. hydrogen monitor to FUNCTIONAL status.

C. Required Contingency C.1 Evaluate in accordance with Immediately Measures and associated TR 7.5.3.

Restoration Time of Condition A or B not met.

8.6.1-1

SEQUOYAH UNITS 1 AND 2 TRM 8.6.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.6.1.1 Perform a CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 8.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 31 days 8.6.1.3 Perform CHANNEL CALIBRATION using sample gas 46 days on a containing: STAGGERED TEST BASIS

a. 1.0 volume % hydrogen, balance nitrogen; and

b. 4.0 volume % hydrogen, balance nitrogen.

8.6.1-2

SEQUOYAH UNITS 1 AND 2 TRM 8.6.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.6 CONTAINMENT SYSTEM 8.6.1 Combustible Gas Control Hydrogen Monitors BASES BACKGROUND The FUNCTIONALITY of the equipment and systems required for the detection of hydrogen gas ensures that this equipment will be available to monitor the hydrogen concentration within containment during significant beyond design-basis accident conditions. The hydrogen monitors of TR 8.6.1 are part of the accident monitoring instrumentation required by 10 CFR 50.44, Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors, October 16, 2003.

8.6.1-3

SEQUOYAH UNITS 1 AND 2 TRM 8.6.2 TECHNICAL REQUIREMENTS MANUAL Revision 62 July 11, 2019 8.6 CONTAINMENT SYSTEM 8.6.2 Ice Bed Temperature Monitoring System TECHNICAL REQUIREMENT (TR)

TR 8.6.2 Ice bed temperature monitoring system shall be FUNCTIONAL with at least 2 FUNCTIONAL resistance temperature detector (RTD) channels in the ice bed at each of 3 basic elevations (10'6", 30'9", and 55' above the floor of the ice condenser) for each one third of the ice condenser.

APPLICABILITY: MODES 1, 2, 3, and 4.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. Main control room ice A.1 Determine ice bed Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months bed temperature temperature at local ice indication Nonfunctional. condenser monitoring panel.

B. Ice bed temperature B.1 Verify ice compartment lower Immediately monitoring system inlet doors are closed.

Nonfunctional and no alternate means of AND monitoring ice bed temperature. B.2 Verify intermediate deck Immediately doors are closed.

AND B.3 Verify top deck doors are Immediately closed.

AND B.4 Verify the last recorded Immediately mean ice bed temperature was 20F and steady.

AND B.5 Restore to FUNCTIONAL 6 days status.

8.6.2-1

SEQUOYAH UNITS 1 AND 2 TRM 8.6.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 CONDITION CONTINGENCY MEASURES RESTORATION TIME C. Required Contingency C.1 Evaluate in accordance with Immediately Measures and associated TR 7.5.3.

Restoration Time of Condition A or B not met.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.6.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 8.6.2-2

SEQUOYAH UNITS 1 AND 2 TRM 8.6.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.6 CONTAINMENT SYSTEM 8.6.2 Ice Bed Temperature Monitoring System BASES BACKGROUND The FUNCTIONALITY of the ice bed temperature monitoring system ensures that the capability is available for monitoring the ice temperature.

In the event the ice bed temperature monitoring system is Nonfunctional, the Contingency Measures provide assurance that the ice bed heat removal capacity will be retained within the specified time limits.

8.6.2-3

SEQUOYAH UNITS 1 AND 2 TRM 8.6.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.6 CONTAINMENT SYSTEM 8.6.3 Inlet Door Position Monitoring System TECHNICAL REQUIREMENT (TR)

TR 8.6.3 The inlet door monitoring system shall be FUNCTIONAL.

APPLICABILITY: MODES 1, 2, 3, and 4.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. Inlet door position A.1.1 Verify ice bed temperature Immediately monitoring system monitoring system is Nonfunctional. FUNCTIONAL.

AND A.1.2 Verify ice bed temperature is Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 27F.

AND A.1.3 Restore inlet door monitoring 14 days system to FUNCTIONAL status.

OR A.2 Restore inlet door monitoring 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months system to FUNCTIONAL status.

B. Required Contingency B.1 Evaluate in accordance with Immediately Measures and TR 7.5.3.

associated Restoration Time of Condition A not met.

8.6.3-1

SEQUOYAH UNITS 1 AND 2 TRM 8.6.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.6.3.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 8.6.3.2 Perform CHANNEL FUNCTIONAL TEST. 18 months 8.6.3.3 -----------------------------NOTE-------------------------------------

Channel calibration consists of cycling of the inlet door and verifying position indication reflects door position.

Perform CHANNEL CALIBRATION. 18 months 8.6.3-2

SEQUOYAH UNITS 1 AND 2 TRM 8.6.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.6 CONTAINMENT SYSTEM 8.6.3 Inlet Door Position Monitoring System BASES BACKGROUND The FUNCTIONALITY of the inlet door position monitoring system ensures that the capability is available for monitoring the individual inlet door position. In the event the monitoring system is Nonfunctional, the Contingency Measures provide assurance that the ice bed heat removal capacity will be retained within the specified time limits.

8.6.3-3

SEQUOYAH UNITS 1 AND 2 TRM 8.6.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.6 CONTAINMENT SYSTEM 8.6.4 Lower Containment Vent Coolers TECHNICAL REQUIREMENTS (TR)

TR 8.6.4 Two independent trains of lower containment vent coolers shall be FUNCTIONAL with two coolers to each train.

APPLICABILITY: MODES 1, 2, 3, and 4.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One required lower A.1 Restore to FUNCTIONAL 7 days containment vent cooler status.

Nonfunctional.

B. Two required lower B.1 Restore to FUNCTIONAL 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months containment vent status.

coolers in the same train Nonfunctional.

C. Required Contingency C.1 Evaluate in accordance with Immediately Measures and associated TR 7.5.3.

Restoration Time of Condition A or B not met.

8.6.4-1

SEQUOYAH UNITS 1 AND 2 TRM 8.6.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.6.4.1 Verify each lower containment vent cooler fan operates 31 days for greater than or equal to 15 minutes.

8.6.4.2 Verify each lower containment vent cooler fan starts 18 months from the control room.

8.6.4.3 Verify a cooling water flow rate of 200 gpm to each 18 months cooler.

8.6.4-2

SEQUOYAH UNITS 1 AND 2 TRM 8.6.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.6 CONTAINMENT SYSTEM 8.6.4 Lower Containment Vent Coolers BASES BACKGROUND The FUNCTIONALITY of the lower containment vent coolers ensures that adequate heat removal capacity is available to provide long term cooling following a non-LOCA event. Post accident use of these coolers ensures containment temperatures remain within environmental qualification limits for all safety-related equipment required to remain FUNCTIONAL.

8.6.4-3

SEQUOYAH UNITS 1 AND 2 TRM 8.7.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.1 Steam Generator Pressure/Temperature Limitation TECHNICAL REQUIREMENT (TR)

TR 8.7.1 The temperature of the primary and secondary coolants in the steam generators shall be > 70°F when the pressure of either coolant in the steam generator is > 200 psig.

APPLICABILITY: At all times.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. -----------NOTE------------- A.1 Reduce the steam 30 minutes Contingency Measure generator pressure of the A.2 and A.3 shall be applicable side to completed whenever 200 psig.

this Condition is entered.

AND TR not met. A.2 Determine by engineering Prior to increasing evaluation the effects of steam generator the overpressurization on temperatures > 200 F the structural integrity of the steam generator.

AND A.3 Determine that the steam Prior to increasing generator remains steam generator acceptable for continued temperatures > 200 F operation.

8.7.1-1

SEQUOYAH UNITS 1 AND 2 TRM 8.7.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY

NOTE---------------------------------

8.7.1.1 Only required to be performed when the temperature of either the primary or secondary coolant is < 70°F.

Verify pressure of each side of the steam generator is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

< 200 psig.

8.7.1-2

SEQUOYAH UNITS 1 AND 2 TRM 8.7.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.1 Steam Generator Pressure / Temperature Limitation BASES BACKGROUND The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70°F and 200 psig are based on a steam generator Reference Temperature Nil Ductility Transition (RT NDT ) of 25°F and are sufficient to prevent brittle fracture.

8.7.1-3

SEQUOYAH UNITS 1 AND 2 TRM 8.7.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.2 Flood Protection TECHNICAL REQUIREMENT (TR)

TR 8.7.2 The flood protection plan shall be ready for implementation to maintain the plant in a safe condition.

APPLICABILITY: When one or more of the following conditions exist:

a. Early warning of major flood-producing rainfall conditions in the east Tennessee watershed,

b. Early warning that a critical combination of flood and/or higher than normal summer pool levels plus possible dam failures or other dam safety emergencies may or have developed, or

c. Warnings that flood elevation is predicted to exceed plant grade (Stages I and II).

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. Early warning is issued. --------------------NOTE-------------------

Completion of A.2.1 and A.2.2 are not required if communications are verified.

A.1 Verify communications 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months between Sequoyah Nuclear Plant and TVA River Systems Operations (RSO).

OR A.2.1 Complete Stage I flood 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months protection procedure.

AND A.2.2 Complete Stage II flood 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months protection procedure.

8.7.2-1

SEQUOYAH UNITS 1 AND 2 TRM 8.7.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 CONDITION CONTINGENCY MEASURES RESTORATION TIME B. Stage I flood warning B.1 Be in MODE 3 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months issued.

AND B.2 T avg 350°F 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months AND B.3 Verify SDM is 5% k/k. 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months AND B.4 Complete Stage I 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months protection procedure.

AND B.5.1 Verify communications 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months between Sequoyah Nuclear Plant and TVA RSO.

OR B.5.2 Complete Stage II flood 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months protection procedure.

C. Stage II flood warning C.1 Initiate Stage II flood 17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months prior to the issued. protection procedure. predicted arrival time of the initial critical flood level (703 ft Mean Sea Level (MSL) winter and summer).

AND C.2 Complete Stage II flood Prior to predicted protection procedure. Stage II flood level.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.7.2.1 Verify communications between Sequoyah Nuclear Every 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Plant and TVA River System Operations (RSO).

8.7.2-2

SEQUOYAH UNITS 1 AND 2 TRM 8.7.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.2 Flood Protection BASES BACKGROUND The requirements for flood protection ensures that facility protective actions will be taken and operation will be terminated in the event of flood conditions. A Stage 1 flood warning is issued when the water in the forebay is predicted to exceed 697 feet Mean Sea Level USGS datum during October 1 through April 15, or 703 Feet Mean Sea Level USGS datum during April 15 through September 30 due to a major flood-producing storm not combined with any dam failures or emergencies. A Stage I flood warning is also issued when the water level is predicted to exceed elevation 703 from a combination of flood and dam failures, winter or summer. A Stage II flood warning is issued when the water in the forebay is predicted to exceed 703 feet Mean Sea Level USGS datum. A maximum allowed water level of 703 feet Mean Sea Level USGS datum provides sufficient margin to ensure waves due to high winds cannot disrupt the flood mode preparation. A Stage I or Stage II flood warning requires the implementation of procedures which include plant shutdown.

Further, in the event of a loss of communications simultaneous with a critical flood, or combination of flood and dam failure, the plant will be shutdown and flood protection measures will be implemented.

8.7.2-3

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.3 Snubbers TECHNICAL REQUIREMENT (TR)

TR 8.7.3 Each safety related snubber shall be FUNCTIONAL.

APPLICABILITY: MODES 1, 2, 3, and 4, MODES 5 and 6 for snubbers located on systems or partial systems required OPERABLE/FUNCTIONAL in those MODES.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One or more required A.1.1 Replace or restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months snubber(s) associated Nonfunctional snubber(s) with a TRM system to FUNCTIONAL status.

Nonfunctional.

AND A.1.2 Perform engineering 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months evaluation on the attached component.

OR A.2 Declare the attached Immediately system Nonfunctional and enter appropriate TRM Contingency Measure.

8.7.3-1

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 CONDITION CONTINGENCY MEASURES RESTORATION TIME B. One or more required B.1 Evaluate entry into Immediately snubber(s) associated Technical Specification with a Technical LCO 3.0.8.

Specification structure, system, or component AND Nonfunctional.

B.2 Evaluate the risk Immediately associated with the Nonfunctional snubber and the ability to properly manage the risk.

AND B.3 Evaluate Auxiliary Immediately Feedwater OPERABILITY and/or alternative core cooling capability.

AND B.4 Evaluate non-seismic Immediately capability associated with the Nonfunctional snubber.

AND B.5.1 Perform an engineering 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months evaluation on the attached component to determine potential system degradation.

OR B.5.2 Declare the affected plant Immediately system(s) inoperable.

8.7.3-2

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.7.3.1 Perform snubber inservice inspections in accordance In accordance with with Appendix 1. Appendix 1 8.7.3-3

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 Appendix 1 Augmented Inservice Inspection Program

a. Inspection Groups The snubbers may be categorized into two major groups based on whether the snubbers are accessible or inaccessible during reactor operation. These major groups may be further subdivided into subgroups based on design, environment, or other features which may be expected to affect the FUNCTIONALITY of the snubbers within the subgroup.

Each subgroup may be tested independently in accordance with Appendix 1 (d) through (h).

b. Visual Inspection Schedule and Lot Size All of the safety-related snubbers shall be included in one population, or they shall be categorized as accessible or inaccessible for visual inspection. If used, the accessible or inaccessible categories shall be considered separately for visual inspections.

When recombining categories into one population, the shorter interval of the categories shall be used.

The visual inspection interval for the population or each category shall be determined based upon the criteria provided in Table 8.7.3-1, and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before the amendment which incorporated this change was issued by the NRC.

8.7.3-4

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 Table 8.7.3-1 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population or Column A Column B Column C Category Extended Interval Repeat Interval Reduce Interval (Notes 1 and 2) (Notes 3 and 6) (Notes 4 and 6) (Notes 5 and 6) 1 0 0 1 80 0 0 2 100 0 1 4 150 0 3 8 200 2 5 13 300 5 12 25 400 8 18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1: The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. These categories may be examined separately or jointly. However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.

Note 2: Interpolation between population or category size and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as described by interpolation.

Note 3: If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.

Note 4: If the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.

Note 5: If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval. However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation; that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.

Note 6: The provisions of Technical Requirement Verification 7.6.2 are applicable for all inspection intervals up to and including 48 months.

8.7.3-5

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015

c. Visual Inspection Performance and Evaluation Visual inspections shall verify (1) that there are no visible indications of damage or impaired FUNCTIONALITY, (2) bolts attaching the snubber to the foundation or supporting structure are secure, and (3) snubbers attached to sections of safety-related systems that have experienced unexpected potentially damaging transients since the last inspection period shall be evaluated for the possibility of concealed damage and functionally tested, if applicable, to confirm FUNCTIONALITY.

Snubbers which appear Nonfuntional as a result of visual inspections may be determined FUNCTIONAL for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible and (2) the affected snubber is functionally tested in the as-found condition and determined FUNCTIONAL per Appendix 1 (e). Hydraulic snubbers with Nonfunctional single or common fluid reservoirs which have uncovered fluid ports shall be declared Nonfunctional.

Also, snubbers which have been made Nonfunctional as the result of unexpected transients, isolated damage, or other such random events, when the provisions of Appendix 1 (g) and (h) have been met and any other appropriate corrective action implemented, shall not be counted in determining the next visual inspection interval.

d. FUNCTIONAL Test Schedule, Lot Size, and Composition At an interval commensurate with each refueling outage, a representative sample of 10% of the total of the safety-related snubbers in use in the plant shall be functionally tested either in place or in a bench test. The representative sample selected for FUNCTIONAL testing shall include the various configuration, operating environments, and the range of size and capacity of snubbers within the groups or subgroups. The representative sample should be weighted to include more snubbers from severe service areas such as near heavy equipment. Unless a failure analysis as required by Appendix 1 (f) indicates otherwise, the sample shall be a composite based on the ratio of each group to the total number of snubbers installed in the plant. Snubbers placed in the same location as snubbers which failed the previous FUNCTIONAL test shall be included in the next lot if the failure analysis shows that failure was due to location.

The security of fasteners for attachment of the snubbers to the component and to the snubber anchorage shall be verified on snubbers selected for FUNCTIONAL tests.

The provisions of Technical Requirement Verification 7.6.2 are applicable to the interval for performing functional tests. During plant operating MODES 1 through 4 (and MODES 5 and 6 for snubbers located on systems or partial systems required OPERABLE/FUNCTIONAL in the MODES), administrative controls are required for performing snubber functional testing for the purpose of satisfying the functional test interval requirement.

8.7.3-6

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015

e. Functional Test Acceptance Criteria The snubber functional test shall verify that:

1. Activation (restraining action) is achieved within the specified range in both tension and compression, except that inertia dependent, acceleration limiting mechanical snubbers, may be tested to verify only that activation takes place in both directions of travel.

2. Snubber bleed, or release where required, is present in both tension and compression within the specified range.

3. The force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel.

4. Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.

f. Functional Test Failure Analysis and Additional Test Lots If any snubber selected for functional testing either fails to lock up or fails to move due to manufacture or design deficiency, all snubbers of the same design subject to the same defect shall be functionally tested. If a snubber does not meet the functional test acceptance criteria, an additional lot equal to one-half the original lot size shall be functionally tested for each failed snubber. An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure. The result of this analysis shall be used, if applicable, in selecting snubbers to be tested in the subsequent lot in an effort to determine the functionality of other snubbers which may be subject to the same failure mode. (Selection of snubbers for future testing may also be based on the failure analysis.) Testing shall continue until no additional nonfunctional snubber is found within a subsequent required lot or all snubbers of the original inspection group have been tested, or all suspect snubbers identified by the failure analysis have been tested, as applicable.

The discovery of loose or missing attachment fasteners will be evaluated to determine whether the cause may be localized or generic. The result of the evaluation will be used to select other suspect snubbers for verifying the attachment fasteners, as applicable.

Snubbers shall not be subjected to prior maintenance specifically for the purpose of meeting functional test requirements.

g. Functional Test Failure - Attached Component Analysis For snubber(s) found nonfunctional, an engineering evaluation shall be performed on the components which are restrained by the snubber(s). The purpose of this engineering evaluation shall be to determine if the components restrained by the snubber(s) were adversely affected by the nonfunctionality of the snubber(s) and in order to ensure that the restrained component remains capable of meeting the designed service.

8.7.3-7

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015

h. Functional Testing of Repaired and Spare Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced. Replacement snubbers and snubbers which have repairs which might affect the functional test results shall be tested to meet the functional test criteria before installation in the unit. These snubbers shall have met the acceptance criteria subsequent to their most recent service, and the functional test must have been performed within 12 months before being installed in the unit.

i. Snubber Service Life Program The service life of hydraulic and mechanical snubbers shall be monitored to ensure that the service life is not exceeded between verification inspections. The maximum expected service life for the various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be FUNCTIONAL. The parts replacements shall be documented, and the documentation shall be retained in accordance with Appendix B, Table 2, of the Nuclear Quality Assurance Plan.

j. Exemption From Visual Inspection or Functional Tests Permanent or other exemptions from the verification program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and if applicable snubber life destructive testing was performed to qualify snubber functionality for the applicable design conditions at either the completion of their fabrication or at a subsequent date.

8.7.3-8

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.3 Snubbers BASES BACKGROUND Snubbers are designed to prevent unrestrained pipe or component motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. The consequence of a Nonfunctional snubber is an increase in the probability of structural damage to piping or components as a result of a seismic or other event initiating dynamic loads. It is therefore required that all snubbers protecting the primary coolant system or any other safety system or component be FUNCTIONAL during reactor operation.

Because the snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is allowed to replace or restore the Nonfunctional snubber(s) associated with a TRM system to FUNCTIONAL status and perform an engineering evaluation on the supported component or declare the supported system inoperable and follow the appropriate limiting condition for operation statement for that system. The engineering evaluation is performed to determine whether the mode of failure of the snubber has adversely affected any safety-related component or system.

Individual snubbers associated with TRM systems may be removed from service for functional testing during plant operating MODES 1 through 4 (and MODES 5 and 6 for snubbers located on systems or partial systems required FUNCTIONAL in these MODES) provided the following administrative controls are implemented:

Contingency Measures for Condition A shall be met.

Snubbers on trained systems or portions of trained systems may be removed only on the scheduled train work week. Snubbers on non-trained systems or portions on non-trained systems may only be removed following a documented risk assessment. Snubbers may not be removed from service for testing on one train of a system while the other train has been declared Nonfunctional for any reason.

No more than one snubber may be removed from service at a time on any line and attached piping which is analyzed as a seismic subsystem. Multiple snubbers may be removed for testing simultaneously only if separated by a seismic anchor.

8.7.3-9

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7.3 Snubbers BASES BACKGROUND (continued)

For snubber(s) associated with Technical Specification (TS) required structures, systems, or components (SSC)an evaluation must be performed to determine if the provisions of TS LCO 3.0.8 can be applied.

The following table describes the evaluations to be performed:

One or more Nonfunctional Immediately evaluate the following plant conditions to snubber(s) determine the Applicability of TS LCO 3.0.8:

(For snubbers associated 1. The risk associated with the Nonfunctional snubber(s) with a TS SSC(s)) and the ability to properly manage the risks.

2. Auxiliary feedwater (AFW) OPERABILITY and/or alternative core cooling capability.

3. Non-seismic capability associated with the Nonfunctional snubber(s).

Evaluate risk. Risk associated with entry into TS LCO 3.0.8 resulting from snubber maintenance activities or an emergent OPERABILITY issue must be assessed and managed.

(For MODES 1 through 4): On the affected SSC(s), implement compensatory measures, such as postings, rescheduling maintenance activities, and briefings of plant operators, as appropriate, to enhance the availability of the affected equipment.

If the snubber(s) affects only one train of a TS SSC or subsystem,

1. Ensure that at least one train of the AFW system (including a minimum set of supporting equipment required for its successful operation) not associated with the Nonfunctional snubber(s) is OPERABLE.

2. Ensure no maintenance work is planned on the OPERABLE AFW system until TS LCO 3.0.8 is exited.

8.7.3-10

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7.3 Snubbers BASES BACKGROUND (continued)

Evaluate risk. (continued) If the snubber(s) affects more than one train of a TS SSC or subsystem,

1. Ensure at least one train of AFW system (including a minimum set of supporting equipment required for its successful operation) not associated with the Nonfunctional snubber(s) is OPERABLE, OR Some alternate means of core cooling such as feed and bleed using the steam generators, fire water system, or aggressive secondary cooldown using the steam generators must be available.

2. Ensure no maintenance work is planned on the OPERABLE AFW system until TS LCO 3.0.8 is exited.

(In MODES 5 and 6 for snubbers located on SSC or partial systems required OPERABLE in those MODES): Review the outage schedule and ensure that a diverse means of performing the required safety function is available. For example, if a snubber is rendered Nonfunctional on the normal charging line, the ability to add borated water via the safety injection (SI) system would be a diverse means of performing the required safety function.

Evaluate any non-seismic An evaluation of the non-seismic function(s) (if any) of the function(s) performed by Nonfunctional snubber(s) shall be performed immediately.

the snubber(s).

1. If the analysis concludes that the supported TS SSC is OPERABLE for its non-seismic load function, then TS LCO 3.0.8 may be applied to this Nonfunctional snubber.

2. If the analysis concludes that the supported TS SSC is inoperable for its non-seismic function, then immediately declare the affected SSC inoperable. The provisions of TS LCO 3.0.8 would not apply.

8.7.3-11

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7.3 Snubbers BASES BACKGROUND (continued)

Evaluate any non-seismic 3. The following shall be documented for the purpose of function(s) performed by making them available on a recoverable basis for NRC the snubber(s). (continued) staff inspection:

a. The design function of the Nonfunctional snubber(s) (i.e., seismic vs. non-seismic).

b. The implementation of any applicable restrictions (such as one AFW train OPERABLE, etc.).

c. The associated plant configuration (such as plant MODE, power level, and any applicable TS Action, etc.).

Perform an engineering Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , perform an engineering evaluation on the evaluation. attached component. The purpose of this engineering evaluation is to determine if the component to which the Nonfunctional snubber(s) is attached has been adversely affected by the mode of failure of the snubber. This is to ensure that the component remains capable of meeting its design function.

A snubber removed from service for FUNCTIONAL TRV testing does not require an engineering evaluation.

If the above evaluations determine that TS LCO 3.0.8 is applicable for the Nonfunctional snubber(s) associated with a TS SSC, the provisions of TS LCO 3.0.8 may be applied in lieu of declaring the affected SSC inoperable. If TS LCO 3.0.8 is determined to not be applicable, the affected TS supported SSC LCO must be declared not met.

Safety-related snubbers are visually inspected for overall integrity and FUNCTIONALITY. The inspection will include verification of proper orientation, adequate fluid level is applicable, and attachment of the snubber to its anchorage. The removal of insulation or the verification of torque values for threaded fasteners is not required for visual inspections.

8.7.3-12

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7.3 Snubbers BASES BACKGROUND (continued)

The inspection frequency is based upon maintaining a constant level of snubber protection. Thus, the required inspection interval varies inversely with the observed snubber failures. The number of Nonfunctional snubbers found during a required inspection determines the time interval for the next required inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25 percent) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the pervious schedule.

When the cause of the rejection of a snubber in a visual inspection is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible and FUNCTIONALITY verified by inservice functional testing, if applicable, that snubber may be exempted from being counted as Nonfunctional. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration. Test groups may be established based on design features and installed conditions which may be expected to be generic. Each of these groups are tested separately unless an engineering analysis indicates the group is improperly constituted. All suspect snubbers are subject in inspection and testing regardless of test groupings.

To further increase the assurance of snubber reliability, functional tests shall be performed at an interval commensurate with each refueling outage. These tests will include stroking of the snubbers to verify proper movement, activation, and bleed or release. The performance of hydraulic snubbers generally depends on a clean, deaerated fluid contained within variable pressure chambers, flowing at closely controlled rates. Since these characteristics are subject to change with exposure to the reactor environment, time, and other factors, their performance within the specified range should be verified. Mechanical snubbers which depend upon overcoming the inertia of a mass and the braking action of a capstan spring contained within the snubber for limiting the acceleration of the attached component (within the load rating of the snubber) are not subject to changes in performance in the same manner as hydraulic snubbers. Pending the development of information regarding the change during the service of the snubber of the acceleration/resistance relationship and the optimum method for detecting this change, these mechanical snubbers may be tested to verify that when subjected to a large change in velocity the resistance to movement increases greatly.

8.7.3-13

SEQUOYAH UNITS 1 AND 2 TRM 8.7.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7.3 Snubbers BASES BACKGROUND (continued)

The performance change information was developed in order to establish test methods to be used during and after the first refueling outage.

Ten percent of the total population of snubbers is an adequate sample for functional tests. The initial sample is to be proportioned among the groups in order to obtain a representative sample. An observed failure of a snubber in the initial lot will require an engineering analysis and testing of additional snubbers selected from snubbers likely to have the same defect. A thorough inspection of the snubber threaded attachments to the pipe or components and the anchorage will be made in conjunction with all required functional tests.

A list of individual snubbers with detailed information of snubber location and size shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall be determined based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g.,

temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guide 8.8 and 8.10. The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.

8.7.3-14

SEQUOYAH UNITS 1 AND 2 TRM 8.7.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.4 Sealed Source Contamination TECHNICAL REQUIREMENT (TR)

TR 8.7.4 Each sealed source containing radioactive material > 100 µCi of beta and/or gamma emitting material or > 5 µCi of alpha emitting material, shall be free of 0.005 µCi of removable contamination.

APPLICABILITY: At all times.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One or more sealed A.1 Withdraw the sealed Immediately sources with removable source from use.

contamination not within limits. AND A.2.1 Initiate action to Immediately decontaminate and repair the sealed source.

OR A.2.2 Initiate action to dispose of Immediately the sealed source in accordance with NRC Regulations.

8.7.4-1

SEQUOYAH UNITS 1 AND 2 TRM 8.7.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION

NOTES----------------------------------------------------------

1. The TRVs shall be performed by Sequoyah personnel or other personnel specifically authorized by the NRC or Agreement State.

2. The test method used shall have a detection sensitivity of 0.005 µCi per test sample.

TRV VERIFICATION FREQUENCY 8.7.4.1 --------------------------------NOTE---------------------------------

Startup sources and fission detectors previously subjected to core flux are excluded.

Perform leakage and/or contamination testing on each 184 days sealed source in use containing radioactive materials with a half-life > 30 days (excluding Hydrogen 3) and in any form other than gas.

8.7.4.2 Perform leakage and/or contamination testing for each Prior to placing in use sealed source and fission detector not in use. or transferring to another licensee, if not performed within the previous 184 days.

8.7.4.3 Perform leakage and/or contamination testing on each Prior to placing in use.

sealed source and fission detector not in use that was received without a certificate indicating the last test date.

8.7.4.4 Perform leakage and/or contamination testing on each Once within 31 days sealed startup source and fission detector. prior to being subjected to core flux or installed in the core.

AND Following repair or maintenance to the sealed source.

8.7.4.5 Submit report to NRC for sealed source or fission Annually detector leakage tests revealing the presence of 0.005 µCi of removable contamination.

8.7.4-2

SEQUOYAH UNITS 1 AND 2 TRM 8.7.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.4 Sealed Source Contamination BASES BACKGROUND The limitations on removable contamination for sources requiring leak testing, including alpha emitters, are based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from by-product, source and special nuclear material sources will not exceed allowable intake values. Sealed sources are classified into three groups according to their use, with Technical Requirements Verification commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

8.7.4-3

SEQUOYAH UNITS 1 AND 2 TRM 8.7.5 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.5 Heating, Ventilating, and Air Conditioning (HVAC) Maintenance Rule Equipment TECHNICAL REQUIREMENT (TR)

TR 8.7.5 The HVAC components shown in Table 8.7.5-1 shall be FUNCTIONAL.

APPLICABILITY: As shown in Table 8.7.5-1.

CONTINGENCY MEASURES+

NOTES----------------------------------------------------------------

Separate entry is allowed for each HVAC component.

CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One or more HVAC A.1 Enter the associated Immediately component(s) in Table Nonfunctional component in 8.7.5-1 Nonfunctional. the Operation narrative logs and LCO tracking logs for Maintenance Rule Unavailability tracking.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY None None None 8.7.5-1

SEQUOYAH UNITS 1 AND 2 TRM 8.7.5 TECHNICAL REQUIREMENTS MANUAL Revision 61 February 21, 2019 Table 8.7.5-1 HVAC Maintenance Rule Equipment EQUIPMENT COMPONENTS APPLICABLE MODES Electrical Board Room A Train chiller and air ALL MODES 1.

Cooling, A Train handling unit Electric Board Room B Train chiller and air ALL MODES 2.

Cooling, B Train handling unit Shutdown Board Room A Train chiller, chilled water ALL MODES 3.

Cooling, A Train system, and 1A and 2A air handling units Shutdown Board Room B Train chiller, chilled water ALL MODES 4.

Cooling, B Train system, and 1B and 2B air handling units 1A 480 V Electric Board 1A chiller, condensing and ALL MODES 5.

Room Cooling air handling units 1B 480 V Electric Board 1B chiller, condensing and ALL MODES 6.

Room Cooling air handling units 2A 480 V Electric Board 2A chiller, condensing and ALL MODES 7.

Room Cooling air handling units 2B 480 V Electric Board 2B chiller, condensing and ALL MODES 8.

Room Cooling air handling units 1A 480 V Transformer 1A1-A, 1A2-A, 1A3-A, and ALL MODES 9.

Room Ventilation 1A4-A exhaust fans 1B 480 V Transformer 1B1-B, 1B2-B, and 1B3-B ALL MODES 10.

Room Ventilation exhaust fans 2A 480 V Transformer 2A1-A, 2A2-A, and 2A3-A ALL MODES 11.

Room Ventilation exhaust fans 2B 480 V Transformer 2B1-B, 2B2-B, 2B3-B, and ALL MODES 12.

Room Ventilation 2B4-B exhaust fans Thermal Barrier Booster A Train Cooler MODES 1,2,3, and 4 13.

Pump & Spent Fuel Pit Pump Cooler, A Train 14.

Thermal Barrier Booster B Train Cooler MODES 1,2,3, and 4 Pump & Spent Fuel Pit Pump Cooler, B Train 8.7.5-2

SEQUOYAH UNITS 1 AND 2 TRM 8.7.5 TECHNICAL REQUIREMENTS MANUAL Revision 60 June 8, 2018 8.7 PLANT SYSTEMS 8.7.5 Heating, Ventilating, and Air Conditioning (HVAC) Maintenance Rule Equipment BASES BACKGROUND The HVAC equipment listed in Table 8.7.5-1 is required to be tracked for unavailability by Sequoyahs implementation of 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants. The Maintenance Rule program requires that the time this equipment is Nonfunctional, be monitored, whether due to an unplanned failure or planned maintenance. The required FUNCTIONALITY of the HVAC equipment is commensurate with the required OPERABILITY of the equipment being cooled. Engineering will trend the unavailability of the equipment as required based on Risk Significance of the equipment. The final Maintenance Rule unavailability time will be determined by Engineering. The equipment listed in Table 8.7.5-1 has no Technical Specification LCO or other associated TRM contingency measures for FUNCTIONALITY. Therefore, this TRM was created to provide indication for the unavailability of this HVAC equipment, and to assist in the tracking and trending of the total unavailability time.

APPLICABLE The design basis of this HVAC equipment is to maintain the temperature SAFETY of the area, to which the associated equipment provides cooling, below ANALYSES the design basis limits as described in the Environmental Design Criteria SQN-DC-V-21.0.

This TRM is being implemented for tracking purposes only and there is no associated Safety Analysis affected or implemented by this change.

TECHNICAL This TR is being implemented to track the unavailability time of the REQUIREMENT associated HVAC equipment. This equipment is considered to be FUNCTIONAL when the individual components necessary to maintain the associated area temperature below the design required limits are FUNCTIONAL. These components include the chiller package, cooling coils, air handling unit, pumps, fan, dampers, instrumentation, and controls as applicable to the various systems.

8.7.5-3

SEQUOYAH UNITS 1 AND 2 TRM 8.7.5 TECHNICAL REQUIREMENTS MANUAL Revision 61 February 21, 2019 BASES APPLICABILITY Cooling for the Electric Board Rooms, Shutdown Board Rooms, 480 V Electric Board Rooms and ventilation to the 480 V Transformer Rooms is required for all MODES due to the commonality of the equipment served, requirements for accident mitigation, and the ability to cross tie the 480V board room cooling between Units 1 & 2. Cooling to the Thermal Barrier Booster Pump & Spent Fuel Pit Pump Area is only required in MODES 1, 2, 3, and 4 for the applicable Unit.

CONTINGNECY With any of the equipment listed in Table 8.7.5-1 Nonfunctional, the MEASURES corresponding TR for that Unit and Train of equipment shall be entered into the Operation narrative logs and LCO tracking logs for tracking the unavailability time.

TECHNICAL This TR is for tracking purposes only. There are no Technical REQUIREMENTS Requirements Verification associated with this TR.

VERIFICATION REFERENCES 1. NPG-SPP-03.4, Maintenance Rule Performance Indicator Monitoring, Trending and Reporting - 10 CFR 50.65.

2. TI-4, Maintenance Rule Performance Indicator Monitoring, Trending, and Reporting - 10 CFR 50.65. Attachment 7, Heating, Ventilation and Air Conditioning - System 30.

3. SQN-DC-V-21.0, Sequoyah Nuclear Plant - Environmental Design Criteria.

8.7.5-4

SEQUOYAH UNITS 1 AND 2 TRM 8.7.6 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.6 Explosive Gas Mixtures TECHNICAL REQUIREMENT (TR)

TR 8.7.6 The concentration of oxygen in the waste gas holdup system shall be limited to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY: At all times.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. Oxygen concentration in A.1 Reduce oxygen 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months a waste gas holdup tank concentration to within is > 2% by volume and limit.

4% by volume.

B. Oxygen concentration in B.1 Suspend additions of Immediately a waste gas holdup tank waste gases to the is > 4% by volume and affected waste gas holdup hydrogen concentration tank.

> 2% by volume.

AND B.2 Reduce the oxygen Immediately concentration to 2% by volume.

C. Required Contingency C.1 Evaluate in accordance Immediately Measures and with TR 7.5.3.

associated Restoration Time of Condition A or B not met.

8.7.6-1

SEQUOYAH UNITS 1 AND 2 TRM 8.7.6 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.7.6.1 Verify hydrogen and oxygen concentrations are within Continuously limits with the monitors required FUNCTIONAL by TR 8.3.5.

8.7.6-2

SEQUOYAH UNITS 1 AND 2 TRM 8.7.6 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.6 Explosive Gas Mixture BASES BACKGROUND This requirement is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

8.7.6-3

SEQUOYAH UNITS 1 AND 2 TRM 8.7.7 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.7 Liquid Holdup Tanks TECHNICAL REQUIREMENT (TR)

TR 8.7.7 The quantity of radioactive material contained in the following tanks shall be limited by the following expression:

concentration of isotope i i

(effluent concentration 6,700 limit of isotope i) excluding tritium and dissolved or entrained noble gases.

a. Condensate Storage Tank

b. Steam Generator Layup Tank

c. Outside temporary tanks for radioactive liquid.

APPLICABILITY: At all times.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. The quantity of A.1 Suspend additions of Immediately radioactive material radioactive material to the exceeding the above tank.

limit.

AND A.2 Reduce tank contents to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months within limits.

8.7.7-1

SEQUOYAH UNITS 1 AND 2 TRM 8.7.7 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.7.7.1 Verify the quantity of radioactive material contained in Every 7 days when each tank is within the limit by analyzing a radioactive materials representative sample of the tanks contents. are being added to the tank.

8.7.7-2

SEQUOYAH UNITS 1 AND 2 TRM 8.7.7 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.7 Liquid Holdup Tanks BASES BACKGROUND Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

8.7.7-3

SEQUOYAH UNITS 1 AND 2 TRM 8.7.8 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.8 Gas Decay Tanks TECHNICAL REQUIREMENT (TR)

TR 8.7.8 The quantity of radioactivity contained in each gas decay tank shall be 50,000 curies noble gases (considered as Xe-133).

APPLICABILITY: At all times.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. Quantity of radioactive A.1 Suspend additions of Immediately material contained in radioactive material to the tank not within limits. tank.

AND A.2 Reduce tank contents 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months within limits.

B. Required Contingency B.1 Evaluate in accordance Immediately Measures and with TR 7.5.3.

associated Restoration Time of Condition A not met.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.7.8.1 Verify the quantity of radioactive material contained in Every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when each gas decay tank is within the limit. radioactive materials are being added to the tank.

8.7.8-1

SEQUOYAH UNITS 1 AND 2 TRM 8.7.8 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.8 Gas Decay Tanks BASES BACKGROUND Restricting the quantity of radioactivity contained in each gas decay tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure."

8.7.8-2

SEQUOYAH UNITS 1 AND 2 TRM 8.7.9 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.9 Ventilation Filter Testing TECHNICAL REQUIREMENT (TR)

TR 8.7.9 Engineered Safety Feature (ESF) charcoal adsorber(s) shall be within limits per Technical Specification 5.5.9.

APPLICABILITY: Whenever the charcoal adsorber(s) is required to be OPERABLE.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. TRV 8.7.9.1 is not met. A.1 Evaluate per Technical Immediately Specification 5.5.9.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.7.9.1 Verify by laboratory analysis carbon sample is within Once within 31 days limit. after removal of carbon sample.

8.7.9-1

SEQUOYAH UNITS 1 AND 2 TRM 8.7.9 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.7 PLANT SYSTEMS 8.7.9 Ventilation Filter Testing BASES BACKGROUND None 8.7.9-2

SEQUOYAH UNITS 1 AND 2 TRM 8.8.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.8 ELECTRICAL POWER SYSTEMS 8.8.1 Containment Penetration Conductor Overcurrent Protective Devices TECHNICAL REQUIREMENT (TR)

TR 8.8.1 Primary and backup containment penetration conductor overcurrent protective devices associated with each containment electrical penetration circuit for those circuits that exceed their credible fault currents design rating shall be FUNCTIONAL.

APPLICABILITY: MODES 1, 2, 3, and 4.

CONTINGENCY MEASURES

NOTE--------------------------------------------------------------------

Separate Condition entry is allowed for each containment penetration conductor overcurrent protective device.

CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One or more required A.1 Evaluate in accordance Immediately containment penetration with TR 7.5.3.

conductor overcurrent protective devices AND Nonfunctional.

A.2 Isolate circuit(s) by de-energizing the primary 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or backup isolation device.

AND A.3 Verify circuit is de- Once per 7 days energized by breaker opened or fuses removed where applicable.

8.8.1-1

SEQUOYAH UNITS 1 AND 2 TRM 8.8.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.8.1.1 -----------------------------NOTE------------------------------------

For at least one 6.9 kV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated FUNCTIONAL at least once per 72 months.

Perform CHANNEL CALIBRATION on at least one 18 months reactor coolant pump associated protective relays specified in appropriate plant instructions.

8.8.1.2 -----------------------------NOTE------------------------------------

For at least one 6.9 kV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated FUNCTIONAL at least once per 72 months.

For each circuit breaker found Nonfunctional during the test, an additional representative sample of at least 1 of the circuit breakers of the Nonfunctional type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

Perform integrated system functional test on at least 18 months one reactor coolant pump which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed.

8.8.1-2

SEQUOYAH UNITS 1 AND 2 TRM 8.8.1 TECHNICAL REQUIREMENTS MANUAL Revision 58 April 24, 2017 TRV VERIFICATION FREQUENCY 8.8.1.3 -----------------------------NOTE------------------------------------

Testing shall consist of injecting a current input at the specified setpoint to each selected circuit breaker and verifying that each circuit breaker functions as designed.

Circuit breakers found Nonfunctional during functional testing shall be restored to FUNCTIONAL status prior to resuming operation.

Perform functional test of each low voltage circuit In accordance with breaker in accordance with procedures prepared in 0-TI-SBR-000-001.0 conjunction with manufacturers recommendations.

8.8.1.4 Deleted 8.8.1-3

SEQUOYAH UNITS 1 AND 2 TRM 8.8.1 TECHNICAL REQUIREMENTS MANUAL Revision 58 April 24, 2017 TRV VERIFICATION FREQUENCY 8.8.1.5 Perform an inspection and preventive maintenance on In accordance with each non-molded case circuit breaker in accordance 0-TI-SBR-000-001.0 with procedures prepared in conjunction with manufacturer's recommendations.

8.8.1.6 Perform an inspection and preventive maintenance on In accordance with each molded case circuit breaker in accordance with 0-TI-SBR-000-001.0 procedures prepared in conjunction with manufacturer's recommendations.

8.8.1-4

SEQUOYAH UNITS 1 AND 2 TRM 8.8.1 TECHNICAL REQUIREMENTS MANUAL Revision 58 April 24, 2017 8.8 ELECTRICAL POWER SYSTEMS 8.8.1 Containment Penetration Conductor Overcurrent Protective Devices BASES BACKGROUND Containment electrical penetrations and penetration conductors are protected by either de-energizing circuits not required during reactor operation or by demonstrating the FUNCTIONALITY of primary and backup overcurrent protection circuit breakers during periodic performance of Technical Requirements Verification (TRV).

The TRVs applicable to lower voltage circuit breakers and fuses provide assurance of breaker and fuse reliability by testing circuit breakers and inspecting fuses. Each molded case and non-molded case circuit breaker will be tested at a frequency established by considering applicable maintenance history as well as manufacturer and industry guidelines.

Inspection of fuses and their holders will be performed in accordance with TVAs fuse control procedure each time fuses are manipulated to ensure:

(1) that the proper size fuse is installed, (2) that the fuse shows no sign of deteriorations, (3) that the fuse connections are tight and clean (See IEEE Std 242-1975, Recommended Practice for Protection and coordination of Industrial and Commercial Power Systems). Should a problem be identified during inspection or should a problem arise with a specific brand or model of fuse, necessary corrective actions should be initiated through the plants Corrective Action Program.

TECHNICAL The Primary and backup containment penetration conductor overcurrent REQUIREMENT protective devices excludes those circuits for which credible fault current would not exceed the electrical penetration design rating.

8.8.1-5

SEQUOYAH UNITS 1 AND 2 TRM 8.8.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.8 ELECTRICAL POWER SYSTEMS 8.8.2 Motor Operated Valves Thermal Overload Protection TECHNICAL REQUIREMENT (TR)

TR 8.8.2 The thermal overload protection devices, integral with the motor starter, of each valve used in safety systems shall be FUNCTIONAL.

APPLICABILITY: Whenever the motor operated valve is required to be OPERABLE.

CONTINGENCY MEASURES

NOTE--------------------------------------------------------------------

Separate Condition entry is allowed for each thermal overload protection device.

CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One or more required A.1 Declare the valve(s) Immediately thermal overload INOPERABLE.

protection device(s)

Nonfunctional. AND A.2 Evaluate Technical Immediately Specifications and enter appropriate Action(s).

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.8.2.1 Perform CHANNEL CALIBRATION of a representative 18 months sample of at least 25% of all thermal overload devices which are not bypassed, such that each non-bypassed device is calibrated at least once per 6 years.

8.8.2.2 Perform CHANNEL FUNCTIONAL TEST of the bypass 18 months circuitry for those thermal overload devices which are normally in force during plant operation and bypassed under accident conditions.

8.8.2-1

SEQUOYAH UNITS 1 AND 2 TRM 8.8.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.8 ELECTRICAL POWER SYSTEMS 8.8.2 Motor Operated Valves Thermal Overload Protection BASES BACKGROUND The FUNCTIONALITY of the motor operated valves thermal overload protection devices ensures that the thermal overload protection devices will not prevent safety related valves from performing their function. The Technical Requirements Verification for demonstrating the FUNCTIONALITY of these devices are in accordance with Regulatory Guide 1.106 "Thermal Overload Protection for Electrical Motors on Motor Operated Valves," Revision 1, March 1977.

8.8.2-2

SEQUOYAH UNITS 1 AND 2 TRM 8.8.3 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.8 ELECTRICAL POWER SYSTEMS 8.8.3 Isolation Devices TECHNICAL REQUIREMENT (TR)

TR 8.8.3 All circuit breakers actuated by fault currents that are used as isolation devices protecting IE busses from non qualified loads shall be FUNCTIONAL.

APPLICABILITY: MODE 1, 2, 3 and 4.

CONTINGENCY MEASURES

NOTE--------------------------------------------------------------------

Separate Condition entry is allowed for each circuit breaker.

CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One or more required A.1 --------------NOTE---------------

circuit breaker(s) Molded cased breakers do Nonfunctional. not have a rack-out function.

Trip and rack-out 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Nonfunctional circuit breaker(s).

AND A.2 Verify Nonfunctional circuit Once per 7 days breaker(s) is tripped.

B. Required Contingency B.1 Evaluate in accordance with Immediately Measures and TR 7.5.3.

associated Restoration Time of Condition A not met.

8.8.3-1

SEQUOYAH UNITS 1 AND 2 TRM 8.8.3 TECHNICAL REQUIREMENTS MANUAL Revision 58 April 24, 2017 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.8.3.1 ----------------------------NOTES-----------------------------------

1. Functional testing shall consists of injecting a current input at the specified setpoint to each selected circuit breaker or relay and verifying it functions as designed.

Perform functional test of each low voltage circuit breaker in accordance with procedures prepared in In accordance with conjunction with manufacturers recommendations. 0-TI-SBR-000-001.0 8.8.3.2 Perform inspection and preventive maintenance on In accordance with each non-molded case circuit breaker in accordance 0-TI-SBR-000-001.0 with procedures prepared in conjunction with manufacturer's recommendations.

8.8.3.3 Perform inspection and preventive maintenance on In accordance with each molded case circuit breaker in accordance with 0-TI-SBR-000-001.0 procedures prepared in conjunction with manufacturer's recommendations.

8.8.3-2

SEQUOYAH UNITS 1 AND 2 TRM 8.8.3 TECHNICAL REQUIREMENTS MANUAL Revision 58 April 24, 2017 8.8 ELECTRICAL POWER SYSTEMS 8.8.3 Isolation Devices BASES BACKGROUND Circuit breakers actuated by faulted currents are used as isolation devices in this plant. The FUNCTIONALITY of these circuit breakers ensures that the IE busses will be protected in the event of faults in nonqualified loads powered by the busses.

The testing requirements applicable to lower voltage circuit breakers provides assurance of breaker reliability by testing circuit breakers. Each molded case and non-molded case circuit breaker will be tested at a frequency established by considering applicable maintenance history as well as manufacturer and industry guidelines.

8.8.3-3

SEQUOYAH UNITS 1 AND 2 TRM 8.8.4 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.8 ELECTRICAL POWER SYSTEMS 8.8.4 Emergency Diesel Generator (EDG) Fuel Oil Storage Tanks TECHNICAL REQUIREMENT (TR)

TR 8.8.4 The Emergency Diesel Generator Fuel Oil Storage Tanks shall be FUNCTIONAL.

APPLICABILITY: When associated EDG is required to be OPERABLE.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. TRV 8.8.4.1 not met. A.1 Evaluate in accordance Immediately with TR 7.5.3.

AND A.2 Evaluate EDG(s) for Immediately OPERABILITY requirements of Technical Specification 3.8.3.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.8.4.1 For each emergency diesel generator fuel oil storage 10 years tank perform the following:

a. Drain fuel oil,

b. Remove accumulated sediment, and

c. Clean the tank.

8.8.4-1

SEQUOYAH UNITS 1 AND 2 TRM 8.8.4 TECHNICAL REQUIREMENTS MANUAL Revision 57 January 27, 2017 8.8 ELECTRICAL POWER SYSTEMS 8.8.4 Emergency Diesel Generator Fuel Oil Storage Tanks BASES BACKGROUND A description of the diesel generator fuel oil 7-day storage tank is provided in the Bases for Technical Specification (TS) LCO 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air.

APPLICABLE The Applicable Safety Analyses section for the Bases of TS LCO 3.8.3 SAFETY also applies to this TR.

ANALYSES TECHNICAL TR 8.8.4 specifies preventive maintenance to ensure proper quality of REQUIREMENT the fuel oil.

APPLICABILITY TR 8.8.4 is consistent with TS LCO 3.8.3.

CONTINGENCY A.1 MEASURES This Contingency Measure is entered to evaluate a failure to perform tank cleaning.

A.2 Failure to perform tank cleaning could challenge the assurance of adequate fuel oil quality for proper operation of the diesel generators.

TECHNICAL TRV 8.8.4.1 REQUIREMENTS VERIFICATION Draining of the fuel oil stored in the supply tanks (i.e., 7-Day Tanks),

removal of accumulated sediment, and tank cleaning are required at 10-year intervals by Regulatory Guide 1.137 (Reference 2), paragraph 2.f. This TRV is for preventive maintenance. The presence of sediment does not necessarily represent a failure of this TRV, provided that accumulated sediment is removed during the performance of the verification.

8.8.4-2

SEQUOYAH UNITS 1 AND 2 TRM 8.8.4 TECHNICAL REQUIREMENTS MANUAL Revision 57 January 27, 2017 BASES REFERENCES 1. UFSAR, Section 9.5.4

2. Regulatory Guide 1.137 Fuel-Oil Systems for Standby Diesel Generators, Revision 1, October 1979.

8.8.4-3

SEQUOYAH UNITS 1 AND 2 TRM 8.9.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.9 REFUELING OPERATIONS 8.9.1 Communications TECHNICAL REQUIREMENT (TR)

TR 8.9.1 Direct communications shall be maintained between the control room and personnel at the refueling station.

APPLICABILITY: During CORE ALTERATIONS.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. Direct communications A.1 Suspend CORE Immediately between the control ALTERATIONS.

room and personnel at the refueling station not maintained.

TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.9.1.1 Verify direct communications between the control room Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to and personnel at the refueling station. the start of CORE ALTERATIONS AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter 8.9.1-1

SEQUOYAH UNITS 1 AND 2 TRM 8.9.1 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.9 REFUELING OPERATIONS 8.9.1 Communications BASES BACKGROUND The requirements 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.

8.9.1-2

SEQUOYAH UNITS 1 AND 2 TRM 8.9.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.9 REFUELING OPERATIONS 8.9.2 Manipulator Crane TECHNICAL REQUIREMENT (TR)

TR 8.9.2 The manipulator crane and auxiliary hoist shall be used for movement of drive rods or fuel assemblies and shall be FUNCTIONAL with:

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

1. A capacity of 2750 pounds; and

2. An overload cut off limit of 2700 pounds.

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

1. A capacity of 610 pounds; and

2. A load indicator which shall be used to prevent lifting loads

> 600 pounds.

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

NOTE--------------------------------------------------------------------

Separate Condition entry is allowed for each unit.

CONTINGENCY MEASURES CONDITION CONTINGENCY MEASURES RESTORATION TIME A. One manipulator crane A.1 Suspend use of Immediately and/or auxiliary hoist NONFUNCTIONAL crane Nonfunctional. and/or hoist from operations involving the movement of drive rods and fuel assemblies within the reactor pressure vessel.

8.9.2-1

SEQUOYAH UNITS 1 AND 2 TRM 8.9.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 TECHNICAL REQUIREMENTS VERIFICATION TRV VERIFICATION FREQUENCY 8.9.2.1 For each manipulator crane used for movement of fuel Once within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months assemblies within the reactor pressure vessel, perform prior to start of a load test of 2750 pounds and verify an automatic movement of fuel overload cutoff when the crane load exceeds 2700 assemblies within the pounds. reactor pressure vessel 8.9.2.2 For each auxiliary hoist and associated load indicator Once within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months used for movement of drive rods within the reactor prior to start of pressure vessel, perform a hoist load test of 610 movement of drive rods pounds. within the reactor pressure vessel 8.9.2-2

SEQUOYAH UNITS 1 AND 2 TRM 8.9.2 TECHNICAL REQUIREMENTS MANUAL Revision 49 October 23, 2015 8.9 REFUELING OPERATIONS 8.9.2 Manipulator Crane BASES BACKGROUND The FUNCTIONALITY 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 pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

8.9.2-3

ML20304A403

Text

Subject:

References:

Enclosure:

Attachment:

6.0 INTRODUCTION

6.0 INTRODUCTION

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