Text

Issuance of Amendment Nos. 358 and 352 Regarding Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B
	ML22210A118
Person / Time
Site:	Sequoyah
Issue date:	08/24/2022
From:	David Wrona; Plant Licensing Branch II
To:	Jim Barstow; Tennessee Valley Authority
	Buckberg P
References
	EPID L-2021-LLA-0145
	Download: ML22210A118 (156)
	v • d • e

August 24, 2022 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801

SUBJECT:

SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 358 AND 352 REGARDING TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-505, REVISION 2, PROVIDE RISK-INFORMED EXTENDED COMPLETION TIMES - RITSTF INITIATIVE 4B (EPID L-2021-LLA-0145)

Dear Mr. Barstow:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 358 to Renewed Facility Operating License No. DPR-77, and Amendment No. 352 to Renewed Facility Operating License No. DPR-79, for the Sequoyah Nuclear Plant, Units 1 and 2, respectively. These amendments are in response to your application dated August 5, 2021, as supplemented by letters dates April 28, 2022, May 13, 2022, and July 1, 2022.

The amendment modifies technical specifications to permit the use of risk-informed completion times in accordance with Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, "Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b,"

J. Barstow (ADAMS Accession No. ML18183A493). A copy of our related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.

Sincerely,

/RA/

Perry H. Buckberg, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328

Enclosures:

1. Amendment No. 358 to DPR-77

2. Amendment No. 352 to DPR-79

3. Safety Evaluation cc: Listserv

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 358 Renewed License No. DPR-77

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Tennessee Valley Authority (the licensee) dated August 5, 2021, as supplemented by letters dates April 28, 2022, May 13, 2022, and July 1, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR)

Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

Enclosure 1

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-77 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 358 are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 180 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by David David J. J. Wrona Date: 2022.08.24 Wrona 15:12:16 -04'00' David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: August 24, 2022

ATTACHMENT TO LICENSE AMENDMENT NO. 358 SEQUOYAH NUCLEAR PLANT, UNIT 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace page 3 of the Renewed Facility Operating License with the attached page 3.

Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Page Insert Page 1.3-10 1.3-10

- 1.3-11 3.3.1-1 3.3.1-1 3.3.1-2 3.3.1-2 3.3.1-3 3.3.1-3 3.3.1-5 3.3.1-5 3.3.1-6 3.3.1-6 3.3.1-7 3.3.1-7 3.3.1-8 3.3.1-8 3.3.1-9 3.3.1-9 3.3.1-10 3.3.1-10 3.3.1-11 3.3.1-11 3.3.1-12 3.3.1-12 3.3.1-13 3.3.1-13 3.3.1-17 3.3.1-17 3.3.1-18 3.3.1-18 3.3.1-19 3.3.1-19 3.3.2-1 3.3.2-1 3.3.2-2 3.3.2-2 3.3.2-3 3.3.2-3 3.3.2-4 3.3.2-4 3.3.2-5 3.3.2-5 3.3.2-6 3.3.2-6 3.3.2-7 3.3.2-7 3.3.2-8 3.3.2-8 3.3.2-9 3.3.2-9 3.3.2-10 3.3.2-10 3.3.2-17 3.3.2-17 3.3.2-18 3.3.2-18 3.3.2-19 3.3.2-19 3.3.5-1 3.3.5-1

3.4.11-1 3.4.11-1 3.4.11-2 3.4.11-2 3.5.2-1 3.5.2-1 3.6.2-3 3.6.2-3 3.6.3-2 3.6.3-2 3.6.3-3 3.6.3-3 3.6.6-1 3.6.6-1 3.6.8-1 3.6.8-1 3.6.11-1 3.6.11-1 3.6.11-2 3.6.11-2 3.7.2-1 3.7.2-1 3.7.5-1 3.7.5-1 3.7.5-2 3.7.5-2 3.7.5-3 3.7.5-3 3.7.5-4 3.7.5-4 3.7.7-1 3.7.7-1 3.7.8-2 3.7.8-2 3.8.1-2 3.8.1-2 3.8.1-3 3.8.1-3 3.8.1-4 3.8.1-4 3.8.1-5 3.8.1-5 3.8.1-6 3.8.1-6 3.8.4-1 3.8.4-1 3.8.4-2 3.8.4-2 3.8.7-1 3.8.7-1 3.8.7-2 3.8.7-2 3.8.9-1 3.8.9-1 3.8.9-2 3.8.9-2 3.8.9-3 3.8.9-3 5.5-17 5.5-17

- 5.5-18

(3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the Sequoyah and Watts Bar Unit 1 Nuclear Plants.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 358 are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authoritys Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:

a. Elimination of any test identified in Section 14 of TVAs Final Safety Analysis Report as amended as being essential;

b. Modification of test objectives, methods, or acceptance criteria for any test identified in Section 14 of TVAs Final Safety Analysis Report as amended as being essential; Amendment No. 358 Renewed License No. DPR-77

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1.

If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by SR 3.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

EXAMPLE 1.3-8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore subsystem 7 days subsystem to OPERABLE inoperable. status. OR In accordance with the Risk Informed Completion Time Program B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion 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 When a subsystem is declared inoperable, Condition A is entered. The 7 day Completion Time may be applied as discussed in Example 1.3-2. However, the licensee may elect to apply the Risk Informed Completion Time Program which permits calculation of a Risk Informed Completion Time (RICT) that may be used to complete the Required Action beyond the 7 day Completion Time. The RICT cannot exceed 30 days. After the 7 day Completion Time has expired, the subsystem must be restored to OPERABLE status within the RICT or Condition B must also be entered.

SEQUOYAH - UNIT 1 1.3-10 Amendment 334, 358

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

The Risk Informed Completion Time Program requires recalculation of the RICT to reflect changing plant conditions. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the plant configuration change, whichever is less.

If the 7 day Completion Time clock of Condition A has expired and subsequent changes in plant condition result in exiting the applicability of the Risk Informed Completion Time Program without restoring the inoperable subsystem to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start.

If the RICT expires or is recalculated to be less than the elapsed time since the Condition was entered and the inoperable subsystem has not been restored to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable subsystems are restored to OPERABLE status after Condition B is entered, Condition A is exited, and therefore, the Required Actions of Condition B may be terminated.

IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action COMPLETION TIME should be pursued without delay and in a controlled manner.

SEQUOYAH - UNIT 1 1.3-11 Amendment 358

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.1-1 required channels or for the channel(s) or trains inoperable. train(s).

B. One Manual Reactor B.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Trip channel inoperable. OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program C. One channel or train C.1 Restore channel or train to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. OPERABLE status.

UOR C.2.1 Initiate action to fully insert 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months all rods.

UAND SEQUOYAH - UNIT 1 3.3.1-1 Amendment 334, 358

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2.2 Place the Rod Control 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months System in a condition incapable of rod withdrawal.

D. One Power Range -------------------NOTES------------------

Neutron Flux - High 1. The inoperable channel may be channel inoperable. bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing and setpoint adjustment of other channels.

2. Perform SR 3.2.4.2 if input to QPTR from one or more Power Range Neutron Flux channels are inoperable with THERMAL POWER > 75% RTP.

D.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.3.1-2 Amendment 334 343, 358

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One channel inoperable. -------------------NOTE--------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

E.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR In accordance with the Risk Informed Completion Time Program F. One Intermediate Range F.1 Reduce THERMAL 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Neutron Flux channel POWER to < P-6.

inoperable.

UOR F.2 Increase THERMAL 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months POWER to > P-10.

G. Two Intermediate Range G.1 --------------NOTE--------------

Neutron Flux channels Limited plant cooldown or inoperable. boron dilution is allowed provided the change is accounted for in the calculated SDM.

Suspend operations Immediately involving positive reactivity additions.

UAND G.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to < P-6.

SEQUOYAH - UNIT 1 3.3.1-3 Amendment 334, 358

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME K. One channel -------------------NOTE---------------------

inoperable. The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

K.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR In accordance with the Risk Informed Completion Time Program L. Required Action and L.1 Reduce THERMAL POWER 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated to < P-7.

Completion Time of Condition K not met.

M. One Turbine Trip -------------------NOTE---------------------

channel inoperable. The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

M.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR In accordance with the Risk Informed Completion Time Program N. Required Action and N.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated to < P-9.

Completion Time of Condition M not met.

SEQUOYAH - UNIT 1 3.3.1-5 Amendment 334, 358

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME O. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

O.1 Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program P. One reactor trip breaker --------------------NOTE-------------------

train inoperable. One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing, provided the other train is OPERABLE.

P.1 Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program Q. One or more channels Q.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit conditions.

R. One or more channels R.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit conditions.

SEQUOYAH - UNIT 1 3.3.1-6 Amendment 334, 358

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME S. Required Action and S.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition R not met.

T. One trip mechanism --------------------NOTE-------------------

inoperable for one The reactor trip breaker train shall reactor trip breaker. not be bypassed while one of the diverse trip features is inoperable except for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for performing maintenance to restore the breaker to OPERABLE status T.1 Restore trip mechanism to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program U. One channel inoperable. -------------------NOTE--------------------

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

U.1 For the affected protection 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months set, adjust the Trip Time Delay for one affected steam generator (T S ) toR R match the Trip Time Delay for multiple affected steam generators (T M ).R R UAND SEQUOYAH - UNIT 1 3.3.1-7 Amendment 334, 358

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME U.2 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR In accordance with the Risk Informed Completion Time Program V. One channel inoperable. V.1 For the affected protection 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months set, adjust the Steam Generator Water Level -

Low-Low (EAM) channels trip setpoint to the same value as Steam Generator Water Level - Low-Low (Adverse).

UOR V.2 For the affected protection 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months set, place the Steam Generator Water level--Low- OR Low channel(s) in trip.

In accordance with the Risk Informed Completion Time Program W. One channel inoperable. W.1 For the affected protection 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months set, adjust the Trip Time Delays (T S and T M )

R R R R threshold power level for zero seconds time delay to 0% RTP.

UOR SEQUOYAH - UNIT 1 3.3.1-8 Amendment 334, 358

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME W.2 For the affected protection 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months set, place the Steam Generator Water Level-- OR Low-Low channel(s) in trip.

In accordance with the Risk Informed Completion Time Program X. Required Action and X.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition B, D, E, O, P, Q, T, U, V, or W not met.

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2 -----------------------------NOTE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is 15% RTP.

Compare results of calorimetric heat balance In accordance calculation to power range channel output. Adjust with the power range channel output if absolute difference is Surveillance

> 2%. Frequency Control Program (continued)

SEQUOYAH - UNIT 1 3.3.1-9 Amendment 334, 356, 358

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.3 -----------------------------NOTE-------------------------------

Not required to be performed until 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after THERMAL POWER is 15% RTP.

Compare results of the core power distribution In accordance measurements to Nuclear Instrumentation System with the (NIS) AFD. Adjust NIS channel if absolute Surveillance difference is 3%. Frequency Control Program SR 3.3.1.4 ------------------------------NOTE-------------------------------

This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in service.

Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.5 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.6 ------------------------------NOTE-------------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is 50% RTP.

Calibrate excore channels to agree with core power In accordance distribution measurements. with the Surveillance Frequency Control Program (continued)

SEQUOYAH - UNIT 1 3.3.1-10 Amendment 334, 356, 358

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.7 ------------------------------NOTE-------------------------------

Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entry into MODE 3.

Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.8 ------------------------------NOTE-------------------------------

This Surveillance shall include verification that interlocks P-6 and P-10 are in their required state for existing unit conditions.

Perform COT. --------NOTE--------

Only required when not performed within the Frequency specified in the Surveillance Frequency Control Program Prior to reactor startup AND 0B Four hours after reducing power below P-6 for source range instrumentation AND 1B (continued)

SEQUOYAH - UNIT 1 3.3.1-11 Amendment 334, 358

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY Twelve hours after reducing power below P-10 for power and intermediate range instrumentation AND 2B In accordance with the Surveillance Frequency Control Program SR 3.3.1.9 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.10 ------------------------------NOTE-------------------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program (continued)

SEQUOYAH - UNIT 1 3.3.1-12 Amendment 334, 358

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.11 ------------------------------NOTE-------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.12 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.13 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

Perform TADOT. Prior to exceeding the P-9 interlock whenever the unit has been in MODE 3, if not performed within the previous 31 days SR 3.3.1.14 ------------------------------NOTE-------------------------------

Neutron detectors are excluded from response time testing.

Verify RTS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SEQUOYAH - UNIT 1 3.3.1-13 Amendment 334, 358

RTS Instrumentation 3.3.1 40TTable 3.3.1-1 (page 4 of 9) 40TReactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

12. Underfrequency 1 (g)

P 1 per bus K SR 3.3.1.9 56.973 Hz 57.0 Hz RCPs SR 3.3.1.10 (b)(c)

P SR 3.3.1.14

13. Steam Generator (SG) Water Level

a. Low-Low 1,2 3 per SG U SR 3.3.1.1 14.4% NR 15.0% NR (Adverse) SR 3.3.1.7 (b)(c)

P Span Span SR 3.3.1.10 (b)(c)

P SR 3.3.1.14 Coincident with 1,2 4 V SR 3.3.1.1 0.6 psig 0.5 psig Containment SR 3.3.1.7 (b)(c)

P Pressure (EAM) SR 3.3.1.10 (b)(c)

P SR 3.3.1.14 and 1,2 4 W SR 3.3.1.1 RCS Loop T RCS Loop T RCS Loop T SR 3.3.1.7 (b)(c)

P variable input variable input SR 3.3.1.10 (b)(c)

P nominal trip 50% RTP SR 3.3.1.14 setpoint +

2.5% RTP with (1.01)T SR R T S (Note 3)

R R Time Delay (Note 3)

T S if one R R SG is affected or (1.01)T m R R T m (Note 3)

R R Time Delay (Note 3)

T m if two or R R more SGs are affected (b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and as-left tolerances are specified in UFSAR, Section 7.1.2.

(g) Above the P-7 (Low Power Reactor Trips Block) interlock.

SEQUOYAH - UNIT 1 3.3.1-17 Amendment 334, 358

RTS Instrumentation 3.3.1 40TTable 3.3.1-1 (page 5 of 9) 40TReactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

b. Low-Low 1,2 3 per SG U SR 3.3.1.1 10.1% NR 10.7% NR (EAM) SR 3.3.1.7 (b)(c)

P Span Span SR 3.3.1.10 (b)(c)

P SR 3.3.1.14 Coincident with 1,2 4 W SR 3.3.1.1 RCS Loop T RCS Loop T RCS Loop T SR 3.3.1.7 (b)(c)

P variable input variable input SR 3.3.1.10 (b)(c)

P nominal trip 50% RTP SR 3.3.1.14 setpoint +

2.5% RTP with (1.01)T SR R T S (Note 3)

R R Time Delay (Note 3)

T S if one R R SG is affected or (1.01)T m R R T m (Note 3)

R R Time Delay (Note 3)

T m if two or R R more SGs are affected

14. Turbine Trip

a. Low Fluid Oil 1 (h)

P 3 M SR 3.3.1.10 (b)(c)

P 710 psig 800 psig Pressure SR 3.3.1.13

b. Turbine Stop 1 (h)

P 4 M SR 3.3.1.10 1% open 1% open Valve Closure SR 3.3.1.13 O

15. Safety Injection (SI) 1,2 2 trains SR 3.3.1.12 NA NA Input from Engineered Safety Feature Actuation System (ESFAS)

(b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and as-left tolerances are specified in UFSAR, Section 7.1.2.

(h) Above the P-9 (Power Range Neutron Flux) interlock.

SEQUOYAH - UNIT 1 3.3.1-18 Amendment 334, 349, 358

RTS Instrumentation 3.3.1 40TTable 3.3.1-1 (page 6 of 9) 40TReactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

16. Reactor Trip System Interlocks

a. Intermediate 2 (f)

P 2 Q SR 3.3.1.11 6 x 10 -5 % RTP P P 1 x 10 -4 %

P P Range Neutron RTP Flux, P-6

b. Low Power 1 1 per train R SR 3.3.1.5 NA NA Reactor Trips Block, P-7

c. Power Range 1 4 R SR 3.3.1.11 37.4% RTP 35% RTP Neutron Flux, P-8

d. Power Range 1 4 R SR 3.3.1.11 52.4% RTP 50% RTP Neutron Flux, P-9

e. Power Range 1,2 4 Q SR 3.3.1.11 7.6% RTP and 10% RTP Neutron Flux, 12.4% RTP P-10

f. Turbine Impulse 1 2 R SR 3.3.1.10 12.4% 10% turbine Pressure, P-13 turbine power power

17. Reactor Trip 1,2 2 trains P SR 3.3.1.4 NA NA Breakers (i)

P P 3 (a) , 4 (a) , 5 (a)

P P P P P 2 trains C SR 3.3.1.4 NA NA

18. Reactor Trip Breaker 1,2 1 each per T SR 3.3.1.4 NA NA Undervoltage and reactor trip Shunt Trip breaker Mechanisms 3 (a) , 4 (a) , 5 (a)

P P P P P 1 each per C SR 3.3.1.4 NA NA reactor trip breaker

19. Automatic Trip Logic 1,2 2 trains O SR 3.3.1.5 NA NA 3 (a) , 4 (a) , 5 (a)

P P P P P 2 trains C SR 3.3.1.5 NA NA (a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(f) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(i) Including any reactor trip bypass breakers that are racked in and closed for bypassing a reactor trip breaker.

SEQUOYAH - UNIT 1 3.3.1-19 Amendment 334, 358

ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.2-1 required channels or for the channel(s) or trains inoperable. train(s).

B. One channel or train B.1 Restore channel or train to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.3.2-1 Amendment 334, 358

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

C.1 Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program D. One channel inoperable. -------------------NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

D.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.3.2-2 Amendment 334, 358

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One Containment -------------------NOTE-------------------

Pressure channel One additional channel may be inoperable. bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

E.1 Place channel in bypass. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months F. One channel inoperable. F.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time OR Program F.2 Declare the associated 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Main Steam Isolation Valve inoperable.

G. One channel or train G.1 Restore channel or train to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. OPERABLE status.

SEQUOYAH - UNIT 1 3.3.2-3 Amendment 334, 358

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

H.1 Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program I. One channel inoperable. -------------------NOTE-------------------

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

I.1 For the affected protection 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months set, the Trip Time Delay for one affected steam generator (TS) is adjusted to match the Trip Time Delay for multiple affected steam generators (TM).

AND I.2 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.3.2-4 Amendment 334, 358

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J. One channel inoperable. J.1 For the affected protection 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months set, adjust the Steam Generator Water Level -

Low-Low (EAM) channels trip setpoint to the same value as Steam Generator Water Level -- Low-Low (Adverse).

OR J.2 For the affected protection 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months set, place the Steam Generator Water Level--

Low-Low channel(s) in trip.

K. One channel inoperable. K.1 For the affected protection 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months set, adjust the Trip Time Delays (TS and TM) threshold power level for zero seconds time delay to 0% RTP.

OR K.2 For the affected protection 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months set, place the Steam Generator Water level-- OR Low-Low channel(s) in trip.

In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.3.2-5 Amendment 334, 358

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. One voltage sensor L.1 Restore the inoperable 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months channel inoperable. channel to OPERABLE status. OR In accordance with the Risk Informed Completion Time OR Program L.2 Declare the associated 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months auxiliary feedwater pump inoperable.

M. Two or more voltage M.1.1 Restore all but one voltage 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months sensor channels sensor channel to an inoperable. OPERABLE status.

OR AND One required load shed M.1.2 Restore required load shed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months timer channel timer channel to an inoperable. OPERABLE status.

OR M.2 Declare the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months auxiliary feedwater pump inoperable.

SEQUOYAH - UNIT 1 3.3.2-6 Amendment 334, 358

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME N. One Main Feedwater -------------------NOTE-------------------

Pumps trip channel One channel may be inoperable inoperable. during MODE 1 for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when placing the second main feedwater (MFW) pump in service or removing one of two MFW pumps from service.

N.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program O. Required Action and O.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition N not met.

P. One channel P.1 Declare the associated Immediately inoperable. auxiliary feedwater pump inoperable.

Q. One channel ------------------NOTE-------------------

inoperable. One additional channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing.

Q.1 Place channel in bypass. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months R. One or more channels R.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit condition.

SEQUOYAH - UNIT 1 3.3.2-7 Amendment 334, 358

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME S. Required Action and S.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Conditions B, AND C, or Q not met.

S.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months T. Required Action and T.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Conditions D, AND E, G, H, I, J, K, or R not met. T.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months U. One train inoperable. --------------------NOTE------------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

U.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND U.2 Be in MODE 5. 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function.

SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SEQUOYAH - UNIT 1 3.3.2-8 Amendment 334, 358

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.2 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.3 Perform MASTER RELAY TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.4 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.5 Perform SLAVE RELAY TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.6 ------------------------------NOTE-----------------------------

Verification of relay setpoints not required.

Perform TADOT. In accordance with the Surveillance Frequency Control Program SEQUOYAH - UNIT 1 3.3.2-9 Amendment 334, 358

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.7 ------------------------------NOTE-----------------------------

Verification of setpoint not required for manual initiation functions.

Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.8 ------------------------------NOTE-----------------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.2.9 ------------------------------NOTE-----------------------------

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after SG pressure is 842 psig.

Verify ESFAS RESPONSE TIMES are within limit. In accordance with the Surveillance Frequency Control Program SR 3.3.2.10 ------------------------------NOTE-----------------------------

Verification of setpoint not required.

Perform TADOT. Once per reactor trip breaker cycle SEQUOYAH - UNIT 1 3.3.2-10 Amendment 334, 358

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 7 of 9)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

6. Auxiliary Feedwater

c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

d. Loss of Offsite Power (1) Voltage Sensors 1,2,3 3 per L,M SR 3.3.2.6 Refer to Function 1 of Table shutdown SR 3.3.2.8(b)(c) 3.3.5-1 for setpoints and board(j) SR 3.3.2.9 allowable values.

(2) Load Shed Timer 1,2,3 1 per M SR 3.3.2.8(b)(c) Refer to Function 1 of Table shutdown SR 3.3.2.9 3.3.5-1 for setpoints and board(j) allowable values.

e. Trip of all Main 1,2(k) 1 per N SR 3.3.2.7 NA NA Feedwater pump SR 3.3.2.9 Pumps

f. Auxiliary 1,2,3 3 per P SR 3.3.2.8(b)(c) 2.44 psig 3.21 psig Feedwater Pump pump (motor driven (motor driven Suction Transfer pump) pump) on Suction 12 psig 13.9 psig Pressure - Low (turbine driven (turbine driven pump) pump)

(b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and as-left tolerances are specified in UFSAR, Section 7.1.2.

(j) Unit 1 shutdown boards only.

(k) When one or more Main Feedwater Pump(s) are supplying feedwater to steam generators.

SEQUOYAH - UNIT 1 3.3.2-17 Amendment 334, 358

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 8 of 9)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

6. Auxiliary Feedwater

g. Auxiliary Feedwater Suction Transfer Time Delays (1) Motor-Driven 1,2,3 1 per pump P SR 3.3.2.8(b)(c) 4.4 seconds 4 seconds Pump and 3.6 seconds (2) Turbine-Driven 1,2,3 2 per pump P SR 3.3.2.8(b)(c) 6.05 5.5 seconds Pump seconds and 4.95 seconds

7. Automatic Switchover to Containment Sump

a. Automatic 1,2,3,4 2 trains U SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

b. RWST Level - 1,2,3,4 4 Q SR 3.3.2.1 132.71" and 130" from Low SR 3.3.2.4(b)(c) 127.29" from tank base SR 3.3.2.8(b)(c) tank base SR 3.3.2.9 Coincident with Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Safety Injection and Coincident with 1,2,3,4 4 Q SR 3.3.2.1 31.68 in. 30 in. above Containment SR 3.3.2.4(b)(c) and el. 680 ft Sump Level - SR 3.3.2.8(b)(c) 28.32 in.

SR 3.3.2.9 above el.

High 680 ft (b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and as-left tolerances are specified in UFSAR, Section 7.1.2.

SEQUOYAH - UNIT 1 3.3.2-18 Amendment 334, 358

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 9 of 9)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

8. ESFAS Interlocks

a. Reactor Trip, 1,2,3 1 per train, G SR 3.3.2.10 NA NA P-4 2 trains

b. Pressurizer Pressure, P-11/

Not P-11 (1) Not P-11, 1,2,3 3 R SR 3.3.2.8 1975.2 psig 1970 psig Automatic Unblock of Safety Injection on Increasing Pressure (2) P-11, 1,2,3 3 R SR 3.3.2.8 1956.8 psig 1962 psig Enable Manual Block of Safety Injection on Decreasing Pressure SEQUOYAH - UNIT 1 3.3.2-19 Amendment 334, 358

LOP DG Start Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation LCO 3.3.5 The LOP DG start instrumentation for each Function in Table 3.3.5-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore the inoperable 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one voltage sensor channel to OPERABLE channel inoperable. status. OR In accordance with the Risk Informed Completion Time Program B. One or more Functions B.1.1 Restore all but one voltage 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with two or more voltage sensor channel to sensor channels OPERABLE status.

inoperable.

AND OR B.1.2 Restore required timer to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months One or more Functions OPERABLE status.

with one required timer inoperable.

C. One or more unbalanced C.1 Restore unbalanced 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months voltage relays voltage relays to inoperable. OPERABLE status.

SEQUOYAH - UNIT 1 3.3.5-1 Amendment 334, 345, 358

Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each PORV and each block valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Close and maintain power 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable and capable to associated block valve.

of being manually cycled.

B. One PORV inoperable B.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not capable of being valve.

manually cycled.

AND B.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valve.

AND B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.4.11-1 Amendment 334, 358

Pressurizer PORVs 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve --------------------NOTE-------------------

inoperable. Required Actions C.1 and C.2 do not apply when block valve is inoperable solely as a result of complying with Required Action B.2 or E.2.

C.1 Place associated PORV in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months manual control.

AND C.2 Restore block valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B, AND or C not met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Two PORVs inoperable E.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not capable of being valves.

manually cycled.

AND E.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valves.

AND E.3 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND E.4 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SEQUOYAH - UNIT 1 3.4.11-2 Amendment 334, 358

ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.

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

1. In MODE 3, both safety injection (SI) pump flow paths may be isolated by closing the isolation valves for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to perform pressure isolation valve testing per SR 3.4.14.1.

2. In MODE 3, ECCS pumps may be made incapable of injecting to support transition into or from the Applicability of 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 Low Temperature Overpressure Protection (LTOP) arming temperature specified in the PTLR plus 25°F, whichever comes first.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more trains A.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. Less than 100% of the C.1 Enter LCO 3.0.3. Immediately ECCS flow equivalent to a single OPERABLE ECCS train available.

SEQUOYAH - UNIT 1 3.5.2-1 Amendment 334, 358

Containment Air Locks 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2 Lock an OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed in the affected air lock.

AND B.3 --------------NOTE--------------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify an OPERABLE door Once per 31 days is locked closed in the affected air lock.

C. One or more C.1 Initiate action to evaluate Immediately containment air locks overall containment inoperable for reasons leakage rate per LCO 3.6.1.

other than Condition A or B. AND C.2 Verify a door is closed in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the affected air lock.

AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SEQUOYAH - UNIT 1 3.6.2-3 Amendment 334, 358

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for flow paths with one penetration flow path by Category 1 or 8 CIVs containment isolation use of at least one closed valve inoperable for and de-activated automatic AND reasons other than valve, closed manual valve, Conditions E, F, and G. blind flange, or check valve 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for with flow through the valve Category 2 or 9 CIVs secured.

AND AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for Category 3 or 10 CIVs AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Category 4 or 11 CIVs AND 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for Category 5 or 12 CIVs AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for Category 6 or 13 CIVs AND 7 days for Category 7 or 14 CIVs OR In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.6.3-2 Amendment 334, 358

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2 -------------NOTES-------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is following isolation isolated. for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment B. ------------NOTE------------ B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with two containment and de-activated automatic isolation valves. valve, closed manual valve,

or blind flange.

One or more penetration flow paths with two containment isolation valves inoperable for reasons other than Conditions E, F, and G.

SEQUOYAH - UNIT 1 3.6.3-3 Amendment 334, 358

Containment Spray System 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray System LCO 3.6.6 Two containment spray subsystems shall be OPERABLE.

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

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

RHR spray trains are not required to be OPERABLE in MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment spray 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem inoperable. subsystem to OPERABLE status. OR In accordance with the Risk Informed Completion Time Program B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray train manual, power In accordance operated, and automatic valve in the flow path that with the is not locked, sealed, or otherwise secured in Surveillance position is in the correct position. Frequency Control Program SEQUOYAH - UNIT 1 3.6.6-1 Amendment 334, 358

HMS 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Hydrogen Mitigation System (HMS)

LCO 3.6.8 Two HMS trains shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One HMS train A.1 Restore HMS train to 7 days inoperable. OPERABLE status.

OR In accordance with the Risk Informed Completion Time OR Program A.2 Perform SR 3.6.8.1 on the Once per 7 days OPERABLE train.

B. One containment region B.1 Restore one hydrogen 7 days with no OPERABLE ignitor in the affected hydrogen ignitor. containment region to OR OPERABLE status.

In accordance with the Risk Informed Completion Time Program C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SEQUOYAH - UNIT 1 3.6.8-1 Amendment 334, 358

ARS 3.6.11 3.6 CONTAINMENT SYSTEMS 3.6.11 Air Return System (ARS)

LCO 3.6.11 Two ARS trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ARS train A.1 Restore ARS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion 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 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.11.1 Verify each ARS fan starts on an actual or simulated In accordance actuation signal, after a delay of 9.0 minutes and with the 11.0 minutes, and operates for 15 minutes. Surveillance Frequency Control Program SEQUOYAH - UNIT 1 3.6.11-1 Amendment 334, 358

ARS 3.6.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.11.2 Verify, with the ARS fan dampers closed, each ARS In accordance fan motor current is 24.5 amps and 39.5 amps. with the Surveillance Frequency Control Program SR 3.6.11.3 Verify, with the ARS fan not operating, each ARS In accordance fan damper opens when 68.1 in-lb of torque is with the applied to the counterweight. Surveillance Frequency Control Program SEQUOYAH - UNIT 1 3.6.11-2 Amendment 334, 358

MSIVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCO 3.7.2 Four MSIVs shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 except when all MSIVs are closed.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV inoperable in A.1 Restore MSIV to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months MODE 1. OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met.

C. ------------NOTE------------ C.1 Close MSIV. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Separate Condition entry is allowed for each AND MSIV.

C.2 Verify MSIV is closed. Once per 7 days One or more MSIVs inoperable in MODE 2 or 3.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C not AND met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SEQUOYAH - UNIT 1 3.7.2-1 Amendment 334, 358

AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE.

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

Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

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

LCO 3.0.4.b is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Turbine driven AFW A.1 Restore affected equipment 7 days train inoperable due to to OPERABLE status.

one inoperable steam OR supply.

In accordance with OR the Risk Informed Completion Time

NOTE------------ Program Only applicable if MODE 2 has not been entered following refueling.

One turbine driven AFW pump inoperable in MODE 3 following refueling.

SEQUOYAH - UNIT 1 3.7.5-1 Amendment 334, 358

AFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One AFW train B.1 Restore AFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable in MODE 1, OPERABLE status.

2, or 3 for reasons other OR than Condition A.

In accordance with the Risk Informed Completion Time Program C. Turbine driven AFW C.1 Restore the steam supply 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months train inoperable due to to the turbine driven train to one inoperable steam OPERABLE status.

supply.

OR AND C.2 Restore the motor driven 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months One motor driven AFW AFW train to OPERABLE train inoperable. status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B, AND or C not met.

D.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months OR Two AFW trains inoperable in MODE 1, 2, or 3 for reasons other than Condition C.

SEQUOYAH - UNIT 1 3.7.5-2 Amendment 334, 358

AFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Three AFW trains E.1 --------------NOTE--------------

inoperable in MODE 1, LCO 3.0.3 and all other 2, or 3. LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.

Initiate action to restore Immediately one AFW train to OPERABLE status.

F. Required AFW train F.1 Initiate action to restore Immediately inoperable in MODE 4. AFW train to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 -------------------------------NOTE------------------------------

AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation.

Verify each AFW manual, power operated, and In accordance automatic valve in each water flow path, and in both with the steam supply flow paths to the steam turbine driven Surveillance pump, that is not locked, sealed, or otherwise Frequency secured in position, is in the correct position. Control Program SEQUOYAH - UNIT 1 3.7.5-3 Amendment 334, 358

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.2 -------------------------------NOTE------------------------------

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 842 psig in the steam generator.

Verify the developed head of each AFW pump at the In accordance with flow test point is greater than or equal to the required the Inservice developed head. Testing Program SR 3.7.5.3 ------------------------------NOTES-----------------------------

1. AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation.

2. Only required to be met in MODES 1, 2, and 3.

Verify each AFW automatic valve that is not locked, sealed, or otherwise secured in position, actuates to In accordance with the correct position on an actual or simulated actuation the Surveillance signal. Frequency Control Program SR 3.7.5.4 ------------------------------NOTES-----------------------------

1. Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 842 psig in the steam generator.

2. AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation.

3. Only required to be met in MODES 1, 2, and 3.

Verify each AFW pump starts automatically on an In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program SEQUOYAH - UNIT 1 3.7.5-4 Amendment 334, 358

CCS 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water System (CCS)

LCO 3.7.7 Two CCS trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CCS train A.1 --------------NOTE--------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops -

MODE 4," for residual heat removal loops made inoperable by CCS.

Restore CCS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SEQUOYAH - UNIT 1 3.7.7-1 Amendment 334, 358

ERCW System 3.7.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One ERCW System B.1 --------------NOTES-------------

train inoperable for 1. Enter applicable reasons other than Conditions and Condition A. Required Actions of LCO 3.8.1, "AC Sources - Operating,"

for emergency diesel generator made inoperable by ERCW System.

2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops - MODE 4," for residual heat removal loops made inoperable by ERCW System.

Restore ERCW System 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train to OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met.

C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SEQUOYAH - UNIT 1 3.7.8-2 Amendment 334 336, 358

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3 Restore offsite circuit to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program B. One or more Train A B.1 Perform SR 3.8.1.1 for the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months DG(s) inoperable. offsite circuits.

AND OR Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months One or more Train B thereafter DG(s) inoperable.

AND B.2 Declare required feature(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from supported by the inoperable discovery of DG inoperable when its Condition B required redundant concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)

AND B.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DGs are not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DGs.

AND B.4 Restore DG(s) to 7 days OPERABLE status.

OR SEQUOYAH - UNIT 1 3.8.1-2 Amendment 334, 358

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME In accordance with the Risk Informed Completion Time Program C. One offsite circuit C.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable solely due to OPERABLE offsite circuit.

an offsite power source AND to 6.9 kV Shutdown Board 2A-A or 2B-B Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. thereafter AND C.2 Declare required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from with no offsite power discovery of no offsite available inoperable when power to 6.9 kV its redundant required Shutdown Board feature(s) is inoperable. 2A-A or 2B-B concurrent with inoperability of redundant required feature(s)

AND C.3 Restore offsite circuit to 7 days OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.8.1-3 Amendment 334, 358

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two offsite circuits D.1 Declare required feature(s) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from inoperable. inoperable when its discovery of redundant required Condition D feature(s) is inoperable. concurrent with inoperability of redundant required features AND D.2 Restore one offsite circuit to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program E. One offsite circuit E.1 Restore offsite circuit to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable for reasons OPERABLE status.

other than Condition C. OR AND In accordance with the Risk Informed DG 1A-A or 1B-B Completion Time inoperable. OR Program E.2 Restore DG to OPERABLE 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months status.

OR In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.8.1-4 Amendment 334, 358

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. One or more Train A F.1 Restore one train of DGs to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DG(s) inoperable. OPERABLE status.

AND One or more Train B DG(s) inoperable.

G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B, AND C, D, E, or F not met.

G.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months H. Two offsite circuits H.1 Enter LCO 3.0.3. Immediately inoperable.

AND One or more Train A DG(s) inoperable.

OR One or more Train B DG(s) inoperable.

I. One offsite circuit I.1 Enter LCO 3.0.3. Immediately inoperable.

AND One or more Train A DG(s) inoperable.

AND One or more Train B DG(s) inoperable.

SEQUOYAH - UNIT 1 3.8.1-5 Amendment 334, 358

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated power In accordance with availability for each offsite circuit. the Surveillance Frequency Control Program SR 3.8.1.2 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

2. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer.

When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met.

Verify each DG starts from standby conditions and In accordance with achieves steady state voltage 6800 V and 7260 V, the Surveillance and frequency 59.8 Hz and 60.2 Hz. Frequency Control Program SR 3.8.1.3 ------------------------------NOTES-----------------------------

1. DG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by and immediately follow without shutdown a successful performance of SR 3.8.1.2 or SR 3.8.1.7.

Verify each DG is synchronized and loaded and In accordance with operates for 60 minutes at a load 3960 kW and the Surveillance 4400 kW. Frequency Control Program SEQUOYAH - UNIT 1 3.8.1-6 Amendment 334, 341, 358

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operating LCO 3.8.4 Two Vital DC electrical power trains and four diesel generator (DG) DC electrical power subsystems shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two vital battery A.1 Restore battery terminal 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months chargers on one train voltage to greater than or inoperable. equal to the minimum established float voltage.

AND A.2 Verify battery float current Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2 amps.

AND A.3 Restore vital battery 7 days chargers to OPERABLE status. OR In accordance with the Risk Informed Completion Time Program B. One vital DC electrical B.1 Restore vital DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power train inoperable power train to OPERABLE for reasons other than status. OR Condition A.

In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.8.4-1 Amendment 334, 358

DC Sources - Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time of Condition A or B AND not met.

C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. One or more DG DC D.1 Declare associated DG(s) Immediately electrical power inoperable.

subsystem(s) inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or In accordance equal to the minimum established float voltage. with the Surveillance Frequency Control Program SR 3.8.4.2 Verify each vital battery charger supplies In accordance 150 amps at greater than or equal to the minimum with the established float voltage for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Surveillance Frequency OR Control Program Verify each vital battery charger can recharge the battery to the fully charged state within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

SEQUOYAH - UNIT 1 3.8.4-2 Amendment 334, 358

Inverters - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters - Operating LCO 3.8.7 The required Train A and Train B inverters shall be OPERABLE.

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

Two inverters may be disconnected from their associated DC source for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform an equalizing charge on their associated common battery, provided:

a. The associated AC vital instrument power board(s) are energized from their inverter using internal AC source, and

b. All other AC vital instrument power boards are energized from their associated OPERABLE inverters connected to their DC source.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required inverter A.1 --------------NOTE--------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems - Operating" with any AC vital instrument power board de-energized.

Restore inverter to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.8.7-1 Amendment 334, 358

Inverters - Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion 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 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, and In accordance alignment to required AC vital instrument power with the boards. Surveillance Frequency Control Program SEQUOYAH - UNIT 1 3.8.7-2 Amendment 334, 358

Distribution Systems - Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems - Operating LCO 3.8.9 Two electrical power distribution trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC A.1 --------------NOTE--------------

electrical power Enter applicable Conditions distribution subsystems and Required Actions of inoperable due to one or LCO 3.8.4, "DC Sources -

more Unit 1 AC Operating," for vital DC shutdown boards electrical power trains inoperable. made inoperable by inoperable AC electrical power distribution subsystems.

Restore Unit 1 AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power distribution subsystem(s) to OR OPERABLE status.

In accordance with the Risk Informed Completion Time Program B. One or more AC vital B.1 Restore AC vital instrument 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months instrument power power distribution distribution subsystems subsystem(s) to OR inoperable. OPERABLE status.

In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 1 3.8.9-1 Amendment 334, 358

Distribution Systems - Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more vital DC C.1 Restore vital DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power power distribution distribution subsystems subsystem(s) to OR inoperable. OPERABLE status.

In accordance with the Risk Informed Completion Time Program

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

1. Only applicable during planned maintenance.

2. Only applicable when Unit 1 is defueled or in MODE 6 following defueled with Unit 1 refueling water cavity level 23 ft. above top of reactor vessel flange.

D. One or more AC electrical D.1 Declare associated Immediately power distribution required feature(s) subsystems inoperable inoperable.

due to one or more Unit 1 AC shutdown boards inoperable.

E. One or more AC electrical E.1 Restore Unit 1 AC electrical 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months power distribution power distribution subsystems inoperable subsystem(s) to due to one or more Unit 1 OPERABLE status.

AC shutdown boards inoperable for reasons other than Condition D.

F. One or more DG DC F.1 Declare associated Immediately electrical power supported DG inoperable.

distribution panels inoperable.

SEQUOYAH - UNIT 1 3.8.9-2 Amendment 334, 358

Distribution Systems - Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND G.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months H. Two or more electrical H.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to In accordance required AC, vital DC, DG DC, and AC vital with the instrument electrical power distribution subsystems. Surveillance Frequency Control Program SEQUOYAH - UNIT 1 3.8.9-3 Amendment 334, 358

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Control Room Envelope (CRE) Habitability Program (continued)

f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

5.5.17 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

5.5.18 Risk Informed Completion Time Program This program provides controls to calculate a Risk Informed Completion Time (RICT) and must be implemented in accordance with NEI 06-09-A, Revision 0, "Risk-Managed Technical Specifications (RMTS) Guidelines." The program shall include the following:

a. The RICT may not exceed 30 days;

b. A RICT may only be utilized in MODE 1 and 2;

c. When a RICT is being used, any change to the plant configuration, as defined in NEI 06-09-A, Appendix A, must be considered for the effect on the RICT.

1. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration.

SEQUOYAH - UNIT 1 5.5-17 Amendment 334, 358

Programs and Manuals 5.5

2. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the plant configuration change, whichever is less.

3. Revising the RICT is not required if the plant configuration change would lower plant risk and would result in a longer RICT.

G For emergent conditions, if the extent of condition evaluation for

inoperable structures, systems, or components (SSCs) is not complete

prior to exceeding the Completion Time, the RICT shall account for the

increased possibility of common cause failure (CCF) by either:

Numerically accounting for the increased possibility of CCF in the

RICT calculation; or

Risk Management Actions (RMAs) not already credited in the

RICT calculation shall be implemented that support redundant or

diverse SSCs that perform the function(s) of the inoperable SSCs,

and, if practicable, reduce the frequency of initiating events that

challenge the function(s) performed by the inoperable SSCs.

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SEQUOYAH - UNIT 1 5.5-18 Amendment 358

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 352 Renewed License No. DPR-79

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Tennessee Valley Authority (the licensee) dated August 5, 2021, as supplemented by letters dates April 28, 2022, May 13, 2022, and July 1, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

Enclosure 2

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-79 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 352 are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 180 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by David David J. J. Wrona Date: 2022.08.24 Wrona 15:13:20 -04'00' David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: August 24, 2022 Enclosure 2

ATTACHMENT TO LICENSE AMENDMENT NO. 352 SEQUOYAH NUCLEAR PLANT, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace page 3 of the Renewed Facility Operating License with the attached page 3.

Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Page Insert Page 1.3-10 1.3-10

- 1.3-11 3.3.1-1 3.3.1-1 3.3.1-2 3.3.1-2 3.3.1-3 3.3.1-3 3.3.1-5 3.3.1-5 3.3.1-6 3.3.1-6 3.3.1-7 3.3.1-7 3.3.1-8 3.3.1-8 3.3.1-9 3.3.1-9 3.3.1-10 3.3.1-10 3.3.1-11 3.3.1-11 3.3.1-12 3.3.1-12 3.3.1-13 3.3.1-13 3.3.1-17 3.3.1-17 3.3.1-18 3.3.1-18 3.3.1-19 3.3.1-19 3.3.2-1 3.3.2-1 3.3.2-2 3.3.2-2 3.3.2-3 3.3.2-3 3.3.2-4 3.3.2-4 3.3.2-5 3.3.2-5 3.3.2-6 3.3.2-6 3.3.2-7 3.3.2-7 3.3.2-8 3.3.2-8 3.3.2-9 3.3.2-9 3.3.2-10 3.3.2-10 3.3.2-17 3.3.2-17 3.3.2-18 3.3.2-18 3.3.2-19 3.3.2-19 3.3.5-1 3.3.5-1

3.4.11-1 3.4.11-1 3.4.11-2 3.4.11-2 3.5.2-1 3.5.2-1 3.6.2-3 3.6.2-3 3.6.3-2 3.6.3-2 3.6.3-3 3.6.3-3 3.6.6-1 3.6.6-1 3.6.8-1 3.6.8-1 3.6.11-1 3.6.11-1 3.6.11-2 3.6.11-2 3.7.2-1 3.7.2-1 3.7.5-1 3.7.5-1 3.7.5-2 3.7.5-2 3.7.5-3 3.7.5-3 3.7.5-4 3.7.5-4 3.7.7-1 3.7.7-1 3.7.8-2 3.7.8-2 3.8.1-2 3.8.1-2 3.8.1-3 3.8.1-3 3.8.1-4 3.8.1-4 3.8.1-5 3.8.1-5 3.8.1-6 3.8.1-6 3.8.4-1 3.8.4-1 3.8.4-2 3.8.4-2 3.8.7-1 3.8.7-1 3.8.7-2 3.8.7-2 3.8.9-1 3.8.9-1 3.8.9-2 3.8.9-2 3.8.9-3 3.8.9-3 5.5-17 5.5-17

- 5.5-18

(3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the Sequoyah and Watts Bar Unit 1 Nuclear Plants.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 352 are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:

a. Elimination of any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential; Amendment No. 352 Renewed License No. DPR 79

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1.

If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by SR 3.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

EXAMPLE 1.3-8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore subsystem 7 days subsystem to OPERABLE inoperable. status. OR In accordance with the Risk Informed Completion Time Program B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion 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 When a subsystem is declared inoperable, Condition A is entered. The 7 day Completion Time may be applied as discussed in Example 1.3-2. However, the licensee may elect to apply the Risk Informed Completion Time Program which permits calculation of a Risk Informed Completion Time (RICT) that may be used to complete the Required Action beyond the 7 day Completion Time. The RICT cannot exceed 30 days. After the 7 day Completion Time has expired, the subsystem must be restored to OPERABLE status within the RICT or Condition B must also be entered.

SEQUOYAH - UNIT 2 1.3-10 Amendment 327, 352

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

The Risk Informed Completion Time Program requires recalculation of the RICT to reflect changing plant conditions. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the plant configuration change, whichever is less.

If the 7 day Completion Time clock of Condition A has expired and subsequent changes in plant condition result in exiting the applicability of the Risk Informed Completion Time Program without restoring the inoperable subsystem to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start.

If the RICT expires or is recalculated to be less than the elapsed time since the Condition was entered and the inoperable subsystem has not been restored to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable subsystems are restored to OPERABLE status after Condition B is entered, Condition A is exited, and therefore, the Required Actions of Condition B may be terminated.

IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action COMPLETION TIME should be pursued without delay and in a controlled manner.

SEQUOYAH - UNIT 2 1.3-11 Amendment 352

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.1-1 required channels or for the channel(s) or trains inoperable. train(s).

B. One Manual Reactor B.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Trip channel inoperable. OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program C. One channel or train C.1 Restore channel or train to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. OPERABLE status.

UOR C.2.1 Initiate action to fully insert 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months all rods.

UAND SEQUOYAH - UNIT 2 3.3.1-1 Amendment 327, 352

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2.2 Place the Rod Control 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months System in a condition incapable of rod withdrawal.

D. One Power Range -------------------NOTES------------------

Neutron Flux - High 1. The inoperable channel may channel inoperable. be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing and setpoint adjustment of other channels.

2. Perform SR 3.2.4.2 if input to QPTR from one or more Power Range Neutron Flux channels are inoperable with THERMAL power >75% RTP.

D.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR In accordance with the Risk Informed Completion Time Program SEQUOYAH - UNIT 2 3.3.1-2 Amendment 327, 336, 352

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One channel inoperable. -------------------NOTE--------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

E.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR In accordance with the Risk Informed Completion Time Program F. One Intermediate Range F.1 Reduce THERMAL 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Neutron Flux channel POWER to < P-6.

inoperable.

UOR F.2 Increase THERMAL 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months POWER to > P-10.

G. Two Intermediate Range G.1 --------------NOTE--------------

Neutron Flux channels Limited plant cooldown or inoperable. boron dilution is allowed provided the change is accounted for in the calculated SDM.

Suspend operations Immediately involving positive reactivity additions.

UAND G.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to < P-6.

SEQUOYAH - UNIT 2 3.3.1-3 Amendment 327, 352

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME K. One channel -------------------NOTE---------------------

inoperable. The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

K.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR In accordance with the Risk Informed Completion Time Program L. Required Action and L.1 Reduce THERMAL POWER 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated to < P-7.

Completion Time of Condition K not met.

M. One Turbine Trip -------------------NOTE---------------------

channel inoperable. The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

M.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR In accordance with the Risk Informed Completion Time Program N. Required Action and N.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated to < P-9.

Completion Time of Condition M not met.

SEQUOYAH - UNIT 2 3.3.1-5 Amendment 327, 352