Text

Correction to Technical Specification Amendment Identification Format
	ML18067A181
Person / Time
Site:	Byron, Braidwood
Issue date:	06/04/2018
From:	Joel Wiebe; Plant Licensing Branch III
To:	Bryan Hanson; Exelon Generation Co, Exelon Nuclear
	Wiebe J, NRC/NRR/DORL/LPLIII, 415-660
References
	Download: ML18067A181 (225)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 4, 2018 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 - CORRECTION TO TECHNICAL SPECIFICATION AMENDMENT IDENTIFICATION FORMAT

Dear Mr. Hanson:

When issuing amendments to technical specifications {TSs) for Byron Station, Unit Nos.

1 and 2, and Braidwood Station, Units 1 and 2, the U.S. Nuclear Regulatory Commission (NRC) has not been consistently formatting the amendment number identification at the bottom of the TS page. The NRC considers it important for the operators to be presented with a consistent format to avoid unnecessary questions that could come up and potentially delay operator actions. Therefore, the NRC is issuing corrected pages to the affected technical specification pages. Correction of the amendment identification format does not change the NRC conclusions provided in the affected amendments nor does it change the amendment numbers. Affected amendments are identified in Enclosure 1.

By letter dated July 5, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17088A703), the NRC informed you that an amendment No. 182 would not be issued to Renewed Facility Operating License No. NPF-72. The statement contained a typographical error. The amendment that will not be issued is amendment No. 192.

B. Hanson If you have any questions regarding this letter, please contact me at 301-415-6606 or Joel.Wiebe@nrc.gov.

Sincerely, oel S. Wiebe, Senior Project Manager 1Plant Licensing Branch Ill G I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-456, 50-457, 50-454, and 50-455

Enclosures:

1. List of Affected Amendments

2. Braidwood Station Page Replacement Instructions

3. Byron Station Page Replacement Instructions Cc: Listserv

List of Affected Amendments Braidwood Station Amendment No. Date ADAMS Accession No.

102 June 2, 1999 ML020860637 104 October 13, 1999 ML020860566 165 February 24, 2011 ML110070153 172 March 25, 2012 ML110840580 180 December 7, 2014 ML14239A427 183 June 22, 2015 ML15114A188 194 August 31, 2017 ML17163A355 Byron Station Amendment No. Date ADAMS Accession No.

109 June 2, 1999 ML020860637 171 February 24, 2011 ML110070153 179 March 25, 2012 ML110840580 186 December 7, 2014 ML14239A427 189 June 22, 2015 ML15114A188 197 May 26, 2017 ML17073A067 200 August 31, 2017 ML17163A355 Enclosure 1

BRAIDWOOD STATION, UNITS 1 AND 2 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 CORRECTION TO AMENDMENT NUMBER IDENTIFICATION FORMAT Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The corrected pages change the format of the amendment number identification and don't change the amendment number.

Remove TSs TSs 1.3-1 1.3-1 1.3-2 1.3-2 1.3-3 1.3-3 3.0-2 3.0-2 3.0-6 3.0-6 3.1.1-1 3.1.1-1 3.1.2-2 3.1.2-2 3.1.4-4 3.1.4-4 3.1.5-2 3.1.5-2 3.1.6-2 3.1.6-2 3.1.6-3 3.1.6-3 3.1.8-2 3.1.8-2 3.2.1-3 3.2.1-3 3.2.1-5 3.2.1-5 3.2.1-6 3.2.1-6 3.2.2-3 3.2.2-3 3.2.3-1 3.2.3-1 3.2.4-4 3.2.4-4 3.2.5-1 3.2.5-1 3.3.1-3 3.3.1-3 3.3.1-4 3.3.1-4 3.3.1-6 3.3.1-6 3.3.2-3 3.3.2-3 3.3.2-7 3.3.2-7 3.3.3-3 3.3.3-3 3.3.4-2 3.3.4-2 3.3.7-2 3.3.7-2 3.3.8-3 3.3.8-3 3.3.9-3 3.3.9-3 3.3.9-4 3.3.9-4 3.3.9-5 3.3.9-5 3.4.2-1 3.4.2-1 3.4.3-2 3.4.3-2 3.4.4-1 3.4.4-1 3.4.5-3 3.4.5-3 Enclosure 2

TSs (continued) TSs (continued) 3.4.5-4 3.4.5-4 3.4.6-2 3.4.6-2 3.4.6-3 3.4.6-3 3.4.7-3 3.4.7-3 3.4.7-4 3.4.7-4 3.4.8-2 3.4.8-2 3.4.9-2 3.4.9-2 3.4.11-3 3.4.11-3 3.4.12-4 3.4.12-4 3.4.12-5 3.4.12-5 3.4.13-2 3.4.13-2 3.4.14-4 3.4.14-4 3.4.16-2 3.4.16-2 3.4.17-2 3.4.17-2 3.4.19-1 3.4.19-1 3.4.19-2 3.4.19-2 3.5.1-2 3.5.1-2 3.5.2-3 3.5.2-3 3.5.4-2 3.5.4-2 3.5.5-2 3.5.5-2 3.6.2-5 3.6.2-5 3.6.3-5 3.6.3-5 3.6.4-1 3.6.4-1 3.6.5-1 3.6.5-1 3.6.6-2 3.6.6-2 3.6.7-1 3.6.7-1 3.6.7-2 3.6.7-2 3.7.3-1 3.7.3-1 3.7.4-2 3.7.4-2 3.7.5-3 3.7.5-3 3.7.6-2 3.7.6-2 3.7.7-2 3.7.7-2 3.7.10-4 3.7.10-4 3.7.12-2 3.7.12-2 3.7.13-3 3.7.13-3 3.7.13-4 3.7.13-4 3.7.14-1 3.7.14-1 3.7.15-1 3.7.15-1 3.8.1-5 3.8.1-5 3.8.1-6 3.8.1-6 3.8.1-8 3.8.1-8 3.8.1-9 3.8.1-9 3.8.1-10 3.8.1-10 3.8.1-11 3.8.1-11 3.8.1-12 3.8.1-12 3.8.3-2 3.8.3-2 3.8.4-3 3.8.4-3 3.8.6-3 3.8.6-3 3.8.6-4 3.8.6-4 3.8.6-5 3.8.6-5

TSs (continued) TSs (continued) 3.8.7-2 3.8.7-2 3.8.9-2 3.8.9-2 3.8.9-3 3.8.9-3 3.8.10-4 3.8.10-4 3.9.1-1 3.9.1-1 3.9.2-2 3.9.2-2 3.9.3-1 3.9.3-1 3.9.3-2 3.9.3-2 3.9.5-2 3.9.5-2 3.9.6-2 3.9.6-2 3.9.7-1 3.9.7-1 5.5-7 5.5-7 5.5-8 5.5-8 5.5-9 5.5-9 5.5-10 5.5-10 5.5-11 5.5-11 5.5-24 5.5-24 5.6-6 5.6-6 5.6-7 5.6-7

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCD state Conditions that typically describe the ways in which the requirements of the LCD can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the LCD. Unless otherwise specified, the Completion Time begins when a senior licensed operator on the operating shift crew with responsibility for plant operations makes the determination that an LCD is not met and an ACTIONS Condition is entered. The "otherwise specified" exceptions are varied, such as a Required Action Note or Surveillance Requirement Note that provides an alternative time to perform specific tasks, such as testing, without starting the Completion Time. While utilizing the Note, should a Condition be applicable for any reason not addressed by the Note, the Completion Time begins. Should the time allowance in the Note be exceeded, the Completion Time begins at that point. The exceptions may also be incorporated into the Completion Time. For example, LCO 3.8.1, "AC Sources - Operating," Required Action B.3, requires declaring required feature(s) supported by an inoperable diesel generator, inoperable when the redundant required feature(s) are inoperable. The Completion Time states, "4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition B concurrent with inoperability of redundant required feature(s)." In this case the Completion Time does not begin until the conditions in the Completion Time are satisfied. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCD Applicability.

If situations are discovered that require entry into more BRAIDWOOD - UNITS 1 &2 1.3 - 1 Amendment 194

Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued) than one Condition at a time within a single LCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the discovery of the situation that required entry into the Condition, unless otherwise specified.

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

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

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be rimited to the more restrictive of either:

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

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

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

BRAIDWOOD - UNITS 1 &2 1.3 - 2 Amendment 194

Completion Times 1.3 Completion Times DESCRIPTION (continued)

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . . . " Example 1. 3-3 i 11 ustrates one use of this type of Completion Time. The 10 day Completion Time specified for Conditions A and Bin Example 1.3-3 may not be extended.

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

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.l 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 B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition Bis entered.

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

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

BRAIDWOOD - UNITS 1 &2 1.3 - 3 Amendment 194

LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

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

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

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

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

LCD 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the required testing to demonstrate OPERABILITY.

BRAIDWOOD - UNITS 1 &2 3.0 - 2 Amendment 194

SR Applicability 3.0 3.0 SR APPLICABILITY SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. The delay period is only applicable when there is a reasonable expectation the surveillance will be met when performed. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCD 3.0.4 This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

SR 3.0.5 SRs shall apply to each unit individually, unless otherwise indicated.

BRAIDWOOD - UNITS 1 &2 3.0 - 6 Amendment 194

SOM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SOM)

LCO 3.1.1 SOM shall be within the limits specified in the COLR.

APPLICABILITY: MODE 2 with keff < 1.0, MODES 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SOM not within limit. A.l Initiate boration to 15 minutes restore SOM to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SOM is within the limits specified In accordance in the COLR. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.1.1-1 Amendment 165

Core Reactivity 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify measured core reactivity is within Prior to

+/- 1% ~k/k of predicted values. entering MODE 1 after each refueling SR 3.1.2.2 -------------------NOTES-------------------

1. Only required to be performed after 60 Effective Full Power Days (EFPD).

2. The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 EFPD after each fuel loading.

Verify measured core reactivity is within In accordance

+/- 1% ~k/k of predicted values. with the Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.1.2 - 2 Amendment 165

Rod Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.l 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 or Required Action C.3 not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within In accordance alignment limit. with the Survei 11 ance Frequency Control Program SR 3.1.4.2 Verify rod freedom of movement In accordance (trippability) by moving each rod not fully with the inserted in the core~ 10 steps in either Surveillance direction. Frequency Control Program SR 3.1.4.3 Verify rod drop time of each rod, from the Prior to fully withdrawn position, is~ 2.7 seconds criticality from the beginning of decay of stationary after each gripper coil voltage to dashpot entry, removal of the with: reactor head

a. Tavg ~ 550°F; and

b. All reactor coolant pumps operating.

BRAIDWOOD - UNITS 1 &2 3.1.4-4 Amendment 165

Shutdown Bank Insertion Limits 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each shutdown bank is within the In accordance insertion limits specified in the COLR. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.1.5-2 Amendment 165

Control Bank Insertion Limits 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Control bank sequence B.1.1 Verify SOM is within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or overlap limits not the limits specified met. in the COLR.

OR B.1.2 Initiate boration to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore SOM to within limit.

AND B.2 Restore control bank 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months sequence and overlap to within limits.

C. Required Action and C.l Be in MODE 2 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion keff < 1.0.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify estimated critical control bank Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months position is within the limits specified in prior to the COLR. criticality SR 3.1.6.2 Verify each control bank is within the In accordance insertion limits specified in the COLR. with the Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.1.6-2 Amendment 165

Control Bank Insertion Limits 3.1.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.6.3 Verify each control bank not fully In accordance withdrawn from the core is within the with the sequence and overlap limits specified in Surveillance the COLR. Frequency Contra l Program BRAIDWOOD - UNITS 1 &2 3.1.6 - 3 Amendment 165

PHYSICS TESTS Exceptions-MODE 2 3.1.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. RCS lowest loop C.l Restore RCS lowest 15 minutes average temperature loop average not within limit. temperature to within limit.

D. Required Action and 0.1 Be in MODE 3. 15 minutes associated Completion Time of Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Perform CHANNEL OPERATIONAL TEST on power Prior to range and intermediate range channels per initiation of SR 3.3.1.7, SR 3.3.1.8, and PHYSICS TESTS Table 3.3.1.1-1.

SR 3.1.8.2 Verify the RCS lowest loop average In accordance temperature is~ 530°F. with the Surveillance Frequency Control Program SR 3.1.8.3 Verify THERMAL POWER is~ 5% RTP. In accordance with the Surveillance Frequency Control Program SR 3.1.8.4 Verify SOM is within the limits specified In accordance in the COLR. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.1.8-2 Amendment 165

F0(Z) 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 -------------------NOTES-------------------

1. During power escalation at the beginning of each cycle, THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution map is obtained.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring Power Distribution Monitoring System (PDMS) inoperable. Performance of SR 3.2.1.3 satisfies the initial performance of this SR after declaring PDMS inoperable.

Verify F5 (Z) is within limit specified in Prior to the COLR. exceeding 75% RTP after each refueling AND Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by

~ 10% RTP, the THERMAL POWER at which F5(Z) was last verified AND In accordance with the Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.2.1 - 3 Amendment 165

Fq(Z) 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.2 (continued)

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

3. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring PDMS inoperable. Performance of SR 3.2.1.4 satisfies the initial performance of this SR after declaring PDMS inoperable.

Verify FtCZ) is within limit specified in Prior to the COLR. exceeding 75% RTP after each refueling Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by

~ 10% RTP, the THERMAL POWER at which Ft CZ) was last verified In accordance with the Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.2.1 - 5 Amendment 165

Fq(Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.3 -------------------NOTE--------------------

Only required to be performed when PDMS is OPERABLE.

Verify Ficz) is within limit specified in In accordance the COLR. with the Surveillance Frequency Control Program SR 3.2.1.4 -------------------NOTE--------------------

Only required to be performed when PDMS is OPERABLE.

Verify Ft(Z) is within limit specified in In accordance the COLR. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.2.1 - 6 Amendment 165

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring PDMS inoperable.

Performance of SR 3.2.2.2 satisfies the initial performance of this SR after declaring PDMS inoperable.

Verify F1H is within limits specified in the Prior to COLR. exceeding 75% RTP after each refueling In accordance with the Surveillance Frequency Control Program SR 3.2.2.2 -------------------NOTE--------------------

Only required to be performed when PDMS is OPERABLE.

Verify F1H is within limit specified in the In accordance COLR. with the Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.2.2 - 3 Amendment 165

AFD 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCD 3.2.3 The AFD shall be maintained within the limits specified in the COLR.

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

The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.

APPLICABILITY: MODE 1 with THERMAL POWER~ 50% RTP when Power Distribution Monitoring System (PDMS) is inoperable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AFD not within limits. A.l Reduce THERMAL POWER 30 minutes to < 50% RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring PDMS inoperable.

Verify AFD is within limits for each In accordance OPERABLE excore channel. with the Surveillance Frequency Contra l Program BRAIDWOOD - UNITS 1 &2 3.2.3 - 1 Amendment 165

QPTR 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 ------------------NOTES--------------------

1. With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER s 75% RTP, the remaining three power range channel inputs can be used for calculating QPTR.

2. SR 3.2.4.2 may be performed in lieu of this Surveillance.

3. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring PDMS inoperable.

Verify QPTR is s 1.02 by calculation. In accordance with the Surveillance Frequency Control Program SR 3.2.4.2 -------------------NOTES-------------------

1. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after input from one Power Range Neutron Flux channel is inoperable with THERMAL POWER

> 75% RTP.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring PDMS inoperable.

Verify QPTR is s 1.02 using the movable In accordance incore detectors. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.2.4 - 4 Amendment 165

DNBR 3.2.5 3.2 POWER DISTRIBUTION LIMITS 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)

LCO 3.2.5 DNBR shall be within the limit specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER~ 50% RTP when Power Distribution Monitoring System (PDMS) is OPERABLE.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DNBR not within limit. A.l Restore DNBR to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months within limit.

B. Required Action and B.l Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 50% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.5.1 Verify DNBR is within limit specified in In accordance the COLR. with the Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.2.5 - 1 Amendment 165

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One Power Range -------------NOTE------------

Neutron Flux-High One channel may be bypassed channel inoperable. 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.

D.1 Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

OR D.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

BRAIDWOOD - UNITS 1 &2 3.3.1 - 3 Amendment 180

RTS Instrumentation 3.3.1 ACTIONS (continued)

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

inoperable. One 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.

E.l Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

OR E.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

BRAIDWOOD - UNITS 1 &2 3.3.1 - 4 Amendment 180

RTS Instrumentation 3.3.1 ACTIONS (continued)

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

inoperable. 1. For Functions with installed bypass test capability (Functions 8a, 9, 10), one 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.

2. For Functions with no installed bypass test capability (Functions 12 and 13), 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.l Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

OR K.2 Reduce THERMAL POWER 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months to< P-7.

L. 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.

L.l Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

OR L.2 Reduce THERMAL POWER 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months to< P-8.

(continued)

BRAIDWOOD - UNITS 1 &2 3.3.1 - 6 Amendment 180

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One channel 0.1 --------NOTE---------

inoperable. One 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.

Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

OR 0.2.1 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND D. 2. 2 Be in MODE 4. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

BRAIDWOOD - UNITS 1 &2 3.3.2 - 3 Amendment 180

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

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

inoperable. One 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.

Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

OR K.2.1 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND K.2.2 Be in MODE 5. 108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months (continued)

BRAIDWOOD - UNITS 1 &2 3.3.2 - 7 Amendment 180

PAM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. ---------NOTE--------- G.l Initiate action in Immediately Only applicable to accordance with Functions 11, 12, and Specification 5.6.7.

14.

Required Action and associated Completion Time of Condition Dor E not met.

SURVEILLANCE REQUIREMENTS

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

SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required In accordance instrumentation channel that is normally with the energized. Surveillance Frequency Control Program SR 3.3.3.2 -------------------NOTE--------------------

Radiation detectors for Function 11, Containment Area Radiation, are excluded.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.3.3 - 3 Amendment 165

Remote Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL CHECK for each required In accordance instrumentation channel that is normally with the energized. Surveillance Frequency Control Program SR 3.3.4.2 -------------------NOTE--------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each In accordance required instrumentation channel. with the Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.3.4 - 2 Amendment 165

VC Filtration System Actuation Instrumentation 3.3.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and 0.1 Suspend movement of Immediately associated Completion irradiated fuel Time of Condition A assemblies.

or B not met during movement of irradiated fuel assemblies.

E. Required Action and E.1 Initiate action to Immediately associated Completion restore one VC Time of Condition A Filtration System or B not met in MODE 5 train to OPERABLE or 6. status.

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.7-1 to determine which SRs apply for each VC Filtration System Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.2 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.7.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.3.7 - 2 Amendment 165

FHB Ventilation System Actuation Instrumentation 3.3.8 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.8-1 to determine which SRs apply for each FHB Ventilation System Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.8.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.8.2 Perform COT. In accordance with the Survei 11 ance Frequency Control Program SR 3.3.8.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.3.8 - 3 Amendment 165

BOPS 3.3.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.9.1 Verify one or more reactor coolant pump(s) In accordance in operation. with the Surveillance Frequency Control Program SR 3.3.9.2 Verify each RCS loop isolation valve is In accordance open. with the Surveillance Frequency Control Program SR 3.3.9.3 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.9.4 Verify each Boron Dilution Alert channel In accordance selector switch is in the Normal position. with the Surveillance Frequency Control Program SR 3.3.9.5 Verify each manual, power operated, and In accordance automatic valve in the flow path, that is with the not locked, sealed, or otherwise secured in Survei 11 ance position, is in the correct position. Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.3.9 - 3 Amendment 165

BOPS 3.3.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.9.6 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.9.7 -------------------NOTE--------------------

The CHANNEL CALIBRATION is only required to include that portion of the channel associated with the Boron Dilution Alert function.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.3.9 - 4 Amendment 165

BOPS 3.3.9 Table 3.3.9-1 (page 1 of 1)

Boron Dilution Protection System Instrumentation FUNCTION REQUIRED CHANNELS SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE Boron Dilution Alert Channels Volume Control Tank Level High 2 SR 3.3.9.3 ~ 71.15%

SR 3.3.9.6 SR 3.3.9.7 BRAIDWOOD - UNITS 1 &2 3.3.9 - 5 Amendment 165

RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCD 3.4.2 Each RCS loop average temperature <Tavg) shall be 2 550°F.

APPLICABILITY: MODE 1, MODE 2 with keff 2 1. 0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tavg in one or more RCS A. l Be in MODE 2 with 30 minutes loops not within keff< 1.0.

limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each loop 2 550°F. In accordance with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.2 - 1 Amendment 165

RCS P/T Limits 3.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ---------NOTE--------- C.l Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed to within limits.

whenever this Condition is entered. AND C.2 Determine RCS is Prior to Requirements of LCO acceptable for entering MODE 4 not met any time other continued operation.

than in MODE 1, 2, 3, or 4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 -------------------NOTE--------------------

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and In accordance RCS heatup and cooldown rates are within with the the limits specified in the PTLR. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.3 - 2 Amendment 165

RCS Loops-MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops-MODES 1 and 2 LCO 3.4.4 Four RCS loops shall be OPERABLE and in operation.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months LCO not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation. In accordance with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.4 - 1 Amendment 165

RCS Loops-MODE 3 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.l Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition D not met.

F. Two required RCS loops F.l Initiate action to Immediately inoperable. place the Rod Control System in a condition incapable of rod withdrawal .

AND F.2 Suspend all Immediately operations involving a reduction of RCS boron concentration.

AND F.3 Initiate action to Immediately restore one RCS loop to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4. 5.1 Verify each required RCS loop is in In accordance operation. with the Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.4.5 - 3 Amendment 165

RCS Loops-MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.5.2 Verify steam generator secondary side In accordance narrow range water level is~ 18% for each with the required RCS loop. Surveillance Frequency Control Program SR 3.4.5.3 Verify correct breaker alignment and In accordance indicated power are available to each with the required pump that is not in operation. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.5 - 4 Amendment 165

RCS Loops-MODE 4 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One required loop B.1 Initiate action to Irrrnediately inoperable. restore a second loop to OPERABLE status.

AND B.2 --------NOTE---------

Only required if RHR loop is OPERABLE.

Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. Two required loops C.l Suspend all Irrrnediately inoperable. operations involving a reduction of RCS boron concentration.

AND C.2 Initiate action to Irrrnediately restore one loop to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify required RHR or RCS loop is in In accordance operation. with the Surveillance Frequency Control Program SR 3.4.6.2 Verify SG secondary side narrow range water In accordance level is~ 18% for each required RCS loop. with the Survei 11 ance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.4.6 - 2 Amendment 165

RCS Loops-MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.6.3 Verify correct breaker alignment and In accordance indicated power are available to each with the required pump that is not in operation. Surveillance Frequency Control Program SR 3.4.6.4 -------------------NOTE--------------------

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

Verify required RHR loop locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.6 - 3 Amendment 183

RCS Loops-MODE 5, Loops Filled 3.4. 7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two required RHR loops D.1 Suspend all Irrmediately inoperable. operations involving a reduction of RCS OR boron concentration.

Required RHR loop AND inoperable and one or both required SG D.2.1 Initiate action to Irrmediately secondary side water restore one RHR loop level Cs) not within to OPERABLE status.

limits.

OR D.2.2 Initiate action to Irrmediately restore required SG secondary side water level(s) to within limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required RHR loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4.7.2 Verify SG secondary side narrow range water In accordance level is~ 18% in required SGs. with the Surveillance Frequency Control Program SR 3.4. 7 .3 Verify correct breaker alignment and In accordance indicated power are available to each with the required RHR pump that is not in operation. Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.4. 7 - 3 Amendment 183

RCS Loops-MODE 5, Loops Filled 3.4. 7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4. 7.4 Verify required RHR loop locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.7 - 4 Amendment 183

RCS Loops-MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One required RHR loop B.1 Initiate action to Irrmediately inoperable. restore RHR loop to OPERABLE status.

C. Two required RHR loops C.l Suspend all Irrmediately inoperable. operations involving reduction in RCS boron concentration.

AND C.2 Initiate action to Irrmediately restore one RHR loop to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify required RHR loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4.8.2 Verify correct breaker alignment and In accordance indicated power are available to each with the required RHR pump that is not in operation. Surveillance Frequency Control Program SR 3.4.8.3 Verify RHR loop locations susceptible to In accordance gas accumulation are sufficiently filled with the with water. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.8 - 2 Amendment 183

Pressurizer 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.l 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 AND not met.

C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is~ 92%. In accordance with the Survei 11 ance Frequency Control Program SR 3.4.9.2 Verify capacity of each required group of In accordance pressurizer heaters is~ 150 kW. with the Survei 11 ance Frequency Control Program SR 3.4.9.3 Verify required pressurizer heaters are In accordance capable of being powered from an ESF power with the supply. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.9 - 2 Amendment 165

Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 -------------------NOTE--------------------

Not required to be met with block valve closed in accordance with the Required Action of Condition B or E.

Perform a complete cycle of each block In accordance valve. with the Surveillance Frequency Control Program SR 3.4.11.2 -------------------NOTE--------------------

Only required to be performed in MODES 1 and 2.

Perform a complete cycle of each PORV. In accordance with the Surveillance Frequency Control Program SR 3.4.11.3 Perform a complete cycle of each solenoid In accordance air control valve and check valve on the with the air accumulators in PORV control systems. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.11 - 3 Amendment 165

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify no SI pump is capable of injecting In accordance into the RCS. with the Surveillance Frequency Control Program SR 3.4.12.2 Verify a maximum of one charging pump In accordance (centrifugal) is capable of injecting into with the the RCS. Survei 11 ance Frequency Control Program SR 3.4.12.3 -------------------NOTE--------------------

Only required to be met for accumulator whose pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.

Verify each accumulator is isolated. In accordance with the Surveillance Frequency Control Program SR 3.4.12.4 Verify required RCS vent 2 2.0 square In accordance inches open. with the Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.4.12 - 4 Amendment 165

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.5 Verify RHR suction valves are open for each In accordance required RHR suction relief valve. with the Survei 11 ance Frequency Contra l Program SR 3.4.12.6 Verify PORV block valve is open for each In accordance required PORV. with the Surveillance Frequency Control Program SR 3.4.12.7 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after decreasing RCS cold leg temperature to ~ 350°F.

Perform a COT on each required PORV, In accordance excluding actuation. with the Surveillance Frequency Control Program SR 3.4.12.8 Perform CHANNEL CALIBRATION for each In accordance required PORV actuation channel. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.12 - 5 Amendment 165

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 -------------------NOTES-------------------

1. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

2. Not applicable to primary to secondary LEAKAGE.

Verify RCS operational LEAKAGE is within In accordance limits by performance of RCS water with the inventory balance. Surveillance Frequency Control Program SR 3.4.13.2 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Verify primary to secondary LEAKAGE is In accordance

~ 150 gallons per day through any one SG. with the Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.13-2 Amendment 165

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 (continued) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months fo 11 owing valve actuation due to automatic or manual action or fl ow through the valve SR 3.4.14.2 Verify RHR System suction isolation valve In accordance interlock prevents the valves from being with the opened with a simulated or actual RCS Surveillance pressure signal 2 360 psig. Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.14 - 4 Amendment 165

RCS Specific Activity 3.4.16 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 AND or B not met.

C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR DOSE EQUIVALENT I-131

> 60 µCi/gm.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant DOSE EQUIVALENT In accordance XE-133 specific activity~ 603 µCi/gm. with the Surveillance Frequency Control Program SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT In accordance I-131 specific activity~ 1.0 µCi/gm. with the Surveillance Frequency Control Program Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of

~ 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period BRAIDWOOD - UNITS 1 &2 3.4.16 - 2 Amendment 165

RCS Loop Isolation Valves 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify each RCS loop isolation valve is In accordance open and power is removed from each loop with the isolation valve operator. Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.4.17 - 2 Amendment 165

SG Tube Integrity 3 .4 .19 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.19 Steam Generator (SG) Tube Integrity LCD 3.4.19 SG tube integrity shall be maintained.

AND All SG tubes satisfying the tube plugging criteria shall be plugged in accordance with the Steam Generator Program.

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

ACTIONS

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

Separate Condition entry is allowed for each SG tube.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes A.1 Verify tube integrity 7 days satisfying the tube of the affected plugging criteria and tube(s) is maintained not plugged in until the next accordance with the refueling outage or Steam Generator SG tube inspection.

Program.

AND A.2 Plug the affected Prior to tube(s) in accordance entering MODE 4 with the Steam following the Generator Program. next refueling outage or SG tube inspection 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 AND not met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR SG tube integrity not maintained.

J BRAIDWOOD - UNITS 1 &2 3.4.19-1 Amendment 172

SG Tube Integrity 3.4.19 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.19.1 Verify SG tube integrity in accordance with In accordance the Steam Generator Program. with the Steam Generator Program SR 3.4.19.2 Verify that each inspected SG tube that Prior to satisfies the tube plugging criteria is entering MODE 4 plugged in accordance with the Steam following a SG Generator Program. tube inspection BRAIDWOOD - UNITS 1 &2 3.4.19 - 2 Amendment 172

Accumulators 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is In accordance fully open. with the Survei 11 ance Frequency Contra l Program SR 3.5.1.2 Verify borated water level in each In accordance accumulator is 2 31% ands 63%. with the Survei 11 ance Frequency Contra l Program SR 3.5.1.3 Verify nitrogen cover pressure in each In accordance accumulator is 2 602 psig ands 647 psig. with the Surveillance Frequency Contra l Program SR 3.5.1.4 Verify boron concentration in each In accordance accumulator is 2 2200 ppm ands 2400 ppm. with the Surveillance Frequency Control Program SR 3.5.1.5 -------------------NOTE--------------------

Only required to be performed for affected accumulators after each solution volume increase of 2 10% of indicated level that is not the result of addition from the refueling water storage tank containing a boron concentration 2 2200 ppm and s 2400 ppm.

Verify boron concentration in each Once within accumulator is 2 2200 ppm ands 2400 ppm. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SR 3.5.1.6 Verify power is removed from each In accordance accumulator isolation valve operator. with the Surveillance Frequency Contra l Program BRAIDWOOD - UNITS 1 &2 3.5.1 - 2 Amendment 165

ECCS-Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves are in the In accordance listed position with power to the valve with the operator removed: Surveillance Frequency Number Position Function Control Program MOV SI8806 Open Suction to SI Pumps MOV SI8835 Open SI Pump Discharge to Reactor Coolant System (RCS) Cold Legs MOV SI8813 Open SI Pump Recirculation to the Refueling Water Storage Tank MOV SI8809A Open RHR Pump Discharge to RCS Cold Legs MOV SI8809B Open RHR Pump Discharge to RCS Cold Legs MOV SI8840 Closed RHR Pump Discharge to RCS Hot Legs MOV SI8802A Closed SI Pump Discharge to RCS Hot Legs MOV SI8802B Closed SI Pump Discharge to RCS Hot Legs SR 3.5.2.2 --------------------NOTE-------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each ECCS manual, power operated, In accordance and automatic valve in the flow path, that with the is not locked, sealed, or otherwise secured Surveillance in position, is in the correct position. Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.5.2 - 3 Amendment 183

RWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 -------------------NOTE--------------------

Only required to be performed when ambient air temperature is< 35°F or> 100°F.

Verify RWST borated water temperature is In accordance 2 35°F and ~ 100°F. with the Surveillance Frequency Control Program SR 3.5.4.2 -------------------NOTE--------------------

Only required to be performed when ambient air temperature is< 35°F.

Verify RWST vent path temperature is In accordance 2 35°F. with the Survei 11 ance Frequency Control Program SR 3.5.4.3 Verify RWST borated water level is 2 89%. In accordance with the Surveillance Frequency Control Program SR 3.5.4.4 Verify RWST boron concentration is In accordance 2 2300 ppm and~ 2500 ppm. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.5.4 - 2 Amendment 165

Seal Injection Flow 3.5.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.5.1 -------------------NOTE--------------------

Not required to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the Reactor Coolant System pressure stabilizes at~ 2215 psig ands 2255 psig.

Verify manual seal injection throttle In accordance valves are adjusted to give a flow within with the the limits of Figure 3.5.5-1. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.5.5 - 2 Amendment 165

Containment Air Locks 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1 -------------------NOTES-------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.

Perform required air lock leakage rate In accordance testing in accordance with the Containment with the Leakage Rate Testing Program. Containment Leakage Rate Testing Program SR 3.6.2.2 Verify only one door in the air lock can be In accordance opened at a time. with the Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.6.2 - 5 Amendment 165

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.l 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 E.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 3.6.3.1 Verify each 48 inch purge valve is sealed In accordance closed. with the Survei 11 ance Frequency Control Program SR 3.6.3.2 Verify each 8 inch purge valve is closed, In accordance except when the 8 inch containment purge with the valves are open for purging or venting Surveillance under administrative controls. Frequency Control Program SR 3.6.3.3 -------------------NOTE--------------------

Valves and blind flanges in high radiation areas may be verified by use of administrative controls.

Verify each containment isolation manual In accordance valve, remote manual valve, and blind with the flange that is located outside containment Surveillance and not locked, sealed, or otherwise Frequency secured and required to be closed during Control Program accident conditions is closed, except for containment isolation valves that are open under administrative controls.

(continued)

BRAIDWOOD - UNITS 1 &2 3.6.3 - 5 Amendment 165

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be~ -0.1 psig and~ +1.0 psig.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure A.l Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not within limits. pressure to within limits.

B. Required Action and B.l Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Ti me 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 3.6.4.1 Verify containment pressure is within In accordance limits. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.6.4 - 1 Amendment 165

Containment Air Temperature 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature LCD 3.6.5 Containment average air temperature shall be~ 120°F.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average A.l Restore containment 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months air temperature not average air within limit. temperature to within limit.

B. Required Action and B.l 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 3.6.5.1 Verify containment average air temperature In accordance is within limit. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.6.5 - 1 Amendment 165

Containment Spray and Cooling Systems 3.6.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 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 AND not met.

D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Two containment spray E.l Enter LCO 3.0.3. Immediately trains inoperable.

OR Any combination of three or more trains inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 --------------------NOTE-------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each containment spray manual, power In accordance operated, and automatic valve in the flow with the path that is not locked, sealed, or Surveillance otherwise secured in position is in the Frequency correct position. Control Program SR 3.6.6.2 Operate each containment cooling train fan In accordance unit for 2 15 minutes. with the Surveillance Frequency Control Program SR 3.6.6.3 Verify each containment cooling train In accordance cooling water flow rate is 2 2660 gpm to with the each cooler. Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.6.6 - 2 Amendment 183

Spray Additive System 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Spray Additive System LCD 3.6.7 The Spray Additive System shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spray Additive System A.1 Restore Spray 7 days inoperable. Additive System to OPERABLE status.

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 3.6.7.1 Verify each spray additive manual and In accordance automatic valve in the flow path that is with the not locked, sealed, or otherwise secured in Surveillance position is in the correct position. Frequency Control Program SR 3.6.7.2 Verify spray additive tank solution level In accordance is~ 78.6% and~ 90.3%. with the Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.6.7 - 1 Amendment 165

Spray Additive System 3.6.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.7.3 Verify spray additive tank sodium hydroxide In accordance solution concentration is~ 30% and~ 36% with the by weight. Surveillance Frequency Control Program SR 3.6. 7.4 Verify each spray additive automatic valve In accordance in the flow path that is not locked, with the sealed, or otherwise secured in position, Surveillance actuates to the correct position on an Frequency actual or simulated actuation signal. Control Program SR 3.6.7.5 Verify spray additive flow rate from each In accordance solution's flow path. with the Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.6.7 - 2 Amendment 165

Secondary Specific Activity 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Secondary Specific Activity LCO 3.7.3 The specific activity of the secondary coolant shall be s 0.1 µCi/gm DOSE EQUIVALENT I-131.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not A.l Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months within limit.

AND A.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 3.7.3.1 Verify the specific activity of the In accordance secondary coolant is s 0.1 µCi/gm DOSE with the EQUIVALENT I-131. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.7.3 - 1 Amendment 165

SG PORVs

3. 7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each SG PORV. In accordance with the Survei 11 ance Frequency Control Program SR 3. 7.4.2 Verify one complete cycle of each SG PORV In accordance block valve. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.7.4-2 Amendment 165

AF System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.7 Verify proper alignment of the required AF Prior to flow paths by verifying flow from the entering MODE 2 condensate storage tank to each steam whenever unit generator. has been in MODE 5, MODE 6, or defueled for a cumulative period of

> 30 days SR 3.7.5.8 Verify fuel oil properties are tested in In accordance accordance with, and maintained within the with the Diesel limits of, the Diesel Fuel Oil Testing Fuel Oil Program. Testing Program BRAIDWOOD - UNITS 1 &2 3.7.5 - 3 Amendment 165

CST 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the CST level is~ 66%. In accordance with the Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.7.6 - 2 Amendment 165

CC System 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 -------------------NOTE--------------------

Isolation of CC flow to individual components does not render the CC System inoperable.

Verify each CC manual and power operated In accordance valve in the flow path servicing safety with the related equipment, that is not locked, Surveillance sealed, or otherwise secured in position, Frequency is in the correct position. Control Program SR 3.7.7.2 Verify each Essential Service Water System In accordance manual and power operated valve directly with the serving the CC heat exchangers that is not Surveillance locked, sealed, or otherwise in the correct Frequency position, is in the correct position, or Control Program can be aligned to the correct position.

SR 3.7.7.3 Verify each required CC pump starts In accordance automatically on an actual or simulated with the actuation signal. Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.7.7 - 2 Amendment 165

VC Filtration System 3.7.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3. 7.10.2 Perform required VC Filtration System In accordance filter testing in accordance with the with the VFTP Ventilation Filter Testing Program (VFTP).

SR 3.7.10.3 Verify each VC Filtration System train In accordance actuates on an actual or simulated with the actuation signal. Surveillance Frequency Control Program SR 3.7.10.4 Perform required CRE unfiltered air In accordance inleakage testing in accordance with the with the Control Room Envelope Habitability Program. Control Room Envelope Habitability Program BRAIDWOOD - UNITS 1 &2 3.7.10 - 4 Amendment 165

Nonaccessible Area Exhaust Filter Plenum Ventilation System 3.7.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Operate each Nonaccessible Area Exhaust In accordance Filter Plenum Ventilation System train for with the

~ 15 minutes. Survei 11 ance Frequency Control Program SR 3.7.12.2 Perform required Nonaccessible Area Exhaust In accordance Filter Plenum Ventilation System filter with the VFTP testing in accordance with the Ventilation Filter Testing Program (VFTP).

SR 3.7.12.3 Verify each Nonaccessible Area Exhaust In accordance Filter Plenum Ventilation System train with the actuates on a manual, an actual, or a Surveillance simulated actuation signal. Frequency Control Program SR 3. 7.12.4 Verify two Nonaccessible Area Exhaust In accordance Filter Plenum Ventilation System trains can with the maintain a pressure~ -0.25 inches water Surveillance gauge relative to atmospheric pressure Frequency during the emergency mode of operation at a Control Program flow rate of~ 73,590 cfm per train.

BRAIDWOOD - UNITS 1 &2 3.7.12 - 2 Amendment 165

FHB Ventilation System 3.7.13 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two FHB Ventilation C.l Suspend movement of Immediately System trains RECENTLY IRRADIATED inoperable. FUEL assemblies in the fuel handling building.

AND C.2 --------NOTE---------

Only required with equipment hatch not intact.

Suspend movement of Immediately RECENTLY IRRADIATED FUEL assemblies in the containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each FHB Ventilation System train In accordance for~ 15 minutes. with the Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.7.13 - 3 Amendment 165

FHB Ventilation System 3.7.13 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.13.2 Perform required FHB Ventilation System In accordance filter testing in accordance with the with the VFTP Ventilation Filter Testing Program (VFTP).

SR 3.7.13.3 -------------------NOTE--------------------

Only required during movement of RECENTLY IRRADIATED FUEL assemblies with the equipment hatch not intact.

Verify one FHB Ventilation System train can In accordance maintain a pressure~ -0.25 inches water with the gauge relative to atmospheric pressure Surveillance during the emergency mode of operation. Frequency Control Program SR 3.7.13.4 Verify each FHB Ventilation System train In accordance actuates on an actual or simulated with the actuation signal. Survei 11 ance Frequency Control Program SR 3.7.13.5 -------------------NOTE--------------------

Only required during movement of RECENTLY IRRADIATED FUEL assemblies in the fuel handling building with the equipment hatch intact.

Verify one FHB Ventilation System train can In accordance maintain a pressure~ -0.25 inches water with the gauge relative to atmospheric pressure Surveillance during the emergency mode of operation at a Frequency flow rate~ 23,100 cfm. Control Program BRAIDWOOD - UNITS 1 &2 3.7.13 - 4 Amendment 165

Spent Fuel Pool Water Level 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool Water Level LCO 3.7.14 The spent fuel pool water level shall be~ 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel pool.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool water A.1 Suspend movement of Immediately level not within irradiated fuel limit. assemblies in the spent fuel pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the spent fuel pool water level is In accordance

~ 23 ft above the top of the irradiated with the fuel assemblies seated in the storage Surveillance racks. Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.7.14 - 1 Amendment 165

Spent Fuel Pool Boron Concentration 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Pool Boron Concentration LCO 3.7.15 The spent fuel pool boron concentration shall be~ 300 ppm.

APPLICABILITY: Whenever fuel assemblies are stored in the spent fuel pool.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool boron A.1 Suspend movement of Immediately concentration not fuel assemblies in within limit. the spent fuel pool.

AND A.2 Initiate action to Immediately restore spent fuel pool boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the spent fuel pool boron In accordance concentration is within limit. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.7.15-1 Amendment 165

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

A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met. Performance of SR 3.8.1.7 satisfies this SR.

Verify each DG starts from standby In accordance condition and achieves steady state voltage with the 2 3950 V and~ 4580 V and frequency 2 58.8 Surveillance Hz and~ 61.2 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 Surveillance 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 In accordance and operates for 2 60 minutes at a load with the 2 4950 kW and~ 5500 kW. Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.8.1 - 5 Amendment 165

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each day tank contains 2 450 gal of In accordance fuel oil. with the Survei 11 ance Frequency Control Program SR 3.8.1.5 Check for and remove accumulated water from In accordance each day tank. with the Surveillance Frequency Control Program SR 3.8.1.6 Verify the fuel oil transfer system In accordance operates to automatically transfer fuel oil with the from storage tank(s) to the day tank. Survei 11 ance Frequency Control Program SR 3.8.1.7 Verify each DG starts from normal standby In accordance condition and achieves: with the Surveillance

a. Ins 10 seconds, voltage 2 3950 V Frequency and frequency 2 58.8 Hz; and Control Program

b. Steady state voltage 2 3950 V and s 4580 V, and frequency 2 58.8 Hz ands 61.2 Hz.

SR 3.8.1.8 Verify manual transfer of AC power sources In accordance from the required normal qualified with the circuit(s) to the reserve required Surveillance qualified circuit(s). Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.8.1 - 6 Amendment 165

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11 -------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify on an actual or simulated loss of In accordance off site power signal: with the Surveillance

a. De-energization of ESF buses; Frequency Control Program

b. Load shedding from ESF buses; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in~ 10 seconds,

2. energizes auto-connected shutdown loads through the shutdown load sequence timers,

3. maintains steady state voltage

~ 3950 V and~ 4580 V,

4. maintains steady state frequency

~ 58.8 Hz and~ 61.2 Hz, and

5. supplies permanently connected and auto-connected shutdown loads for~ 5 minutes.

(continued)

BRAIDWOOD - UNITS 1 &2 3.8.1 - 8 Amendment 165

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.12 Verify on an actual or simulated Engineered In accordance Safety Feature (ESF) actuation signal each with the DG auto-starts from standby condition and: Surveillance Frequency

a. In~ 10 seconds achieves voltage Control Program 2 3950 V and frequency 2 58.8 Hz;

b. Achieves steady state voltage 2 3950 V and~ 4580 V and frequency 2 58.8 Hz and~ 61.2 Hz; and

c. Operates for 2 5 minutes.

SR 3.8.1.13 Verify each DG's automatic trips are In accordance bypassed on actual or simulated loss of with the voltage signal on the emergency bus Surveillance concurrent with an actual or simulated ESF Frequency actuation signal except: Control Program

a. Engine overspeed; and

b. Generator differential current.

SR 3.8.1.14 -------------------NOTE--------------------

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

Verify each DG operates for 2 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: In accordance with the

a. For 2 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 2 5775 kW and Surveillance

~ 6050 kW; and Frequency Control Program

b. For the remaining hours of the test loaded 2 4950 kW and~ 5500 kW.

(continued)

BRAIDWOOD - UNITS 1 &2 3.8.1 - 9 Amendment 165

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.15 -------------------NOTES-------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 2 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 2 4950 kW and~ 5500 kW or until operating temperature has stabilized.

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

Verify each DG starts and achieves: In accordance with the

a. In~ 10 seconds, voltage 2 3950 V Surveillance and frequency 2 58.8 Hz; and Frequency Control Program

b. Steady state voltage 2 3950 V and

~ 4580 V, and frequency 2 58.8 Hz and~ 61.2 Hz.

SR 3.8.1.16 -------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify each DG: In accordance with the

a. Synchronizes with offsite power source Surveillance while loaded with emergency loads upon Frequency a simulated restoration of offsite Control Program power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

(continued)

BRAIDWOOD - UNITS 1 &2 3.8.1 - 10 Amendment 165

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.17 -------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify, with a DG operating in test mode In accordance and connected to its bus, an actual or with the simulated ESF actuation signal overrides Survei 11 ance the test mode by: Frequency Control Program

a. Returning DG to ready-to-load operation; and

b. Automatically energizing the emergency load from offsite power.

SR 3.8.1.18 -------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify interval between each sequenced load In accordance block is within+/- 10% of design interval with the for each safeguards and shutdown sequence Surveillance timer. Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.8.1 - 11 Amendment 165

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.19 -------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify on an actual or simulated loss of In accordance offsite power signal in conjunction with an with the actual or simulated ESF actuation signal: Survei 11 ance Frequency

a. De-energization of ESF buses; Control Program

b. Load shedding from ESF buses; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads ins 10 seconds,

2. energizes auto-connected emergency loads through the safeguards sequence timers,

3. achieves steady state voltage 2 3950 V ands 4580 V,

4. achieves steady state frequency 2 58.8 Hz ands 61.2 Hz, and

5. supplies permanently connected and auto-connected emergency loads for 2 5 minutes.

SR 3.8.1.20 Verify when started simultaneously from In accordance standby condition, each DG achieves: with the Surveillance

a. Ins 10 seconds, voltage 2 3950 V Frequency and frequency 2 58.8 Hz; and Control Program

b. Steady state voltage 2 3950 V and s 4580 V, and frequency 2 58.8 Hz ands 61.2 Hz.

BRAIDWOOD - UNITS 1 &2 3.8.1 - 12 Amendment 165

Diesel Fuel Oil 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Declare associated DG Immediately associated Completion inoperable.

Time of Conditions A, B, or C not met.

OR One or more DGs with diesel fuel oil not within limits for reasons other than Condition A, B, or C.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each DG fuel oil storage tank(s) In accordance contains~ 44,000 gal of fuel. with the Surveillance Frequency Control Program SR 3.8.3.2 Verify fuel oil properties of new and In accordance stored fuel oil are tested in accordance with the Diesel with, and maintained within the limits of, Fuel Oil the Diesel Fuel Oil Testing Program. Testing Program SR 3.8.3.3 Check for and remove accumulated water from In accordance each fuel oil storage tank. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.8.3 - 2 Amendment 165

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater In accordance than or equal to the minimum established with the fl oat voltage. Surveillance Frequency Control Program SR 3.8.4.2 Verify each battery charger supplies a load In accordance equal to the manufacturer's rating at with the greater than or equal to the minimum Surveillance established float voltage for 2 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Frequency Control Program Verify each battery charger can recharge the battery to the fully charged state within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while supplying the largest coincident demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

SR 3.8.4.3 -------------------NOTES-------------------

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of the service test in SR 3.8.4.3.

2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify battery capacity is adequate to In accordance supply, and maintain OPERABLE status, the with the required emergency loads for the design Surveillance duty cycle when subjected to a battery Frequency service test. Control Program BRAIDWOOD - UNITS 1 &2 3.8.4 - 3 Amendment 165

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Declare associated Immediately associated Completion battery inoperable.

Time of Condition A, B, C, Dor E not met.

OR One battery with one or more cells with float voltage< 2.07 V and float current

> 3 amps.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 ------------------NOTE--------------------

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is In accordance

~ 3 amps. with the Surveillance Frequency Control Program SR 3.8.6.2 Verify each battery pilot cell float In accordance voltage is~ 2.07 V. with the Surveillance Frequency Control Program SR 3.8.6.3 Verify each battery cell electrolyte level In accordance is greater than or equal to minimum with the established design limits. Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.8.6 - 3 Amendment 165

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.4 Verify each battery pilot cell electrolyte In accordance temperature is greater than or equal to with the minimum established design limits. Survei 11 ance Frequency Control Program SR 3.8.6.5 Verify each battery cell float voltage is In accordance

, 2.07 V. with the Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 &2 3.8.6 - 4 Amendment 165

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.6 ------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify battery capacity is~ 80% of the In accordance manufacturer's rating when subjected to a with the performance discharge test or a modified Surveillance performance discharge test. Frequency Control Program 12 months when battery shows degradation or has reached 85%

of the expected life with capacity< 100%

of manufacturer's rating 24 months when battery has reached 85% of the expected life with capacity ~ 100%

of manufacturer's rating BRAIDWOOD - UNITS 1 &2 3.8.6 - 5 Amendment 165

Inverters-Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage and breaker In accordance alignment to AC instrument buses. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.8.7 - 2 Amendment 165

Distribution Systems-Operating 3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One AC electrical A.1 Restore AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power distribution power distribution subsystem inoperable. subsystem to OPERABLE AND status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCD B. One AC instrument bus B.1 Restore AC instrument 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power bus electrical power distribution subsystem distribution AND inoperable. subsystem to OPERABLE status. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCD C. One DC electrical C.l Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power distribution power distribution subsystem inoperable. subsystem to OPERABLE AND status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCD D. Required Action and 0.1 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, AND B, or C not met.

0.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

BRAIDWOOD - UNITS 1 &2 3.8.9 - 2 Amendment 104

Distribution Systems-Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two electrical power E.1 Enter LCO 3.0.3. Immediately 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 In accordance voltage to AC, DC, and AC instrument bus with the electrical power distribution subsystems. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.8.9 - 3 Amendment 165

Distribution Systems-Shutdown 3.8.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and In accordance voltage to required AC, DC, and AC with the instrument bus electrical power Survei 11 ance distribution subsystems. Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.8.10 - 4 Amendment 165

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCD 3.9.1 Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the limit specified in the COLR.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration A.l Suspend CORE Immediately not within limit. ALTERATI ONS.

A.2 Suspend positive Immediately reactivity additions.

AND A.3 Initiate action to Immediately restore boron concentration to with i n l i mit .

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the In accordance limit specified in the COLR. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.9.1 - 1 Amendment 165

Unborated Water Source Isolation Valves 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify each valve that isolates unborated In accordance water sources is secured in the closed with the position. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.9.2 - 2 Amendment 165

Nuclear Instrumentation 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Nuclear Instrumentation LCD 3.9.3 Two source range neutron flux monitors shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required source A.1 Suspend CORE Immediately range neutron flux ALTERATIONS.

monitor inoperable.

AND A.2 Suspend positive Immediately reactivity additions.

B. Two required source 8.1 Initiate action to Immediately range neutron flux restore one source monitors inoperable. range neutron flux monitor to OPERABLE status.

AND 8.2 Perform SR 3.9.1.1. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months BRAIDWOOD - UNITS 1 &2 3.9.3 - 1 Amendment 102

Nuclear Instrumentation 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.9.3.2 -------------------NOTE--------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. In accordance with the Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.9.3 - 2 Amendment 165

RHR and Coolant Circulation-High Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation and In accordance circulating reactor coolant at a flow rate with the of 2 1000 gpm. Survei 11 ance Frequency Control Program SR 3.9.5.2 Verify required RHR loop locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.9.5 - 2 Amendment 183

RHR and Coolant Circulation-Low Water Level 3.9.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR loop in B.l Suspend operations Imnediately operation. involving a reduction in reactor coolant boron concentration.

AND B.2 Initiate action to Imnediately restore one RHR loop to operation.

AND B.3 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and In accordance circulating reactor coolant at a flow rate with the of~ 1000 gpm. Surveillance Frequency Control Program SR 3.9.6.2 Verify correct breaker alignment and In accordance indicated power available to the required with the RHR pump that is not in operation. Surveillance Frequency Control Program SR 3.9.6.3 Verify RHR loop locations susceptible to In accordance gas accumulation are sufficiently filled with the with water. Survei 11 ance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.9.6 - 2 Amendment 183

Refueling Cavity Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Refueling Cavity Water Level LCD 3.9.7 Refueling cavity water level shall be maintained~ 23 ft above the top of reactor vessel flange.

APPLICABILITY: During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water A.l Suspend movement of Immediately level not within irradiated fuel limit. assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify refueling cavity water level is In accordance

~ 23 ft above the top of reactor vessel with the flange. Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.9.7 - 1 Amendment 165

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the Steam Generator Program shall include the following:

a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes. Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met.

b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE.

1. Structural integrity performance criterion: All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down), all anticipated transients included in the design specification, and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.

BRAIDWOOD - UNITS 1 &2 5.5 - 7 Amendment 172

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued)

2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG.

Leakage is not to exceed a total of 1 gpm for all SGs.

3. The operational LEAKAGE performance criteria is specified in LCO 3.4 .13, RCS Ope rational LEAKAGE.

11 11

c. Provisions for SG tube plugging criteria. Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal wall thickness shall be plugged. The following alternate tube plugging criteria shall be applied as an alternative to the 40% depth based criteria:

For Unit 2, tubes with service-induced flaws located greater than 14.01 inches below the top of the tubesheet do not require plugging. Tubes with service-induced flaws located in the portion of the tube from the top of the tubesheet to 14.01 inches below the top of the tubesheet shall be plugged upon detection.

BRAIDWOOD - UNITS 1 &2 5.5 - 8 Amendment 172

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued) ct. Provisions for SG tube inspections. Periodic SG tube inspections shall be performed. The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy the applicable tube plugging criteria. For Unit 2, portions of the tube below 14.01 inches from the top of the tubesheet are excluded from this requirement.

The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.l, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection. A degradation assessment shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.

1. Inspect 100% of the tubes in each SG during the first refueling outage following SG installation.

2. For Unit 1, after the first refueling outage following SG installation, inspect each SG at least every 72 effective full power months or at least every third refueling outage (whichever results in more frequent inspections). In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection period as defined in a, b, c, and d below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated.

The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be inspected in the inspection period after the determination that a new form of degradation could BRAIDWOOD - UNITS 1 &2 5.5 - 9 Amendment 172

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued) potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage.

a) After the first refueling outage following SG installation, inspect 100% of the tubes during the next 144 effective full power months. This constitutes the first inspection period; b) During the next 120 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period; c) During the next 96 effective full power months, inspect 100% of the tubes. This constitutes the third inspection period; and ct) During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the fourth and subsequent inspection periods.

3. For Unit 2, after the first refueling outage following SG installation, inspect each SG at least every 48 effective full power months or at least every other refueling outage (whichever results in more frequent inspections). In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection period as defined in a, b, and c below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated.

The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be BRAIDWOOD - UNITS 1 &2 5.5 - 10 Amendment 172

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator CSG) Program (continued) inspected in the inspection period after the determination that a new form of degradation could potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage.

a) After the first refueling outage following SG installation, inspect 100% of the tubes during the next 120 effective full power months. This constitutes the first inspection period; b) During the next 96 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period; and c) During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the third and subsequent inspection periods.

4. For Unit 1, if crack indications are found in any SG tube, then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections). For Unit 2, if crack indications are found in any SG tube from 14.01 inches below the top of the tubesheet on the hot leg side to 14.01 inches below the top of the tubesheet on the cold leg side, then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections).

If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.

e. Provisions for monitoring operational primary to secondary LEAKAGE.

BRAIDWOOD - UNITS 1 &2 5.5 - 11 Amendment 172

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.19 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.

BRAIDWOOD - UNITS 1 &2 5.5 - 24 Amendment 165

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.8 Tendon Surveillance Report Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Summary Report in accordance with 10 CFR 50.55a and ASME Section XI.

5.6.9 Steam Generator (SG) Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Specification 5.5.9, Steam Generator (SG) Program.

The report shall include:

a. The scope of inspections performed on each SG,

b. Degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged during the inspection outage for each degradation mechanism, I

f. The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing, BRAIDWOOD - UNITS 1 &2 5.6 - 6 Amendment 172

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.9 Steam Generator (SG) Tube Inspection Report (continued)

h. For Unit 2, the operational primary to secondary leakage rate!

observed (greater than three gallons per day) in each steam generator (if it is not practical to assign the leakage to an individual steam generator, the entire primary to secondary leakage should be conservatively assumed to be from one steam generator) during the cycle preceding the inspection which is the subject of the report,

i. For Unit 2, the calculated accident induced leakage rate from I the portion of the tubes below 14.01 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. In addition, if the calculated accident induced leakage rate from the most limiting accident is less than 3.11 times the maximum operational primary to secondary leakage rate, the report should describe how it was determined, and

j. For Unit 2, the results of monitoring for tube axial displacement (slippage). If slippage is discovered, the implications of the discovery and corrective action shall be provided.

BRAIDWOOD - UNITS 1 &2 5.6 - 7 Amendment 172

BYRON STATION, UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-456 CORRECTION TO AMENDMENT NUMBER IDENTIFICATION FORMAT Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The corrected pages change the format of the amendment number identification and don't change the amendment number.

Remove TSs TSs 1.1-4 1.1-4 1.3-1 1.3-1 1.3-2 1.3-2 1.3-3 1.3-3 3.0-2 3.0-2 3.0-6 3.0-6 3.1.1-1 3.1.1-1 3.1.2-2 3.1.2-2 3.1.4-4 3.1.4-4 3.1.5-2 3.1.5-2 3.1.6-2 3.1.6-2 3.1.6-3 3.1.6-3 3.1.8-2 3.1.8-2 3.2.1-3 3.2.1-3 3.2.1-5 3.2.1-5 3.2.1-6 3.2.1-6 3.2.2-3 3.2.2-3 3.2.3-1 3.2.3-1 3.2.4-4 3.2.4-4 3.2.5-1 3.2.5-1 3.3.1-3 3.3.1-3 3.3.1-4 3.3.1-4 3.3.1-5 3.3.1-5 3.3.2-3 3.3.2-3 3.3.2-7 3.3.2-7 3.3.3-3 3.3.3-3 3.3.4-2 3.3.4-2 3.3.7-2 3.3.7-2 3.3.8-3 3.3.8-3 3.3.9-3 3.3.9-3 3.3.9-4 3.3.9-4 3.3.9-5 3.3.9-5 3.4.2-1 3.4.2-1 3.4.3-2 3.4.3-2 3.4.4-1 3.4.4-1 Enclosure 3

TSs (continued) TSs (continued) 3.4.5-3 3.4.5-3 3.4.5-4 3.4.5-4 3.4.6-2 3.4.6-2 3.4.6-3 3.4.6-3 3.4.7-3 3.4.7-3 3.4.7-4 3.4.7-4 3.4.8-2 3.4.8-2 3.4.9-2 3.4.9-2 3.4.10-2 3.4.10-2 3.4.11-3 3.4.11-3 3.4.12-4 3.4.12-4 3.4.12-5 3.4.12-5 3.4.13-2 3.4.13-2 3.4.14-3 3.4.14-3 3.4.14-4 3.4.14-4 3.4.16-2 3.4.16-2 3.4.17-2 3.4.17-2 3.4.19-1 3.4.19-1 3.4.19-2 3.4.19-2 3.5.1-2 3.5.1-2 3.5.2-3 3.5.2-3 3.5.2-4 3.5.2-4 3.5.4-2 3.5.4-2 3.5.5-2 3.5.5-2 3.6.2-5 3.6.2-5 3.6.3-5 3.6.3-5 3.6.3-6 3.6.3-6 3.6.4-1 3.6.4-1 3.6.5-1 3.6.5-1 3.6.6-2 3.6.6-2 3.6.6-3 3.6.6-3 3.6.6-4 3.6.6-4 3.6.7-1 3.6.7-1 3.6.7-2 3.6.7-2 3.7.2-3 3.7.2-3 3.7.3-1 3.7.3-1 3.7.4-2 3.7.4-2 3.7.5-2 3.7.5-2 3.7.5-3 3.7.5-3 3.7.6-2 3.7.6-2 3.7.7-2 3.7.7-2 3.7.8-3 3.7.8-3 3.7.12-2 3.7.12-2 3.7.13-3 3.7.13-3 3.7.13-4 3.7.13-4 3.7.14-1 3.7.14-1 3.7.15-2 3.7.15-2 3.8.1-9 3.8.1-9 3.8.1-10 3.8.1-10 3.8.1-11 3.8.1-11

TSs (continued) TSs (continued) 3.8.1-12 3.8.1-12 3.8.3-2 3.8.3-2 3.8.4-3 3.8.4-3 3.8.6-3 3.8.6-3 3.8.6-4 3.8.6-4 3.8.7-2 3.8.7-2 3.8.8-2 3.8.8-2 3.8.9-3 3.8.9-3 3.8.10-4 3.8.10-4 3.9.1-1 3.9.1-1 3.9.2-2 3.9.2-2 3.9.3-1 3.9.3-1 3.9.3-2 3.9.3-2 3.9.5-2 3.9.5-2 3.9.6-2 3.9.6-2 3.9.6-3 3.9.6-3 3.9.7-1 3.9.7-1 5.5-6 5.5-6 5.5-7 5.5-7 5.5-8 5.5-8 5.5-9 5.5-9 5.5-10 5.5-10 5.5-11 5.5-11 5.5-24 5.5-24 5.6-6 5.6-6 5.6-7 5.6-7

Definitions 1.1 1.1 Definitions INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE, such as that from pump seals or valve packing (except Reactor Coolant pump (RCP) seal water injection or leakoff),

that is captured and conducted to collection systems or a sump or collecting tank;

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; or

3. Reactor Coolant System (RCS) LEAKAGE through a Steam Generator to the Secondary System (primary to secondary LEAKAGE);

b. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE;

c. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.

MASTER RELAY TEST A MASTER RELAY TEST shall consist of energizing each master relay and verifying the OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

BYRON - UNITS 1 &2 1.1 - 4 Amendment 197

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCD state Conditions that typically describe the ways in which the requirements of the LCD can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the LCD. Unless otherwise specified, the Completion Time begins when a senior licensed operator on the operating shift crew with responsibility for plant operations makes the determination that an LCD is not met and an ACTIONS Condition is entered. The "otherwise specified" exceptions are varied, such as a Required Action Note or Surveillance Requirement Note that provides an alternative time to perform specific tasks, such as testing, without starting the Completion Time. While utilizing the Note, should a Condition be applicable for any reason not addressed by the Note, the Completion Time begins. Should the time allowance in the Note be exceeded, the Completion Time begins at that point. The exceptions may also be incorporated into the Completion Time. For example, LCD 3.8.1, "AC Sources - Operating," Required Action B.3, requires declaring required feature(s) supported by an inoperable diesel generator, inoperable when the redundant required feature(s) are inoperable. The Completion Time states, "4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition B concurrent with inoperability of redundant required feature(s)." In this case the Completion Time does not begin until the conditions in the Completion Time are satisfied. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCD Applicability.

If situations are discovered that require entry into more BYRON - UNITS 1 &2 1.3 - 1 Amendment 200

Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued) than one Condition at a time within a single LCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the discovery of the situation that required entry into the Condition, unless otherwise specified.

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

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

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

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

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

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

BYRON - UNITS 1 &2 1.3 - 2 Amendment 200

Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . . . " Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Conditions A and Bin Example 1.3-3 may not be extended.

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

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.l 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 8.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition Bis entered.

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

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

BYRON - UNITS 1 &2 1.3 - 3 Amendment 200

LCD Applicability 3.0 3.0 LCD Applicability LCD 3.0.4 When an LCD is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

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

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

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

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

LCD 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCD 3.0.2 for the system returned to service under administrative control to perform the required testing to demonstrate OPERABILITY.

BYRON - UNITS 1 &2 3.0 - 2 Amendment 200

SR Applicability 3.0 3.0 SR APPLICABILITY SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. The delay period is only applicable when there is a reasonable expectation the surveillance will be met when performed. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

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

SR 3.0.5 SRs shall apply to each unit individually, unless otherwise indicated.

BYRON - UNITS 1 &2 3.0 - 6 Amendment 200

SOM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SOM)

LCO 3.1.1 SOM shall be within the limits specified in the COLR.

APPLICABILITY: MODE 2 with keff < 1.0, MODES 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SOM not within limit. A.1 Initiate boration to 15 minutes restore SOM to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SOM is within the limits specified In accordance in the COLR. with the Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.1.1-1 Amendment 171

Core Reactivity 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify measured core reactivity is within Prior to

+/- 1% ~k/k of predicted values. entering MODE 1 after each refueling SR 3.1.2.2 -------------------NOTES-------------------

1. Only required to be performed after 60 Effective Full Power Days (EFPD).

2. The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 EFPD after each fuel loading.

Verify measured core reactivity is within In accordance

+/- 1% ~k/k of predicted values. with the Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.1.2 - 2 Amendment 171

Rod Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 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 B or Required Action C.3 not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within In accordance alignment limit. with the Survei 11 ance Frequency Control Program SR 3.1.4.2 Verify rod freedom of movement In accordance (trippability) by moving each rod not fully with the inserted in the core~ 10 steps in either Surveillance direction. Frequency Contra l Program SR 3.1.4.3 Verify rod drop time of each rod, from the Prior to fully withdrawn position, is~ 2.7 seconds criticality from the beginning of decay of stationary after each gripper coil voltage to dashpot entry, removal of the with: reactor head

a. Tavg ~ 550°F; and

b. All reactor coolant pumps operating.

BYRON - UNITS 1 &2 3.1.4 - 4 Amendment 171

Shutdown Bank Insertion Limits 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1. 5.1 Verify each shutdown bank is within the In accordance insertion limits specified in the COLR. with the Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.1.5-2 Amendment 171

Control Bank Insertion Limits 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Control bank sequence B.1.1 Verify SOM is within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or overlap limits not the limits specified met. in the COLR.

OR B.1.2 Initiate boration to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore SOM to within limit.

AND B.2 Restore control bank 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months sequence and overlap to within limits.

C. Required Action and C.l Be in MODE 2 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion keff < 1.0.

Ti me not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify estimated critical control bank Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months position is within the limits specified in prior to the COLR. criticality SR 3.1.6.2 Verify each control bank is within the In accordance insertion limits specified in the COLR. with the Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.1.6 - 2 Amendment 171

Control Bank Insertion Limits 3.1.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.6.3 Verify each control bank not fully In accordance withdrawn from the core is within the with the sequence and overlap limits specified in Survei 11 ance the COLR. Frequency Control Program BYRON - UNITS 1 &2 3.1.6-3 Amendment 171

PHYSICS TESTS Exceptions-MODE 2 3.1.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. RCS lowest loop C.l Restore RCS lowest 15 minutes average temperature loop average not within limit. temperature to within limit.

D. Required Action and 0.1 Be in MODE 3. 15 minutes associated Completion Time of Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Perform CHANNEL OPERATIONAL TEST on power Prior to range and intermediate range channels per initiation of SR 3.3.1.7, SR 3.3.1.8, and PHYSICS TESTS Table 3.3.1.1-1.

SR 3.1.8.2 Verify the RCS lowest loop average In accordance temperature is~ 530°F. with the Surveillance Frequency Control Program SR 3.1.8.3 Verify THERMAL POWER is s 5% RTP. In accordance with the Surveillance Frequency Control Program SR 3.1.8.4 Verify SOM is within the limits specified In accordance in the COLR. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.1.8 - 2 Amendment 171

F0(Z) 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 -------------------NOTES-------------------

1. During power escalation at the beginning of each cycle, THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution map is obtained.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring Power Distribution Monitoring System (PDMS) inoperable. Performance of SR 3.2.1.3 satisfies the initial performance of this SR after declaring PDMS inoperable.

Verify Fg (Z) is within limit specified in Prior to the COLR. exceeding 75% RTP after each refueling Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by

~ 10% RTP, the THERMAL POWER at which F~(Z) was last verified AND In accordance with the Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.2.1 - 3 Amendment 171

Fq(Z) 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.2 (continued)

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

3. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring PDMS inoperable. Performance of SR 3.2.1.4 satisfies the initial performance of this SR after declaring PDMS inoperable.

Verify F~(Z) is within limit specified in Prior to the COLR. exceeding 75% RTP after each refueling Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by 2 10% RTP, the THERMAL POWER at which *F~ (Z) was last verified In accordance with the Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.2.1 - 5 Amendment 171

F0( Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.3 -------------------NOTE--------------------

Only required to be performed when PDMS is OPERABLE.

Verify F~(Z) is within limit specified in In accordance the COLR. with the Surveillance Frequency Control Program SR 3.2.1.4 -------------------NOTE--------------------

Only required to be performed when PDMS is OPERABLE.

Verify Ft(Z) is within limit specified in In accordance the COLR. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.2.1 - 6 Amendment 171

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring PDMS inoperable.

Performance of SR 3.2.2.2 satisfies the initial performance of this SR after declaring PDMS inoperable.

Verify F:H is within limits specified in the Prior to COLR. exceeding 75% RTP after each refueling In accordance with the Surveillance Frequency Control Program SR 3.2.2.2 -------------------NOTE--------------------

Only required to be performed when PDMS is OPERABLE.

Verify F:H is within limit specified in the In accordance COLR. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.2.2 - 3 Amendment 171

AFD 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCD 3.2.3 The AFD shall be maintained within the limits specified in the COLR.

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

The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.

APPLICABILITY: MODE 1 with THERMAL POWER~ 50% RTP when Power Distribution Monitoring System (PDMS) is inoperable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AFD not within limits. A.l Reduce THERMAL POWER 30 minutes to < 50% RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring PDMS inoperable.

Verify AFD is within limits for each In accordance OPERABLE excore channel. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.2.3 - 1 Amendment 171

QPTR 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 ------------------NOTES--------------------

1. With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER~ 75% RTP, the remaining three power range channel inputs can be used for calculating QPTR.

2. SR 3.2.4.2 may be performed in lieu of this Surveillance.

3. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring PDMS inoperable.

Verify QPTR is~ 1.02 by calculation. In accordance with the Survei 11 ance Frequency Control Program SR 3.2.4.2 -------------------NOTES-------------------

1. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after input from one Power Range Neutron Flux channel is inoperable with THERMAL POWER

> 75% RTP.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after declaring PDMS inoperable.

Verify QPTR is~ 1.02 using the movable In accordance incore detectors. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.2.4 - 4 Amendment 171

DNBR 3.2.5 3.2 POWER DISTRIBUTION LIMITS 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)

LCD 3.2.5 DNBR shall be within the limit specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER~ 50% RTP when Power Distribution Monitoring System (PDMS) is OPERABLE.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DNBR not within limit. A.1 Restore DNBR to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months within limit.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 50% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.5.1 Verify DNBR is within limit specified in In accordance the COLR. with the Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.2.5 - 1 Amendment 171

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One Power Range ------------NOTE-------------

Neutron Flux-High One channel may be bypassed channel inoperable. 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.

D.l Pl ace channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

OR D.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months E. One channel -------------NOTE------------

inoperable. One 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.

E.l Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

OR E.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

BYRON - UNITS 1 &2 3.3.1 - 3 Amendment 186

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. One Intermediate Range F.l Reduce THERMAL POWER 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Neutron Flux channel to< P-6.

inoperable.

OR F.2 Increase THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to> P-10.

G. Two Intermediate Range G.1 Suspend operations Immediately Neutron Flux channels involving positive inoperable. reactivity additions.

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

H. One Source Range H.l Suspend operations Immediately Neutron Flux channel involving positive inoperable. reactivity additions.

I. Two Source Range I.1 Open Reactor Trip Immediately Neutron Flux channels Breakers (RTBs).

inoperable.

(continued)

BYRON - UNITS 1 &2 3.3.1 - 4 Amendment 186

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J. One Source Range J.l Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Neutron Flux channel OPERABLE status.

inoperable.

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

AND J.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.

K. One channel ------------NOTES------------

inoperable. 1. For Functions with installed bypass test capability (Functions 8a, 9, 10), one 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.

2. For Functions with no installed bypass test capability (Functions 12 and 13), 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 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

OR K.2 Reduce THERMAL POWER 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months to< P-7.

(continued)

BYRON - UNITS 1 &2 3.3.1 - 5 Amendment 186

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One channel D.l --------NOTE---------

inoperable. One 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.

Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

OR D.2.1 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND D. 2. 2 Be i n MODE 4 . 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

BYRON - UNITS 1 &2 3.3.2 - 3 Amendment 186

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

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

inoperable. One 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.

Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

OR K.2.1 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND K. 2. 2 Be in MODE 5. 108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months (continued)

BYRON - UNITS 1 &2 3.3.2 - 7 Amendment 186

PAM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. ---------NOTE--------- G.l Initiate action in Immediately Only applicable to accordance with Functions 11, 12, and Specification 5.6.7.

14.

Required Action and associated Completion Time of Condition Dor E not met.

SURVEILLANCE REQUIREMENTS

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

SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required In accordance instrumentation channel that is normally with the energized. Surveillance Frequency Control Program SR 3.3.3.2 -------------------NOTE--------------------

Radiation detectors for Function 11, Containment Area Radiation, are excluded.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.3.3 - 3 Amendment 171

Remote Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL CHECK for each required In accordance instrumentation channel that is normally with the energized. Survei 11 ance Frequency Control Program SR 3.3.4.2 -------------------NOTE--------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each In accordance required instrumentation channel. with the Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.3.4 - 2 Amendment 171

VC Filtration System Actuation Instrumentation 3.3.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.l Suspend movement of Immediately associated Completion i rradi ated fuel Time of Condition A assemblies.

or B not met during movement of irradiated fuel assemblies.

E. Required Action and E.l Initiate action to Immediately associated Completion restore one VC Time of Condition A Filtration System or B not met in MODE 5 train to OPERABLE or 6. status.

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.7-1 to determine which SRs apply for each VC Filtration System Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.2 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.7.3 Perform CHANNEL CALIBRATION. In accordance with the Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.3.7 - 2 Amendment 171

FHB Ventilation System Actuation Instrumentation 3.3.8 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.8-1 to determine which SRs apply for each FHB Ventilation System Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.8.1 Perform CHANNEL CHECK. In accordance with the Survei 11 ance Frequency Control Program SR 3.3.8.2 Perform COT. In accordance with the Survei 11 ance Frequency Control Program SR 3.3.8.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.3.8 - 3 Amendment 171

BOPS 3.3.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.9.1 Verify one or more reactor coolant pump(s) In accordance in operation. with the Surveillance Frequency Control Program SR 3.3.9.2 Verify each RCS loop isolation valve is In accordance open. with the Surveillance Frequency Control Program SR 3.3.9.3 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.9.4 Verify each Boron Dilution Alert channel In accordance selector switch is in the Normal position. with the Survei 11 ance Frequency Control Program SR 3.3.9.5 Verify each manual, ~ower operated, and In accordance automatic valve int e flow path, that is with the not locked, sealed, or otherwise secured in Surveillance position, is in the correct position. Frequency Control Program SR 3.3.9.6 Perform COT. In accordance with the Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.3.9 - 3 Amendment 171

BOPS 3.3.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.9.7 -------------------NOTE--------------------

The CHANNEL CALIBRATION is only required to include that portion of the channel associated with the Boron Dilution Alert function.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Contra l Program BYRON - UNITS 1 &2 3.3.9 - 4 Amendment 171

BOPS 3.3.9 Table 3.3.9-1 (page 1 of 1)

Boron Dilution Protection System Instrurrentation3 FUNCTION REQUIRED CHANNELS SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE Boron Dilution Alert Channels Volume Control Tank Level High 2 SR 3.3.9.3 ~ 71.15%

SR 3.3.9.6 SR 3.3.9.7 BYRON - UNITS 1 &2 3.3.9 - 5 Amendment 171

RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCD 3.4.2 Each RCS loop average temperature <Tavg) shall be~ 550°F.

APPLICABILITY: MODE 1, MODE 2 with keff ~ 1. 0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tavg in one or more RCS A.1 Be in MODE 2 with 30 minutes loops not within keff< 1.0.

limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each loop ~ 550°F. In accordance with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.4.2 - 1 Amendment 171

RCS P/T Limits 3.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ---------NOTE--------- C.l Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed to within limits.

whenever this Condition is entered. AND C.2 Determine RCS is Prior to Requirements of LCO acceptable for entering MODE 4 not met any time other continued operation.

than in MODE 1, 2, 3, or 4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 -------------------NOTE--------------------

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and In accordance RCS heatup and cooldown rates are within with the the limits specified in the PTLR. Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.4.3 - 2 Amendment 171

RCS Loops-MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops-MODES 1 and 2 LCO 3.4.4 Four RCS loops shall be OPERABLE and in operation.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of A.l Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months LCO not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation. In accordance with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.4.4 - 1 Amendment 171

RCS Loops-MODE 3 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.l Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition D not met.

F. Two required RCS loops F.l Initiate action to Immediately inoperable. place the Rod Control System in a condition incapable of rod withdrawal.

AND F.2 Suspend all Immediately operations involving a reduction of RCS boron concentration.

AND F.3 Initiate action to Immediately restore one RCS loop to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify each required RCS loop is in In accordance operation. with the Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.4.5 - 3 Amendment 171

RCS Loops-MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.5.2 Verify steam generator secondary side In accordance narrow range water level is 2 18% for each with the required RCS loop. Surveillance Frequency Control Program SR 3.4.5.3 Verify correct breaker alignment and In accordance indicated power are available to each with the required pump that is not in operation. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.4.5 - 4 Amendment 171

RCS Loops-MODE 4 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One required loop B.l Initiate action to Irrrnediately inoperable. restore a second loop to OPERABLE status.

AND B.2 --------NOTE---------

Only required if RHR loop is OPERABLE.

Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. Two required loops C.l Suspend all Irrrnediately inoperable. operations involving a reduction of RCS boron concentration.

AND C.2 Initiate action to Irrrnediately restore one loop to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify required RHR or RCS loop is in In accordance operation. with the Surveillance Frequency Control Program SR 3.4.6.2 Verify SG secondary side narrow range water In accordance level is~ 18% for each required RCS loop. with the Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.4.6 - 2 Amendment 171

RCS Loops-MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.6.3 Verify correct breaker alignment and In accordance indicated power are available to each with the required pump that is not in operation. Surveillance Frequency Control Program SR 3.4.6.4 -------------------NOTE-------------------

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

Verify required RHR loop locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.4.6 - 3 Amendment 189

RCS Loops-MODE 5, Loops Filled 3.4. 7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two required RHR loops D.l Suspend all Irrrnediately inoperable. operations involving a reduction of RCS OR boron concentration.

Required RHR loop AND inoperable and one or both required SG D.2.1 Initiate action to Irrrnediately secondary side water restore one RHR loop level(s) not within to OPERABLE status.

limits.

OR D.2.2 Initiate action to Irrrnediately restore required SG secondary side water level(s) to within limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required RHR loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4.7.2 Verify SG secondary side narrow range water In accordance level is~ 18% in required SGs. with the Surveillance Frequency Control Program SR 3.4.7.3 Verify correct breaker alignment and In accordance indicated power are available to each with the required RHR pump that is not in operation. Survei 11 ance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.4.7 - 3 Amendment 189

RCS Loops-MODE 5, Loops Filled 3.4. 7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4. 7.4 Verify required RHR loop locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.4.7 - 4 Amendment 189

RCS Loops-MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)

CONDITION REQU I RED ACTION COMPLETION TIME B. One required RHR loop B.1 Initiate action to Irrrnediately inoperable. restore RHR loop to OPERABLE status.

C. Two required RHR loops C.l Suspend all Irrrnediately inoperable. operations involving reduction in RCS boron concentration.

AND C.2 Initiate action to Inmediately restore one RHR loop to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify required RHR loop is in operation. In accordance with the Survei 11 ance Frequency Control Program SR 3.4.8.2 Verify correct breaker alignment and In accordance indicated power are available to each with the required RHR pump that is not in operation. Surveillance Frequency Control Program SR 3.4.8.3 Verify RHR loop locations susceptible to In accordance gas accumulation are sufficiently filled with the with water. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.4.8 - 2 Amendment 189

Pressurizer 3.4.9 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 B AND not met.

C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is~ 92%. In accordance with the Surveillance Frequency Control Program SR 3.4.9.2 Verify capacity of each required group of In accordance pressurizer heaters is~ 150 kW. with the Surveillance Frequency Control Program SR 3.4.9.3 Verify required pressurizer heaters are In accordance capable of being powered from an ESF power with the supply. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.4.9 - 2 Amendment 171

Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is In accordance OPERABLE in accordance with the INSERVICE with the TESTING PROGRAM. Following testing, lift INSERVICE settings shall be within+/- 1%. TESTING PROGRAM BYRON - UNITS 1 &2 3.4.10-2 Amendment 197

Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 -------------------NOTE--------------------

Not required to be met with block valve closed in accordance with the Required Action of Condition B or E.

Perform a complete cycle of each block In accordance valve. with the Surveillance Frequency Control Program SR 3.4.11.2 -------------------NOTE--------------------

Only required to be performed in MODES 1 and 2.

Perform a complete cycle of each PORV. In accordance with the Surveillance Frequency Contra l Program SR 3.4.11.3 Perform a complete cycle of each solenoid In accordance air control valve and check valve on the with the air accumulators in PORV control systems. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.4.11 - 3 Amendment 171

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify no SI pump is capable of injecting In accordance into the RCS. with the Surveillance Frequency Control Program SR 3.4.12.2 Verify a maximum of one charging pump In accordance (centrifugal) is capable of injecting into with the the RCS. Surveillance Frequency Control Program SR 3.4.12.3 -------------------NOTE--------------------

Only required to be met for accumulator whose pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.

Verify each accumulator is isolated. In accordance with the Surveillance Frequency Control Program SR 3.4.12.4 Verify required RCS vent 2 2.0 square In accordance inches open. with the Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.4.12 - 4 Amendment 171

LTOP System 3 .4 .12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.5 Verify RHR suction valves are open for each In accordance required RHR suction relief valve. with the Surveillance Frequency Control Program SR 3.4.12.6 Verify PORV block valve is open for each In accordance required PORV. with the Surveillance Frequency Control Program SR 3.4.12.7 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after decreasing RCS cold leg temperature to s 350°F.

Perform a COT on each required PORV, In accordance excluding actuation. with the Surveillance Frequency Control Program SR 3.4.12.8 Perform CHANNEL CALIBRATION for each In accordance required PORV actuation channel. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.4.12 - 5 Amendment 171

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 -------------------NOTES-------------------

1. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

2. Not applicable to primary to secondary LEAKAGE.

Verify RCS operational LEAKAGE is within In accordance limits by performance of RCS water with the inventory balance. Surveillance Frequency Control Program SR 3.4.13.2 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Verify primary to secondary LEAKAGE is In accordance

~ 150 gallons per day through any one SG. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.4.13 - 2 Amendment 171

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 -------------------NOTES-------------------

1. Only required to be performed in MODES 1 and 2.

2. RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided.

3. Not required to be performed for RH8701A and Band RH8702A and Bon the Frequency required following valve actuation or flow through the valve.

Verify leakage from each RCS PIV is In accordance equivalent to s 0.5 gpm per nominal inch of with the valve size up to a maximum of 5 gpm at an INSERVICE RCS pressure~ 2215 psig ands 2255 psig. TESTING PROGRAM, and in accordance with the Surveillance Frequency Control Program Prior to entering MODE 2 whenever the unit has been in MODE 5 for

~ 7 days, if leakage testing has not been performed once within the previous 9 months (continued)

BYRON - UNITS 1 &2 3.4.14 - 3 Amendment 197

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 (continued) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or fl ow through the valve SR 3.4.14.2 Verify RHR System suction isolation valve In accordance interlock prevents the valves from being with the opened with a simulated or actual RCS Surveillance pressure signal~ 360 psig. Frequency Control Program BYRON - UNITS 1 &2 3.4.14 - 4 Amendment 171

RCS Specific Activity 3.4.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.l 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 AND or B not met.

C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR DOSE EQUIVALENT I-131

> 60 µCi/gm.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant DOSE EQUIVALENT In accordance XE-133 specific activity s 603 µCi/gm. with the Surveillance Frequency Control Program SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT In accordance I-131 specific activity s 1.0 µCi/gm. with the Survei 11 ance Frequency Control Program Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of

~ 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period BYRON - UNITS 1 &2 3.4.16 - 2 Amendment 171

RCS Loop Isolation Valves 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify each RCS loop isolation valve is In accordance open and power is removed from each loop with the isolation valve operator. Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.4.17 - 2 Amendment 171

SG Tube Integrity 3.4.19 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.19 Steam Generator (SG) Tube Integrity LCO 3.4.19 SG tube integrity shall be maintained.

AND All SG tubes satisfying the tube plugging criteria shall be plugged in accordance with the Steam Generator Program.

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

ACTIONS

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

Separate Condition entry is allowed for each SG tube.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes A.1 Verify tube integrity 7 days satisfying the tube of the affected plugging criteria and tube(s) is maintained not plugged in until the next accordance with the refueling outage or Steam Generator SG tube inspection.

Program.

AND A.2 Plug the affected Prior to tube(s) in accordance entering MODE 4 with the Steam following the Generator Program. next refueling outage or SG tube inspection 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 AND not met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR SG tube integrity not maintained.

BYRON - UNITS 1 &2 3.4.19 - 1 Amendment 179

SG Tube Integrity 3.4.19 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.19.1 Verify SG tube integrity in accordance with In accordance the Steam Generator Program. with the Steam Generator Program SR 3.4.19.2 Verify that each inspected SG tube that Prior to satisfies the tube plugging criteria is entering MODE 4 plugged in accordance with the Steam following a SG Generator Program. tube inspection BYRON - UNITS 1 &2 3.4.19 - 2 Amendment 179

Accumulators 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is In accordance fully open. with the Surveillance Frequency Contra l Program SR 3.5.1.2 Verify borated water level in each In accordance accumulator is 2 31% ands 63%. with the Survei 11 ance Frequency Contra l Program SR 3.5.1.3 Verify nitrogen cover pressure in each In accordance accumulator is 2 602 psig ands 647 psig. with the Surveillance Frequency Control Program SR 3.5.1.4 Verify boron concentration in each In accordance accumulator is 2 2200 ppm ands 2400 ppm. with the Survei 11 ance Frequency Contra l Program SR 3.5.1.5 -------------------NOTE--------------------

Only required to be performed for affected accumulators after each solution volume increase of 2 10% of indicated level that is not the result of addition from the refueling water storage tank containing a boron concentration 2 2200 ppm and s 2400 ppm.

Verify boron concentration in each Once within accumulator is 2 2200 ppm ands 2400 ppm. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SR 3.5.1.6 Verify power is removed from each In accordance accumulator isolation valve operator. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.5.1 - 2 Amendment 171

ECCS-Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves are in the In accordance listed position with power to the valve with the operator removed: Survei 11 ance Frequency Number Position Function Control Program MOV SI8806 Open Suction to SI Pumps MOV SI8835 Open SI Pump Discharge to Reactor Coolant System (RCS) Cold Legs MOV SI8813 Open SI Pump Recirculation to the Refueling Water Storage Tank MOV SI8809A Open RHR Pump Discharge to RCS Cold Legs MOV SI8809B Open RHR Pump Discharge to RCS Cold Legs MOV SI8840 Closed RHR Pump Discharge to RCS Hot Legs MOV SI8802A Closed SI Pump Discharge to RCS Hot Legs MOV SI8802B Closed SI Pump Discharge to RCS Hot Legs SR 3.5.2.2 -------------------NOTE-------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each ECCS manual, power operated, In accordance and automatic valve in the flow path, that with the is not locked, sealed, or otherwise secured Surveillance in position, is in the correct position. Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.5.2 - 3 Amendment 189

ECCS-Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify ECCS locations susceptible to gas In accordance accumulation are sufficiently filled with with the water. Surveillance Frequency Control Program SR 3.5.2.4 Verify each ECCS pump's developed head at In accordance the test flow point is greater than or with the equal to the required developed head. INSERVICE TESTING PROGRAM SR 3.5.2.5 Verify each ECCS automatic valve in the In accordance flow path that is not locked, sealed, or with the otherwise secured in position, actuates to Surveillance the correct position on an actual or Frequency simulated actuation signal. Control Program SR 3.5.2.6 Verify each ECCS pumf starts automatically In accordance on an actual or simu ated actuation signal. with the Surveillance Frequency Control Program SR 3.5.2.7 Verify, for each ECCS throttle valve listed In accordance below, each position stop is in the correct with the position: Surveillance Frequency Valve Number Valve Function Control Program SI8810 A,B,C,D Centrifugal Charging System SI8816 A,B,C,D SI System (Hot Leg)

SI8822 A,B,C,D SI System (Cold Leg)

SR 3.5.2.8 Verify, by visual inspection, each ECCS In accordance train containment sump suction inlet is not with the restricted by debris and the suction inlet Survei 11 ance screens show no evidence of structural Frequency distress or abnormal corrosion. Contra 1 Program BYRON - UNITS 1 &2 3.5.2 - 4 Amendment 197

RWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 -------------------NOTE--------------------

Only required to be performed when ambient air temperature is< 35°F or> 100°F.

Verify RWST borated water temperature is In accordance 2 35°F and ::; 100°F. with the Surveillance Frequency Control Program SR 3.5.4.2 -------------------NOTE--------------------

Only required to be performed when ambient air temperature is< 35°F.

Verify RWST vent path temperature is In accordance 2 35°F. with the Surveillance Frequency Control Program SR 3.5.4.3 Verify RWST borated water level is 2 89%. In accordance with the Surveillance Frequency Control Program SR 3.5.4.4 Verify RWST boron concentration is In accordance 2 2300 ppm and::; 2500 ppm. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.5.4 - 2 Amendment 171

Seal Injection Flow 3.5.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.5.1 -------------------NOTE--------------------

Not required to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the Reactor Coolant System pressure stabilizes at~ 2215 psig and~ 2255 psig.

Verify manual seal injection throttle In accordance valves are adjusted to give a flow within with the the limits of Figure 3.5.5-1. Surveillance Frequency Control Pro ram BYRON - UNITS 1 &2 3.5.5 - 2 Amendment 171

Containment Air Locks 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1 -------------------NOTES-------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.

Perform required air lock leakage rate In accordance testing in accordance with the Containment with the Leakage Rate Testing Program. Containment Leakage Rate Testing Program SR 3.6.2.2 Verify only one door in the air lock can be In accordance opened at a time. with the Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.6.2 - 5 Amendment 171

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.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 E.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 3.6.3.1 Verify each 48 inch purge valve is sealed In accordance closed. with the Surveillance Frequency Control Program SR 3.6.3.2 Verify each 8 inch purge valve is closed, In accordance except when the 8 inch containment purge with the valves are open for purging or venting Surveillance under administrative controls. Frequency Control Program SR 3.6.3.3 -------------------NOTE--------------------

Valves and blind flanges in high radiation areas may be verified by use of administrative controls.

Verify each containment isolation manual In accordance valve, remote manual valve, and blind with the flange that is located outside containment Surveillance and not locked, sealed, or otherwise Frequency secured and required to be closed during Control Program accident conditions is closed, except for containment isolation valves that are open under administrative controls.

(continued)

BYRON - UNITS 1 &2 3.6.3 - 5 Amendment 171

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.4 -------------------NOTE--------------------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify each containment isolation manual Prior to valve, remote manual valve, and blind entering MODE 4 flange that is located inside containment from MODE 5 if and not locked, sealed, or otherwise not performed secured and required to be closed during within the accident conditions is closed, except for previous containment isolation valves that are open 92 days under administrative controls.

SR 3.6.3.5 Verify the isolation time of each automatic In accordance containment isolation valve is within with the limits. INSERVICE TESTING PROGRAM SR 3.6.3.6 Perform leakage rate testing for 8 inch In accordance containment purge valves with resilient with the seals. Surveillance Frequency Control Program SR 3.6.3.7 Perform leakage rate testing for 48 inch In accordance containment purge valves with resilient with the seals. Surveillance Frequency Control Program SR 3.6.3.8 Verify each automatic containment isolation In accordance valve that is not locked, sealed or with the otherwise secured in position, actuates to Surveillance the isolation position on an actual or Frequency simulated actuation signal. Control Program BYRON - UNITS 1 &2 3.6.3 - 6 Amendment 197

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be 2 -0.l psig and~ +1.0 psig.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not within limits. pressure to within limits.

B. Required Action and B.l 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 3.6.4.1 Verify containment pressure is within In accordance limits. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.6.4 - 1 Amendment 171

Containment Air Temperature 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature LCD 3.6.5 Containment average air temperature shall be~ 120°F.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average A.l Restore containment 8 hours air temperature not average air with i n 1i mit . temperature to within 1imit.

B. Required Action and B.l 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 3.6.5.1 Verify containment average air temperature In accordance is within limit. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.6.5 - 1 Amendment 171

Containment Spray and Cooling Systems 3.6.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and 0.1 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 AND not met.

0.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Two containment spray E.1 Enter LCO 3.0.3. Immediately trains inoperable.

OR Any combination of three or more trains inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 -------------------NOTE--------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each containment spray manual, power In accordance operated, and automatic valve in the flow with the path that is not locked, sealed, or Surveillance otherwise secured in position is in the Frequency correct position. Control Program SR 3.6.6.2 Operate each containment cooling train fan In accordance unit for 2 15 minutes. with the Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.6.6 - 2 Amendment 189

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.3 Verify each containment cooling train In accordance cooling water flow rate is~ 2660 gpm to with the each cooler. Surveillance Frequency Control Program SR 3.6.6.4 Verify each containment spray pump's In accordance developed head at the flow test point is with the greater than or equal to the required INSERVICE developed head. TESTING PROGRAM SR 3.6.6.5 Verify each automatic containment spray In accordance valve in the flow path that is not locked, with the sealed, or otherwise secured in position, Surveillance actuates to the correct position on an Frequency actual or simulated actuation signal. Control Program SR 3.6.6.6 Verify each containment s~ray pump starts In accordance automatically on an actua or simulated with the actuation signal. Surveillance Frequency Control Program SR 3.6.6.7 Verify each containment cooling train In accordance starts automatically on an actual or with the simulated actuation signal. Surveillance Frequency Control Program SR 3.6.6.8 Verify each spray nozzle is unobstructed. Following maintenance that could result in nozzle blockage OR Following fluid fl ow through the nozzles (continued)

BYRON - UNITS 1 &2 3.6.6 - 3 Amendment 197

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.9 Verify containment spray locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.6.6 - 4 Amendment 189

Spray Additive System 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Spray Additive System LCD 3.6.7 The Spray Additive System shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spray Additive System A.l Restore Spray 7 days inoperable. Additive System to OPERABLE status.

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 3.6.7.1 Verify each spray additive manual and In accordance automatic valve in the flow path that is with the not locked, sealed, or otherwise secured in Surveillance position is in the correct position. Frequency Control Program SR 3.6.7.2 Verify spray additive tank solution level In accordance is~ 78.6% and~ 90.3%. with the Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.6.7 - 1 Amendment 171

Spray Additive System 3.6.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.7.3 Verify spray additive tank sodium hydroxide In accordance solution concentration is~ 30% and~ 36% with the by weight. Surveillance Frequency Control Program SR 3.6. 7.4 Verify each spray additive automatic valve In accordance in the flow path that is not locked, with the sealed, or otherwise secured in position, Survei 11 ance actuates to the correct position on an Frequency actual or simulated actuation signal. Control Program SR 3.6.7.5 Verify spray additive flow rate from each In accordance solution's flow path. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.6.7 - 2 Amendment 171

MSIVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 -------------------NOTE--------------------

Only required to be performed in MODES 1 and 2.

Verify closure time of each MSIV is In accordance

~ 5 seconds. with the INSERVICE TESTING PROGRAM SR 3.7.2.2 -------------------NOTE--------------------

Only required to be performed in MODES 1 and 2.

Verify each actuator train actuates the In accordance MSIV to the isolation position on an actual with the or simulated actuation signal. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.7.2 - 3 Amendment 197

Secondary Specific Activity 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Secondary Specific Activity LCD 3.7.3 The specific activity of the secondary coolant shall be

~ 0.1 µCi/gm DOSE EQUIVALENT I-131.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not A.l Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months within limit.

AND A.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 3.7.3.1 Verify the specific activity of the In accordance secondary coolant is~ 0.1 µCi/gm DOSE with the EQUIVALENT I-131. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.7.3 - 1 Amendment 171

SG PORVs

3. 7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each SG PORV. In accordance with the Surveillance Frequency Control Program SR 3. 7.4.2 Verify one complete cycle of each SG PORV In accordance block valve. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.7.4 - 2 Amendment 171

AF System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each AF manual, power operated, and In accordance automatic valve in each water flow path, with the that is not locked, sealed, or otherwise Survei 11 ance secured in position, is in the correct Frequency position. Control Program SR 3.7.5.2 Verify day tank contains~ 420 gal of fuel In accordance oil. with the Surveillance Frequency Control Program SR 3.7.5.3 Operate the diesel driven AF pump for In accordance

~ 15 minutes. with the Surveillance Frequency Control Program SR 3.7.5.4 Verify the developed head of each AF pump In accordance at the flow test point is greater than or with the equal to the required developed head. INSERVICE TESTING PROGRAM SR 3.7.5.5 Verify each AF automatic valve that is not In accordance locked, sealed, or otherwise secured in with the position, actuates to the correct position Surveillance on an actual or simulated actuation signal. Frequency Control Program SR 3.7.5.6 Verify each AF pump starts automatically on In accordance an actual or simulated actuation signal. with the Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.7.5 - 2 Amendment 197

AF System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.7 Verify proper alignment of the required AF Prior to flow paths by verifying flow from the entering MODE 2 condensate storage tank to each steam whenever unit generator. has been in MODE 5, MODE 6, or defueled for a cumulative period of

> 30 days SR 3.7.5.8 Verify fuel oil properties are tested in In accordance accordance with, and maintained within the with the Diesel limits of, the Diesel Fuel Oil Testing Fuel Oil Program. Testing Program BYRON - UNITS 1 &2 3.7.5 - 3 Amendment 171

CST 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the CST level is 2 60%. In accordance with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.7.6 - 2 Amendment 171

CC System 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 -------------------NOTE--------------------

Isolation of CC flow to individual components does not render the CC System inoperable.

Verify each CC manual and power operated In accordance valve in the flow path servicing safety with the related equipment, that is not locked, Surveillance sealed, or otherwise secured in position, Frequency is in the correct position. Control Program SR 3.7.7.2 Verify each Essential Service Water System In accordance manual and power operated valve directly with the serving the CC heat exchangers that is not Surveillance locked, sealed, or otherwise in the correct Frequency position, is in the correct position, or Control Program can be aligned to the correct position.

SR 3.7.7.3 Verify each required CC pump starts In accordance automatically on an actual or simulated with the actuation signal. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.7.7 - 2 Amendment 171

SX System 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 -------------------NOTE--------------------

Isolation of SX flow to individual components does not render the SX System inoperable.

Verify each unit-specific SX manual, power In accordance operated, and automatic valve in the flow with the path servicing safety related equipment, Survei 11 ance that is not locked, sealed, or otherwise Frequency secured in position, is in the correct Control Program position.

SR 3.7.8.2 -------------------NOTE--------------------

Not required when opposite unit is in MODE 1, 2, 3, or 4.

Operate the opposite-unit SX pump for In accordance

~ 15 minutes. with the Surveillance Frequency Control Program SR 3.7.8.3 Cycle each opposite-unit SX crosstie valve In accordance that is not secured in the open position with the with power removed. Survei 11 ance Frequency Control Program SR 3.7.8.4 Verify each unit-specific SX automatic In accordance valve in the flow path that is not locked, with the sealed, or otherwise secured in position, Surveillance actuates to the correct position on an Frequency actual or simulated actuation signal. Control Program SR 3.7.8.5 Verify each unit-specific SX pump starts In accordance automatically on an actual or simulated with the actuation signal. Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.7.8 - 3 Amendment 171

Nonaccessible Area Exhaust Filter Plenum Ventilation System 3.7.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Operate each Nonaccessible Area Exhaust In accordance Filter Plenum Ventilation System train for with the

~ 15 minutes. Surveillance Frequency Control Program SR 3.7.12.2 Perform required Nonaccessible Area Exhaust In accordance Filter Plenum Ventilation System filter with the VFTP testing in accordance with the Ventilation Filter Testing Program (VFTP).

SR 3.7.12.3 Verify each Nonaccessible Area Exhaust In accordance Filter Plenum Ventilation System train with the actuates on a manual, an actual, or a Surveillance simulated actuation signal. Frequency Control Program SR 3. 7.12.4 Verify two Nonaccessible Area Exhaust In accordance Filter Plenum Ventilation System trains can with the maintain a pressure~ -0.25 inches water Surveillance gauge relative to atmospheric pressure Frequency during the emergency mode of operation at a Control Program flow rate of~ 68,200 cfm per train.

BYRON - UNITS 1 &2 3. 7.12 - 2 Amendment 171

FHB Ventilation System 3.7.13 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two FHB Ventilation C.l Suspend movement of Immediately System trains RECENTLY IRRADIATED inoperable. FUEL assemblies in the fuel handling building.

AND C.2 --------NOTE---------

Only required with equipment hatch not intact.

Suspend movement of Immediately RECENTLY IRRADIATED FUEL assemblies in the containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each FHB Ventilation System train In accordance for~ 15 minutes. with the Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.7.13 - 3 Amendment 171

FHB Ventilation System 3.7.13 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.13.2 Perform required FHB Ventilation System In accordance filter testing in accordance with the with the VFTP Ventilation Filter Testing Program (VFTP).

SR 3.7.13.3 -------------------NOTE--------------------

Only required during movement of RECENTLY IRRADIATED FUEL assemblies with the equipment hatch not intact.

Verify one FHB Ventilation System train can In accordance maintain a pressures -0.25 inches water with the gauge relative to atmospheric pressure Surveillance during the emergency mode of operation. Frequency Control Program SR 3.7.13.4 Verify each FHB Ventilation System train In accordance actuates on an actual or simulated with the actuation signal. Surveillance Frequency Control Program SR 3.7.13.5 -------------------NOTE--------------------

Only required during movement of RECENTLY IRRADIATED FUEL assemblies in the fuel handling building with the equipment hatch intact.

Verify one FHB Ventilation System train can In accordance maintain a pressures -0.25 inches water with the gauge relative to atmospheric pressure Surveillance during the emergency mode of operation at a Frequency flow rates 23,100 cfm. Control Program BYRON - UNITS 1 &2 3.7.13 - 4 Amendment 171

Spent Fuel Pool Water Level 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool Water Level LCD 3.7.14 The spent fuel pool water level shall be~ 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel pool.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool water A.l Suspend movement of Immediately level not within irradiated fuel limit. assemblies in the spent fuel pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the spent fuel pool water level is In accordance

~ 23 ft above the top of the irradiated with the fuel assemblies seated in the storage Surveillance racks. Frequency Control Program BYRON - UNITS 1 &2 3.7.14 - 1 Amendment 171

Spent Fuel Pool Boron Concentration 3.7.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the spent fuel pool boron In accordance concentration is within limit. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.7.15-2 Amendment 171

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.12 Verify on an actual or simulated Engineered In accordance Safety Feature (ESF) actuation signal each with the DG auto-starts from standby condition and: Surveillance Frequency

a. Ins 10 seconds achieves voltage Control Program 2 3950 V and frequency 2 58.8 Hz;

b. Achieves steady state voltage 2 3950 V ands 4580 V and frequency 2 58.8 Hz ands 61.2 Hz; and

c. Operates for 2 5 minutes.

SR 3.8.1.13 Verify each DG's automatic trips are In accordance bypassed on actual or simulated loss of with the voltage signal on the emergency bus Surveillance concurrent with an actual or simulated ESF Frequency actuation signal except: Control Program

a. Engine overspeed; and

b. Generator differential current.

SR 3.8.1.14 -------------------NOTE--------------------

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

Verify each DG operates for 2 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: In accordance with the

a. For 2 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 2 5775 kW and Surveillance s 6050 kW; and Frequency Control Program

b. For the remaining hours of the test loaded 2 4950 kW ands 5500 kW.

(continued)

BYRON - UNITS 1 &2 3.8.1 - 9 Amendment 171

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.15 -------------------NOTES-------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 2 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 2 4950 kW and~ 5500 kW or until operating temperature has stabilized.

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

Verify each DG starts and achieves: In accordance with the

a. In~ 10 seconds, voltage 2 3950 V Survei 11 ance and frequency 2 58.8 Hz; and Frequency Control Program

b. Steady state voltage 2 3950 V and

~ 4580 V, and frequency 2 58.8 Hz and~ 61.2 Hz.

SR 3.8.1.16 -------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify each DG: In accordance with the

a. Synchronizes with offsite power source Surveillance while loaded with emergency loads upon Frequency a simulated restoration of offsite Control Program power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

(continued)

BYRON - UNITS 1 &2 3.8.1-10 Amendment 171

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.17 -------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify, with a DG operating in test mode In accordance and connected to its bus, an actual or with the simulated ESF actuation signal overrides Survei 11 ance the test mode by: Frequency Control Program

a. Returning DG to ready-to-load operation; and

b. Automatically energizing the emergency load from offsite power.

SR 3.8.1.18 -------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify interval between each sequenced load In accordance block is within+/- 10% of design interval with the for each safeguards and shutdown sequence Surveillance timer. Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.8.1 - 11 Amendment 171

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.19 -------------------NOTE--------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify on an actual or simulated loss of In accordance offsite power signal in conjunction with an with the actual or simulated ESF actuation signal: Surveillance Frequency

a. De-energization of ESF buses; Control Program

b. Load shedding from ESF buses; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads ins 10 seconds,

2. energizes auto-connected emergency loads through the safeguards sequence timers,

3. achieves steady state voltage 2 3950 V ands 4580 V,

4. achieves steady state frequency 2 58.8 Hz ands 61.2 Hz, and

5. supplies permanently connected and auto-connected emergency loads for 2 5 minutes.

SR 3.8.1.20 Verify when started simultaneously from In accordance standby condition, each DG achieves: with the Surveillance

a. Ins 10 seconds, voltage 2 3950 V Frequency and frequency 2 58.8 Hz; and Control Program

b. Steady state voltage 2 3950 V and s 4580 V, and frequency 2 58.8 Hz and s 61.2 Hz.

BYRON - UNITS 1 &2 3.8.1 - 12 Amendment 171

Diesel Fuel Oil 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and 0.1 Declare associated DG Inmediately associated Completion inoperable.

Time of Conditions A, B, or C not met.

One or more DGs with diesel fuel oil not within limits for reasons other than Condition A, B, or C.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each DG fuel oil storage tank(s) In accordance contains~ 44,000 gal of fuel. with the Surveillance Frequency Control Program SR 3.8.3.2 Verify fuel oil properties of new and In accordance stored fuel oil are tested in accordance with the Diesel with, and maintained within the limits of, Fuel Oil the Diesel Fuel Oil Testing Program. Testing Program SR 3.8.3.3 Check for and remove accumulated water from In accordance each fuel oil storage tank. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.8.3 - 2 Amendment 171

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater In accordance than or equal to the minimum established with the fl oat voltage. Survei 11 ance Frequency Control Program SR 3.8.4.2 Verify each battery charger supplies a load In accordance equal to the manufacturer's rating at with the greater than or equal to the minimum Surveillance established float voltage for~ 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Frequency Control Program Verify each battery charger can recharge the battery to the fully charged state within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while supplying the largest coincident demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

SR 3.8.4.3 -------------------NOTES-------------------

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of the service test in SR 3.8.4.3.

2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify battery capacity is adequate to In accordance supply, and maintain OPER.A.BLE status, the with the required emergency loads for the design Surveillance duty cycle when subjected to a battery Frequency service test. Control Program BYRON - UNITS 1 &2 3.8.4 - 3 Amendment 171

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Declare associated Immediately associated Completion battery inoperable.

Time of Condition A, B, C, D, or E not met.

One battery with one or more cells with float voltage< 2.07 V and float current

> 3 amps.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 ----------------NOTE----------------------

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is In accordance

~ 3 amps. with the Surveillance Frequency Control Program SR 3.8.6.2 Verify each battery pilot cell float In accordance voltage is~ 2.07 V. with the Surveillance Frequency Control Program SR 3.8.6.3 Verify each battery cell electrolyte level In accordance is greater than or equal to minimum with the established design limits. Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.8.6 - 3 Amendment 171

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.4 Verify each battery pilot cell electrolyte In accordance temperature is greater than or equal to with the minimum established design limits. Surveillance Frequency Control Program SR 3.8.6.5 Verify each battery cell float voltage is In accordance

~ 2.07 V. with the Surveillance Frequency Control Program SR 3.8.6.6 ------------------NOTE---------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify battery capacity is~ 80% of the In accordance manufacturer's rating when subjected to a with the performance discharge test or a modified Surveillance performance discharge test. Frequency Control Program 12 months when battery shows degradation or has reached 85%

of the expected life with capacity< 100%

of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity~ 100%

of manufacturer's rating BYRON - UNITS 1 &2 3.8.6 - 4 Amendment 171

Inverters-Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage and breaker In accordance alignment to AC instrument buses. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.8.7 - 2 Amendment 171

Inverters-Shutdown 3.8.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Suspend CORE Irrrnediately ALTERATI ONS.

AND A.2.2 Suspend movement of Irrrnediately irradiated fue 1 assemblies.

AND A.2.3 Initiate action to Irrrnediately suspend operations involving positive reactivity additions.

AND A.2.4 Initiate action to Irrrnediately restore required inverters to OPERABLE status.

AND A.2.5 Declare affected Low Irrrnediately Temperature Overpressure Protection feature(s) inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage and breaker In accordance alignment to required AC instrument buses. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.8.8 - 2 Amendment 171

Distribution Systems-Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two electrical power E.1 Enter LCO 3.0.3. Immediately 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 In accordance voltage to AC, DC, and AC instrument bus with the electrical power distribution subsystems. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.8.9 - 3 Amendment 171

Distribution Systems-Shutdown 3.8.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and In accordance voltage to required AC, DC, and AC with the instrument bus electrical power Surveillance distribution subsystems. Frequency Control Program BYRON - UNITS 1 &2 3.8.10 - 4 Amendment 171

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the limit specified in the COLR.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration A.l Suspend CORE Immediately not within limit. ALTERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

AND A.3 Initiate action to Immediately restore boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the In accordance limit specified in the COLR. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.9.1 - 1 Amendment 171

Unborated Water Source Isolation Valves 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify each valve that isolates unborated In accordance water sources is secured in the closed with the position. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.9.2 - 2 Amendment 171

Nuclear Instrumentation 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Nuclear Instrumentation LCD 3.9.3 Two source range neutron flux monitors shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required source A.l Suspend CORE Immediately range neutron flux ALTERATI ONS.

monitor inoperable.

AND A.2 Suspend positive Immediately reactivity additions.

B. Two required source B.l Initiate action to Immediately range neutron flux restore one source monitors inoperable. range neutron flux monitor to OPERABLE status.

AND B.2 Perform SR 3.9.1.1. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months BYRON - UNITS 1 &2 3.9.3 - 1 Amendment 109

Nuclear Instrumentation 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.9.3.2 -------------------NOTE--------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. In accordance with the Survei 11 ance Frequency Control Program BYRON - UNITS 1 &2 3.9.3 - 2 Amendment 171

RHR and Coolant Circulation-High Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Close a11 containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation and In accordance circulating reactor coolant at a flow rate with the of 2 1000 gpm. Surveillance Frequency Control Program SR 3.9.5.2 Verify required RHR loop locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.9.5 - 2 Amendment 189

RHR and Coolant Circulation-Low Water Level 3.9.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR loop in B.l Suspend operations Imnediately operation. involving a reduction in reactor coolant boron concentration.

AND B.2 Initiate action to Imnediately restore one RHR loop to operation.

AND B.3 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and In accordance circulating reactor coolant at a flow rate with the of 2 1000 gpm. Surveillance Frequency Control Program SR 3.9.6.2 Verify correct breaker alignment and In accordance indicated power available to the required with the RHR pump that is not in operation. Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.9.6 - 2 Amendment 189

RHR and Coolant Circulation-Low Water Level 3.9.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.9.6.3 Verify RHR loop locations susceptible to In accordance gas accumulation are sufficiently filled with the with water. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.9.6 - 3 Amendment 189

Refueling Cavity Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Refueling Cavity Water Level LCO 3.9.7 Refueling cavity water level shall be maintained 2 23 ft above the top of reactor vessel flange.

APPLICABILITY: During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water A.l Suspend movement of Immediately level not within irradiated fuel 1imit. assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify refueling cavity water level is In accordance 2 23 ft above the top of reactor vessel with the flange. Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.9.7 - 1 Amendment 171

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 DELETED BYRON - UNITS 1 &2 5.5 - 6 Amendment 197

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the Steam Generator Program shall include the following:

a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes. Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met.

b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE.

1. Structural integrity performance criterion: All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down), all anticipated transients included in the design specification, and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.

BYRON - UNITS 1 &2 5.5 - 7 Amendment 179

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued)

2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG.

Leakage is not to exceed a total of 1 gpm for all SGs.

3. The operational LEAKAGE performance criteria is specified in LCO 3.4.13, "RCS Operational LEAKAGE."

c. Provisions for SG tube plugging criteria. Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal wall thickness shall be plugged. The following alternate tube plugging criteria shall be applied as an alternative to the 40% depth based criteria:

For Unit 2, tubes with service-induced flaws located greater than 14.01 inches below the top of the tubesheet do not require plugging. Tubes with service-induced flaws located in the portion of the tube from the top of the tubesheet to 14.01 inches below the top of the tubesheet shall be plugged upon detection.

BYRON - UNITS 1 &2 5.5 - 8 Amendment 179

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued)

d. Provisions for SG tube inspections. Periodic SG tube inspections shall be performed. The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy the applicable tube plugging criteria. For Unit 2, portions of the tube below 14.01 inches from the top of the tubesheet are excluded from this requirement.

The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.1, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection. A degradation assessment shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.

1. Inspect 100% of the tubes in each SG during the first refueling outage following SG installation.

2. For Unit 1, after the first refueling outage following SG installation, inspect each SG at least every 72 effective full power months or at least every third refueling outage (whichever results in more frequent inspections). In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection period as defined in a, b, c, and ct below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated.

The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be inspected in the inspection period after the determination that a new form of degradation could BYRON - UNITS 1 &2 5.5 - 9 Amendment 179

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator CSG) Program (continued) potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage.

a) After the first refueling outage following SG installation, inspect 100% of the tubes during the next 144 effective full power months. This constitutes the first inspection period; b) During the next 120 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period; c) During the next 96 effective full power months, inspect 100% of the tubes. This constitutes the third inspection period; and d) During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the fourth and subsequent inspection periods.

3. For Unit 2, after the first refueling outage following SG installation, inspect each SG at least every 48 effective full power months or at least every other refueling outage (whichever results in more frequent inspections). In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection period as defined in a, b, and c below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated.

The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be BYRON - UNITS 1 &2 5.5 - 10 Amendment 179

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued) inspected in the inspection period after the determination that a new form of degradation could potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage.

a) After the first refueling outage following SG installation, inspect 100% of the tubes during the next 120 effective full power months. This constitutes the first inspection period; b) During the next 96 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period; and c) During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the third and subsequent inspection periods.

4. For Unit 1, if crack indications are found in any SG tube, then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections). For Unit 2, if crack indications are found in any SG tube from 14.01 inches below the top of the tubesheet on the hot leg side to 14.01 inches below the top of the tubesheet on the cold leg side, then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections).

If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.

e. Provisions for monitoring operational primary to secondary LEAKAGE.

BYRON - UNITS 1 &2 5.5 - 11 Amendment 179

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.19 Surveillance Freguency 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 BYRON - UNITS 1 &2 5.5 - 24 Amendment 171

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.8 Tendon Surveillance Report Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Sunmary Report in accordance with 10 CFR 50.55a and ASME Section XI.

5.6.9 Steam Generator (SG) Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Specification 5.5.9, Steam Generator (SG) Program.

The report shall include:

a. The scope of inspections performed on each SG,

b. Degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged during the inspection outage for each degradation mechanism, I

f. The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing, BYRON - UNITS 1 &2 5.6 - 6 Amendment 179

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.9 Steam Generator (SG) Tube Inspection Report (continued)

h. For Unit 2, the operational primary to secondary leakage rate observed (greater than three gallons per day) in each steam generator (if it is not practical to assign the leakage to an individual steam generator, the entire primary to secondary leakage should be conservatively assumed to be from one steam generator) during the cycle preceding the inspection which is the subject of the report,

i. For Unit 2, the calculated accident induced leakage rate from the portion of the tubes below 14.01 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. In addition, if the calculated accident induced leakage rate from the most limiting accident is less than 3.11 times the maximum operational primary to secondary leakage rate, the report should describe how it was determined, and

j. For Unit 2, the results of monitoring for tube axial displacement (slippage). If slippage is discovered, the implications of the discovery and corrective action shall be provided.

BYRON - UNITS 1 &2 5.6 - 7 Amendment 179

ML18067A181 OFFICE LPL3/PM LPL3/LA LPL3/BC LPL3/PM NAME JWiebe SRohrer DWrona JWiebe DATE 5/24/18 3/8/18 5/25/18 6/4/18

ML18067A181

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ML18067A181

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Dear Mr. Hanson:

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