Text

Resubmittal of Clean-Typed Pages for Multiple Technical Specifications Task Force Traveler Adoption
	ML16123A134
Person / Time
Site:	Vogtle
Issue date:	05/02/2016
From:	Pierce C; Southern Co, Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-16-0630
	Download: ML16123A134 (51)
	v • d • e

Charles R. Pierce Regulatory Affairs Director MAY 0 2 2016 Docket Nos.: 50-424 50-425 Southern Nuclear Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Te 205.992.7872 Fax 205.992.7601 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 SOUTHERN*\\

NUCLEAR A SOUtHERN COMPANY NL-16-0630 Vogtle Electric Generating Plant - Units 1 and 2 Resubmittal of Clean-Typed Pages for Multiple Technical Specifications Task Force Traveler Adoption Ladies and Gentlemen:

By letter dated July 18, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14203A124) and supplemented by letter dated February 27,2015 (ADAMS Accession No. ML15058A891), Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) to adopt various previously approved Technical Specifications Task Force (TSTF) Travelers.

Several administrative issues in the originally submitted clean-typed Technical Specifications (TS) pages were subsequently discovered. In addition, an error was identified on TS page 1.4-8, which had a surveillance note that stated "Not required to be met in MODE 1." This note should say "Not required to be met in MODE3."

Please note that SA 3.9.6.2 was added to these clean-typed pages to reflect the recent issuance of TS Amendment Nos. 178/159.

The enclosure to this letter contains new clean-typed pages and supersedes those originally submitted on July 18, 2014 and February 27, 2015.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369

U.S. Nuclear Regulatory Commission NL-16-0630 Page2 Mr. C. A. Pierce states he is Regulatory Affairs Director of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.

Respectfully ~itted,

c. f(_ ~

C. A. Pierce Regulatory Affairs Director CRP/JMC/Iac

? ~J

.411 z:::::rt(J;';; this~~

dayof_I_VIIt--~..V ____, 2016.

Notary Public My commission expires: /0 - 1 ~ J. o I '1

Enclosure:

Clean-Typed Pages for Multiple Technical Specifications Task Force Traveler Adoption cc:

Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Best, Executive Vice President & Chief Nuclear Officer Mr. D. A. Madison, Vice President-Fleet Operations Mr. M. D. Meier, Vice President-Regulatory Affairs Mr. B. K. Taber, Vice President-Vogtle 1 & 2 Mr. B. J. Adams, Vice President - Engineering Mr. G. W. Gunn, Regulatory Affairs Manager-Vogtle 1 & 2 RType: CVC7000 U. S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. A. E. Martin, NRR Senior Project Manager-Vogtle 1 & 2 Mr. W. D. Deschaine, Senior Resident Inspector-Vogtle 1 & 2 State of Georgia Mr. J. H. Turner, Director-Environmental Protection Division

Vogtle Electric Generating Plant-Units 1 and 2 Resubmittal of Clean-Typed Pages for Multiple Technical Specifications Task Force Traveler Adoption Enclosure Clean-Typed Pages for Multiple Technical Specifications Task Force Traveler Adoption

1.1 Definitions (continued)

Definitions 1.1 SHUTDOWN MARGIN (SDM)

SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

SLAVE RELAY TEST STAGGERED TEST BASIS THERMAL POWER TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT)

Vogtle Units 1 and 2

a.

All rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn.

However, with all RCCAs verified fully inserted by two independent means, it is not necessary to account for a stuck rod in the SDM calculation. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM; and

b.

In MODES 1 and 2, the fuel and moderator temperatures are changed to the hot zero power temperatures.

A SLAVE RELAY TEST shall consist of energizing each slave relay and verifying the OPERABILITY of each slave relay.

The SLAVE RELAY TEST shall include, as a minimum, a continuity check of associated testable actuation devices.

A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

A T ADOT shall consist of operating the trip actuating device and verifying the OPERABILITY of required alarm, interlock, and trip functions. The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the required accuracy.

1.1-6 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE DESCRIPTION Vogtle Units 1 and 2 The purpose of this section is to define the proper use and application of Frequency requirements.

Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR)

Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by SR 3.0.1. They may be stated as clarifying Notes In the Surveillance, as part of the Surveillance, or both.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria.

1.4-1 (continued)

Amendment No.

(Unit 1)

(Unit 2)

1.4 Frequency DESCRIPTION (continued)

EXAMPLES Vogtle Units 1 and 2 Frequency 1.4 Some Surveillances contain notes that modify the Frequency of performance or the conditions during which the acceptance criteria must be satisfied. For these Surveillances, the MODE-entry restrictions of SR 3.0.4 may not apply. Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied:

a.

The Surveillance is not required to be met in the MODE or other specified condition to be entered; or

b.

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

c.

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

Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 discuss these special situations.

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

1.. 4-2 (continued}

Amendment No.

(Unit 1)

(Unit 2)

1.4 Frequency EXAMPLES (continued)

Vogtle Units 1 and 2 EXAMPLE 1.4-1 SINGLE FREQUENCY SURVEILLANCE REQUIREMENTS SURVEILLANCE Perform CHANNEL CHECK.

Frequency 1.4 FREQUENCY 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO}. If the other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not other wise modified (refer to Example 1.4-3), then SR 3.0.3 becomes applicable.

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable, The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.

(continued) 1.4-3 Amendment No.

(Unit 1}

Amendment No.

(Unit 2)

1.4 Frequency EXAMPLES (continued)

Vogtle Units 1 and 2 Frequency 1.4 EXAMPLE 1.4-2 MULTIPLE FREQUENCIES SURVEILLANCE REQUIREMENTS SURVEILLANCE Verify flow is within limits.

FREQUENCY Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

<::.25% RTP 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

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

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

This type of Frequency does not qualify for the extension allowed by SR 3.0.2. Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to

< 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

(continued) 1.4-4 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

1.4 Frequency EXAMPLES (continued)

Vogtle Units 1 and 2 Frequency 1.4 EXAMPLE 1.4-3 FREQUENCY BASED ON A SPECIFIED CONDITION SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

~ 25% RTP.

Perform channel adjustment.

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

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is< 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches~ 25% RTP to perform the Surveillance.

The Surveillance is still considered to be performed within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was

< 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power ~ 25% RTP.

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Surveillance within the specified Frequency and the provisions of SR 3.0.3 would apply.

(continued) 1.4-5 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

1.4 Frequency EXAMPLES (continued)

Vogtle Units 1 and 2 EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE

NOTE Only required to be met in MODE 1.

Verify leakage rates are within limits.

Frequency 1.4 FREQUENCY 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satisfying the SR.

(continued) 1.4-6 Amendment No.

(Unit 1)

Amendment No.

(Unit 2}

1.4 Frequency EXAMPLES (continued)

Vogtle Units 1 and 2 EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE

-NOTE Only required to be performed in MODE 1.

Frequency 1.4 FREQUENCY Perform complete cycle of the valve.

?days The interval continues, whether or not the unit operation is in MODE 1,2, or 3 (the assigned Applicability of the associated LCO) between performances.

As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance. The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to entering MODE 1.

Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not result in entry into MODE 1.

Once the unit reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed. If the Surveillance were not performed prior to entering MODE 1, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

(continued) 1.4-7 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

1.4 Freguency EXAMPLES (continued)

Vogtle Units 1 and 2 EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE NOTE-Not required to be met in MODE 3.

Verify parameter is within limits.

Frequency 1.4 FREQUENCY 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-6 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 3 (the assumed Applicability of the associated LCO is MODES 1, 2, and 3). The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 3, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES to enter MODE 3, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change does not result in entry into MODE 2. Prior to entering MODE 2 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satisfying the SR.

1.4-8 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Core Reactivity Core Reactivity 3.1.2 LCO 3.1.2 The measured core reactivity shall be within +/- 1% L\\klk of predicted values.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Measured core reactivity A.1 Reevaluate core design 7days I

not within limit.

and safety analysis, and determine that the reactor core is acceptable for continued operation.

AND A.2 Establish appropriate 7 days I

operating restrictions and SRs.

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.

Vogtle Units 1 and 2 3.1.2-1 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

ACTIONS CONDITION B. (continued) 8.1.2 AND 8.2 AND 8.3 AND 8.4 AND 8.5 AND 8.6 Vogtle Units 1 and 2 REQUIRED ACTION Rod Group Alignment Limits 3.1.4 COMPLETION TIME Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER tos75% RTP.

Verify SDM is ~ the limit Once per specified in the COLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Perform SR 3.2.1.1 and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months SR 3.2.1.2.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Perform SR 3.2.2.1.

5days Reevaluate safety analyses and confirm results remain valid for duration of operation under these conditions.

(continued) 3.1.4-2 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

ACTIONS (continued)

CONDITION

c. Required Action and associated Completion Time of Condition 8 not met.

D.

More than one rod not within alignment limit.

REQUIRED ACTION

c. 1 Be in MODE 3 D.1.1 Verify SDM is ~ the limit specified in the COLR.

OR Rod Group Alignment Limits 3.1.4 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 1 hour D.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required SDM to within limit.

AND D.2 Be in MODE 3.

SURVEILLANCE REQUIREMENTS SR 3.1.4.1 SURVEILLANCE Verify individual rod positions within alignment limit.

Vogtle Units 1 and 2 3.1.4-3 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months FREQUENCY In accordance with the Surveillance Frequency Control Program (continued)

Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

Control Bank Insertion Limits 3.1.6 SURVEILLANCE REQUIREMENTS (continued)

SR 3.1.6.2 SR 3.1.6.3 SURVEILLANCE Verify each control bank insertion is within the limits specified in the COLR.

Verify sequence and overlap limits specified in the COLR are met for control banks not fully withdrawn from the core.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Vogtle Units 1 and 2 3.1.6-3 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication Rod Position Indication 3.1.7 LCO 3.1.7 The Digital Rod Position Indication (DRPI) System and the Demand Position Indication System shall be OPERABLE.

APPLICABILITY:

MODES 1 and 2.

ACTIONS NOTE Separate Condition entry is allowed for each inoperable rod position indicator and each inoperable demand position indicator.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One DRPI per group A.1 Verify the position of the Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable for one or rods with inoperable more groups.

position indicators indirectly by using movable incore detectors.

OR A.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to ~ 50% RTP.

(continued)

Vogtle Units 1 and 2 3.1.7-1 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

ACTIONS (continued)

CONDITION B.

More than one DRPI 8.1 group inoperable.

AND 8.2 AND 8.3 AND 8.4 C.

One or more rods with C.1 inoperable DRPis have been moved in excess of 24 steps in one direction since the last determination of the OR rod's position.

C.2 Vogtle Units 1 and 2 REQUIRED ACTION Place the control rods under manual control.

Monitor and Record RCS Tavg Verify the position of the rods with inoperable position indicators indirectly by using the Rod Position Indication 3.1.7 COMPLETION TIME Immediately Once per 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months movable incore detectors.

Restore inoperable 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months position indicators to OPERABLE status such that a maximum of one DRPI per group is inoperable.

Verify the position of the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months rods with inoperable DRPis indirectly by using movable incore detectors.

Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to ~50% RTP.

( cont1nued) 3.1.7-2 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

ACTIONS _(continued)

CONDITION REQUIRED ACTION D.

One demand position D.1.1 Verify by administrative indicator per bank means all DRPis for the inoperable for one or affected banks are more banks.

OPERABLE.

AND D.1.2 Verify the most withdrawn rod and the least withdrawn rod of the affected banks are s 12 steps apart.

OR D.2 Reduce THERMAL POWER to s 50% RTP.

E.

Required Action and E.1 Be in MODE 3.

associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SR 3.1.7.1 SURVEILLANCE Verify each DR PI agrees within 12 steps of the group demand position for the full indicated range of rod travel.

Rod Position Indication 3.1.7 COMPLETION TIME Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 hours 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months FREQUENCY In accordance with the Surveillance Frequency Control Program Vogtle Units 1 and 2 3.1.7-3 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (Fa(Z)) (Fa Methodology)

Fa(Z) 3.2.1 LCO 3.2.1 Fa(Z) shall be within the steady state and transient limits specified in the COLR.

APPLICABILITY:

MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Fa(Z) not within steady A.1 Reduce THERMAL 15 minutes state limit.

POWER ~ 1% RTP for each 1% Fa(Z) exceeds steady state limit.

AND A.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Neutron Flux -

High trip setpoints ~ 1% for each 1 % F a(Z) exceeds steady state limit.

AND A.3 Reduce Overpower !:l T 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip setpoints ~ 1% for each 1% Fa(Z) exceeds steady state limit.

AND A.4 Perform SR 3.2.1.1.

Prior to increasing THERMAL POWER above the limit of Required Action A.1 (continued)

Vogtle Units 1 and 2 3.2.1-1 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F:H)

LCO 3.2.2 F:H shall be within the limits specified in the COLR.

APPLICABILITY:

MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---NOTE--

A.1.1 Restore F~H to within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Actions A.2 limits.

and A.3 must be completed whenever OR Condition A is entered.

A.1.2.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months F~H not within limits.

POWER to < 50% RTP.

AND A.1.2.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Neutron Flux-High trip setpoints to ~ 55% RTP.

AND A.2 Perform SR 3.2.2.1.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND (continued)

Vogtle Units 1 and 2 3.2.2-1 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

3.2 POWER DISTRIBUTION LIMITS AFD (RAOC Methodology) 3.2.3 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology)

LCO 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.

ACTIONS CONDITION A.

AFD not within limits.

A.1 SURVEILLANCE REQUIREMENTS REQUIRED ACTION Reduce THERMAL POWER to< 50% RTP.

SURVEILLANCE SR 3.2.3.1 Verify AFD within limits for each OPERABLE excore channel.

Vogtle Units 1 and 2 3.2.3-1 COMPLETION TIME 30 minutes FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)

LCO 3.2.4 The QPTR shall be s 1.02.

APPLICABILITY:

MODE 1 with THERMAL POWER > 50% RTP.

ACTIONS CONDITION A.

NOTE-*--

Required Action A.6 must be completed whenever Required Action A.5 is implemented.

QPTR not within limit.

Vogtle Units 1 and 2 A.1 AND A.2.1 AND A.2.2 AND A.3 REQUIRED ACTION limit THERMAL POWER to 2: 3% below RTP for each 1% of QPTR > 1.00.

Perform SR 3.2.4.1.

limit THERMAL POWER to 2: 3% below RTP for each 1% QPTR > 1.00.

Perform SR 3.2.1.1, SR 3.2.1.2, and SR 3.2.2.1.

3.2.4-1 QPTR 3.2.4 COMPLETION TIME 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

NOTE----

For performances of Required Action A.2.2 the Completion Time is measured from the completion of SR 3.2.4.1.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions with THERMAL POWER limited by Required Actions A.1 and A.2.2 (continued)

Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

ACTIONS CONDITION REQUIRED ACTION A.

(continued)

A.6 NOTE----

Perform Required Action A.6 only after Required Action A.5 is completed.

Perform SR 3.2.1.1, SR 3.2.1.2, and SR 3.2.2.1.

B.

Required Action and 8.1 Reduce THERMAL associated Completion POWER to $: 50% RTP.

Time not met.

Vogtle Units 1 and 2 3.2.4-3 QPTR 3.2.4 COMPLETION TIME NOTE---

Only one of the following Completion Times, whichever becomes applicable first, must be met.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching RTP OR Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL POWER above the limit of Required Action A.1 and A.2.2 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

SURVEILLANCE REQUIREMENTS SR 3.2.4.1 SR 3.2.4.2 SURVEILLANCE

NOTE-------

With one power range channel inoperable, the remaining three power range channels can be used for calculating QPTR.

Verify QPTR is within limit by calculation.

-NOTE Only required to be performed if input to QPTR from one or more Power Range Neutron Flux channels is inoperable with THERMAL POWER

~75% RTP.

Confirm that the normalized symmetric power distribution is consistent with QPTR.

QPTR 3.2.4 FREQUENCY In accordance with the Surveillance Frequency Control Program Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months In accordance with the Surveillance Frequency Control Program Vogtle Units 1 and 2 3.2.4-4 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

3.3 INSTRUMENTATION 3.3.4 Remote Shutdown System Remote Shutdown System 3.3.4 LCO 3.3.4 The Remote Shutdown System Functions shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS

NOTE Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Restore required Function 30 days Functions inoperable.

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 MODE4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Vogtle Units 1 and 2 3.3.4-1 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 Each RCS loop average temperature (Tavg) shall be ~ 551°F.

APPLICABILITY:

MODE 1, MODE 2 with kett 2: 1.0.

ACTIONS CONDITION REQUIRED ACTION A

T avg in one or more RCS A. 1 Be in MODE 3.

loops not within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.2.1 Verify RCS Tavg in each loop 2: 551°F.

Vogtle Units 1 and 2 3.4.2-1 COMPLETION TIME 30 minutes FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

ACTIONS (continued)

CONDITION C.

One required RCS loop C.1 not in operation with Rod Control System capable of rod OR withdrawal.

C.2 D.

Two required RCS loops 0.1 inoperable.

OR No RCS loop in AND operation.

0.2 REQUIRED ACTION Restore required RCS loop to operation.

Place the Rod Control System in a condition incapable of rod withdrawal.

Suspend all operations involving a reduction of RCS loops-MODE 3 3.4.5 COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour Immediately Immediately RCS boron concentration.

AND 0.3 Initiate action to restore one RCS loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.5.1 Verify required RCS loops are in operation.

Vogtle Units 1 and 2 3.4.5-2 Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program (continued)

Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with:

a.

Pressurizer water level :S: 92%; and Pressurizer 3.4.9

b.

Two groups of pressurizer heaters OPERABLE with the capacity of each group ~ 150 kW and capable of being powered from an emergency power supply.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Pressurizer water level A.1 Be in MODE 3 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months not within limit.

AND A.2 Fully insert all rods.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND A.3 Place Rod Control 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months System in a condition incapable of rod withdrawal.

AND A.4 Be in MODE4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B.

One required group of 8.1 Restore required group of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pressurizer heaters pressurizer heaters to inoperable.

OPERABLE status.

(contmued)

Vogtle Units 1 and 2 3.4.9-1 Amendment No.

{Unit 1)

Amendment No.

{Unit 2)

ACTIONS (continued)

CONDITION REQUIRED ACTION

c.

Required Action and C.1 Be in MODE 3.

associated Completion Time of Condition B not AND met.

C.2 Be in MODE4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.9.1 SR 3.4.9.2 Verify pressurizer water level is ~ 92%.

Verify capacity of each required group of pressurizer heaters is ;::: 150 kW.

Vogtle Units 1 and 2 3.4.9-2 Pressurizer 3.4.9 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

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

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

APPLICABILITY:

MODES 1, 2, and 3.

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

CONDITION A.

One or more PORVs A.1 inoperable and capable of being manually cycled.

B.

One PORV inoperable 8.1 and not capable of being manually cycled.

AND 8.2 AND 8.3 Voglle Units 1 and 2 REQUIRED ACTION COMPLETION TIME Close and maintain power 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to associated block valve.

Close associated block valve.

Remove power from associated block valve.

Restore PORV to OPERABLE status.

3.4.11-1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (contmued)

Amendment No.

(Unit 1)

(Unit 2)

ACTIONS (continued)

CONDITION

c. One block valve C.1 inoperable.

AND C.2 D.

Required Action and D.1 associated Completion Time of Condition A, B, AND or C not met.

D.2 E.

Two PORVs inoperable E.1 and not capable of being manually cycled.

AND E.2 AND E.3 AND E.4 F.

Two block valves F.1 inoperable.

Vogtle Units 1 and 2 REQUIRED ACTION Place associated PORV in manual control.

Restore block valve to OPERABLE status.

Be in MODE 3.

Be in MODE4.

Close associated block valves.

Remove power from associated block valves.

Be in MODE 3.

Be in MODE4.

Restore one block valve to OPERABLE status.

3.4.11-2 Pressurizer PORVs 3.4.11 COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 72 hours 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (contmued)

Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

ACTIONS (continued)

CONDITION REQUIRED ACTION G.

Required Action and G.1 Be in MODE 3.

associated Completion Time of Condition F not AND met.

G.2 Be in MODE4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE Pressurizer PORVs 3.4.11 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours FREQUENCY SR 3.4.11.1

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

SR 3.4.11.2

1. Not required to be performed with block valve closed in accordance with the Required Actions of this LCO.

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

Perform a complete cycle of each black valve.

-NOTE-*--*---

Only required to be performed in MODES 1 and 2.

Perform a complete cycle of each PORV.

Vogtle Units 1 and 2 3.4.11-3 In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

SURVEILLANCE REQUIREMENTS SR 3.4.12.1 SR 3.4.12.2 SR 3.4.12.3 SR 3.4.12.4 SURVEILLANCE Verify both safety injection pumps are incapable of injecting into the RCS.

Verify each accumulator is isolated.

Verify RHR suction valves are open for each required RHR suction relief valve.

NOTE Only required to be met when complying with LCO 3.4.12.b.

Verify RCS vent size within specified limits.

Vogtle Units 1 and 2 3.4.12-4 FREQUENCY COPS 3.4.12 In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY:

MODES 1 and 2, MODE 3 with RCS average temperature (T av11) ~ 500°F.

ACTIONS LCO 3.0.4c is applicable.

CONDITION A.

DOSE EQUIVALENT A.1 1-131 > 1.0J!Ci/gm.

AND A.2 B.

Gross specific activity of B.1 the reactor coolant not within limit.

Vogtle Units 1 and 2

--NOTE------

REQUIRED ACTION COMPLETION TIME Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT 1-131 within the acceptable region of Figure 3.4.16-1.

Restore DOSE EQUIVALENT 1-131 to within limit.

Be in MODE 3 with T aVII < 500°F.

3.4.16-1 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 6 hours (continued)

Amendment No.

(Unit 1)

(Unit 2)

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION D.

Required Action and associated Completion Time not met.

D.1 AND D.2 Be in MODE 3.

Be in MODE 5.

SURVEILLANCE REQUIREMENTS SR 3.6.3.1 SR 3.6.3.2 SR 3.6.3.3 SURVEILLANCE Verify each 24 inch purge valve is sealed closed, except for one purge valve in a penetration flow path while in Condition C of this LCO.

Verify each 14 inch purge valve is closed, except when the associated penetration(s) is (are) permitted to be open for purge or venting operations and purge system surveillance and maintenance testing under administrative control.

NOTE----------

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

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

COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

Vogtle Units 1 and 2 3.6.3-4 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)_

SR 3.6.3.4 SR 3.6.3.5 SR 3.6.3.6 SR 3.6.3.7

1.

SURVEILLANCE

NOTES---------

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

2.

The fuel transfer tube blind flange is only required to be verified closed once after refueling prior to entering MODE 4 from MODES.

Verify each containment isolation manual valve and blind flange that is located inside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

Verify the isolation time of each automatic power operated containment isolation valve is within limits.

Perform leakage rate testing for containment purge valves with resilient seals.

Verify each automatic containment isolation valve that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

FREQUENCY Prior to entering MODE4 from MODE 5 if not performed within the previous 92 days In accordance with the lnservice Testing Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Vogtle Units 1 and 2 3.6.3-5 Amendment No.

Amendment No.

(Unit 1)

{Unit 2)

3. 7 PLANT SYSTEMS AFWSystem 3.7.5 3.7.5 Auxiliary Feedwater (AFW) System LCO 3. 7.5 Three AFW trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS LCO 3.0.4b is not applicable.

CONDITION A.

One steam supply to A.1 turbine driven AFW pump inoperable.

OR

---NOTE---

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

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

B.

One AFW train 8.1 inoperable for reasons other than Condition A.

Vogtle Units 1 and 2 NOTE----------------

REQUIRED ACTION Restore affected equipment to OPERABLE status.

Restore AFW train to OPERABLE status.

3.7.5-1 COMPLETION TIME 7 days 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (continued)

Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

SURVEILLANCE REQUIREMENTS SR 3.7.5.1 SR 3.7.5.2 SURVEILLANCE NOTE---

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

Verify each AFW manual, power operated, and automatic valve in each water flow path, and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

NOTE.-----*

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after ~ 900 psig in the steam generator.

Verify the developed head of each AFW pump at the flow test point is greater than or equal to the required developed head.

AFWSystem 3.7.5 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

Vogtle Units 1 and 2 3.7.5-3 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

SR 3.7.5.3 SR 3.7.5.4 SURVEILLANCE

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

Verify each AFW automatic valve that is not locked, sealed, or otherwise secured in position actuates to the correct position on an actual or simulated actuation signal.

NOTES-----

1. Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after ~ 900 psig in the steam generator.

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

Verify each AFW pump starts automatically on an actual or simulated actuation signal.

AFWSystem 3.7.5 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

Vogtle Units 1 and 2 3.7.5-4 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

SURVEILLANCE REQUIREMENTS (continuedl SR 3.7.5.5 SR 3.7.5.6 SURVEILLANCE Verify that each AFW pumphouse ESF supply fan starts and associated dampers actuate on a simulated or actual actuation signal.

Verify that the ESF outside air intake and exhaust dampers for the turbine-driven AFW pump actuate on a simulated or actual actuation signal.

AFWSystem 3.7.5 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Vogtle Units 1 and 2 3.7.5-5 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

Diesel Fuel Oil, Lube Oil, Starting Air, and Ventilation 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains In accordance with

~ 68,000 gal of fuel.

the Surveillance Frequency Control Program SR 3.8.3.2 Verify lube oil inventory is~ 336 gal.

In accordance with the Surveillance Frequency Control Program SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil In accordance with are tested in accordance with, and maintained the Diesel Fuel Oil within the limits of, the Diesel Fuel Oil Testing Testing Program Program.

SR 3.8.3.4 Verify each DG has one air start receiver with a In accordance with pressure ~ 210 psig.

the Surveillance Frequency Control Program SR 3.8.3.5 Check for and remove accumulated water from In accordance with each fuel oil storage tank.

the Surveillance Frequency Control Program SR 3.8.3.6 Verify each DG ventilation supply fan starts and In accordance with the necessary dampers actuate on a simulated or the Surveillance actual actuation signal.

Frequency Control Program Vogtle Units 1 and 2 3.8.3-3 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration Boron Concentration 3.9.1 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.

NOTE---

Only applicable to the refueling canal and refueling cavity when connected to the RCS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Boron concentration not A.1 Suspend CORE Immediately within limit.

ALTERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

AND A.3 Initiate action to restore Immediately boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SR 3.9.1.1 SURVEILLANCE Verify boron concentration is within the limit specified in the COLR.

Vogtle Units 1 and 2 3.9.1-1 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

Containment Penetrations 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Containment Penetrations LCO 3.9.4 The containment penetrations shall be in the following status:

a.

The equipment hatch is capable of being closed and held in place by four bolts;

b.

The emergency and personnel air locks are isolated by at least one air lock door, or if open, the emergency and personnel air locks are isolable by at least one air lock door with a designated individual available to close the open air lock door(s); and

c.

Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:

1.

closed by a manual or automatic isolation valve, blind flange, or equivalent, or

2.

capable of being closed by at least two OPERABLE Containment Ventilation Isolation valves

---NOTE-*--*

Penetration flow path(s) providing direct access from the containment atmosphere to the outside atmosphere may be unisolated under administrative controls.

APPLICABILITY:

During CORE ALTERATIONS, During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more containment A. 1 Suspend CORE ALTERATIONS.

Immediately penetrations not in required status.

Vogtle Units 1 and 2 A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

3.9.4-1 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

SURVEILLANCE REQUIREMENTS SR 3.9.4.1 SR 3.9.4.2 SR 3.9.4.3 SURVEILLANCE Verify each required containment penetration is in the required status.

*--------NOTE-----------------

Not required to be met for containment purge and exhaust valve(s) in penetrations closed to comply with LCO 3.9.4.c.1.

Verify at least two containment ventilation valves in each open containment ventilation penetration providing direct access from the containment atmosphere to the outside atmosphere are capable of being closed from the control room.

NOTE---*--------------

Only required for an open equipment hatch.

Verify the capability to install the equipment hatch.

Vogtle Units 1 and 2 3.9.4-2 Containment Penetrations 3.9.4 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

RHR and Coolant Circulation-Low Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.

NOTES---

1. One RHR loop may be inoperable for s 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

2. All RHR pumps may be de-energized for s 15 minutes when switching from one train to another provided:

a.

The core outlet temperature is maintained > 10 degrees F below saturation temperature.

b.

No operations are permitted that would cause a reduction of the Reactor Coolant System (RCS) boron concentration; and

c.

No draining operations to further reduce RCS water volume are permitted.

APPLICABILITY:

MODE 6 with the water level < 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION A.

Less than the required number of RHR loops OPERABLE.

Vogtle Units 1 and 2 REQUIRED ACTION COMPLETION TIME A.1 Initiate action to restore Immediately required RHR loops to OPERABLE status.

A.2 Initiate action to Immediately establish ~ 23 ft of water above the top of reactor vessel flange.

(continued) 3.9.6-1 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

ACTIONS RHR and Coolant Circulation-Low Water Level 3.9.6 CONDITION REQUIRED ACTION COMPLETION TIME

8.

No RHR loop in operation.

8.1 Suspend operations involving a reduction in reactor coolant boron concentration.

Immediately 8.2 Initiate action to restore Immediately one RHR loop to AND 8.3 operation.

Close all containment penetrations providing direct access from containment atmosphere to outside atmosphere.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SURVEILLANCE REQUIREMENTS SR 3.9.6.1 SR 3.9.6.2 SURVEILLANCE Verify one RHR loop is in operation and circulating reactor coolant at a flow rate of;:: 3000 gpm.

NOTE---*

An operating RHR loop will meet this requirement for the RHR loop running unless the RHR loop is in a low flow system operation.

Verify RHR loop locations susceptible to gas accumulation are sufficiently filled with water.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Vogtle Units 1 and 2 3.9.6-2 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program Programs and Manuals 5.5 This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a.

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b.

Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentrations stated in 10 CFR 20, Appendix B (to paragraphs 20.1001-20.2401),

Table 2, Column 2;

c.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d.

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e.

Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.

Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days.

f.

Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that Vogtle Units 1 and 2 5.5-3 Amendment No.

Amendment No.

(continued}

(Unit 1)

(Unit 2}

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.15 Safety Function Determination Program <SFDP>

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate actions may be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:

a.

Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b.

Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c.

Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d.

Other appropriate limitations and remedial or compensatory actions.

A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a.

A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or

b.

A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or

c.

A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

(continued)

Vogtle Units 1 and 2 5.5-15 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Containment Leakage Rate Testing Program (continued)

4.

The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR 50, Appendix J, Option 8, will be performed in accordance with the requirements of and frequency specified by the ASME Section XI code, Subsection IWE, except where relief has been authorized by the NRC.

5.

A one time exception to NEI 94-01, Rev. 0, "Industry Guidelines for Implementing Performance-Based Option of 10 CFR 50, Appendix J":

Section 9.2.3:

The next Type A test, after the March 2002 test for Unit 1 and the March 1995 test for Unit 2, shall be performed within 15 years.

The peak calculated primary containment internal pressure for the design basis loss of coolant accident, P., is 37 psig.

The maximum allowable containment leakage rate, La, at P,, is 0.2% of primary containment air weight per day.

Leakage rate acceptance criteria are:

a.

Containment overall leakage rate acceptance criteria are s 1.0 L.. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are ' ~ 0.60 La for the combined Type 8 and Type C tests, and s 0.75 La for Type A tests;

b.

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is s: 0.05 La when tested at~ Pa.

2)

For each door, the leakage rate is ~ 0.01 La when pressurized to a: P *.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

(continued)

Vogtle Units 1 and 2 5.5-17 Amendment No.

Amendment No.

(Unit 1}

(Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.18 5.5.19 Configuration Risk Management Program The Configuration Risk Management Program (CRMP) provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability. The program applies to technical specification structures, systems, or components for which a risk-informed allowed outage time has been granted. The program shall include the following elements:

a.

Provisions for the control and implementation of a level 1 at power internal events PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.

b.

Provisions for performing an assessment prior to entering the LCO Condition for preplan ned activities.

c.

Provisions for performing an assessment after entering the LCO Condition for unplanned entry into the LCO Condition.

d.

Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Condition.

e.

Provisions for considering other applicable risk significant contributors such as Level2 issues and external events, qualitatively or quantitatively.

Battery Monitoring and Maintenance Program This program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," of the following:

a.

Actions to restore battery cells with float voltage< 2.13 V, and

b.

Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates.

(continued)

Vogtle Units 1 and 2 5.5-18 Amendment No.