Text

Part 1 of 6 - Tech Spec Pages for Amendments 231 and 212 for North Anna, Units 1 & 2. Table of Contents Through Page 3.5.2-3
	ML021220108
Person / Time
Site:	North Anna
Issue date:	04/05/2002
From:	; Office of Nuclear Reactor Regulation
To:	;
References
	-nr, TAC MB0799, TAC MB0800
	Download: ML021220108 (183)
	v • d • e

TECHNICAL SPECIFICATIONS FOR NORTH ANNA UNITS 1 & 2

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 3.0 3.0 INSTRUMENTATION.

Reactor Trip System (RTS)

Instrumentation..

Engineered Safety Feature Actuation System (ESFAS)

Instrumentation..............

Post Accident Monitoring (PAM)

Instrumentation Remote Shutdown System Loss of Power (LOP)

Emergency Diesel Generator (EDG)

Start Instrumentation...........

1.1-1 1.1-1 1.2-1 1.3-1 1.4-1

. 2.0-1 2.0-1 2.0-1 USE AND APPLICATION.........

Definitions........

Logical Connectors Completion Times Frequency...........

SAFETY LIMITS (SLs)..........

SLs......................................

SL Violations......

LIMITING CONDITION FOR OPERATION (LCO)

APPLICABILITY SURVEILLANCE REQUIREMENT (SR)

APPLICABILITY..........

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM).....

Core Reactivity.................

Moderator Temperature Coefficient (MTC).......

Rod Group Alignment Limits Shutdown Bank Insertion Limits Control Bank Insertion Limits..............

Rod Position Indication..................

Primary Grade Water Flow Path Isolation Valves PHYSICS TESTS Exceptions-MODE 2.............

POWER DISTRIBUTION LIMITS.

Heat Flux Hot Channel Factor'(FQ(Z))....N.

Nuclear Enthalpy Rise Hot Channel Factor (FH)

AXIAL FLUX DIFFERENCE (AFD).....

QUADRANT POWER TILT RATIO (QPTR) 3.3.1-1 3.3.1-1 3.3.2-1 3.3.3-1 3.3.4-1 3.3.5-1 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6 3.1.7 3.1.8 3.1.9 3.2 3.2.1 3.2.2 3.2.3 3.2.4 3.3 3.3.1 3.3.2 3.3.3 3.3.4 3.3.5 3.4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 North Anna Units 1 and 2

.. 3.0-1

. 3.0-4 3.1.1-1 3.1.1-1 3.1.2-1 3.1.3-1 3.1.4-1 3.1.5-1 3.1.6-1 3.1.7-1 3.1.8-1 3.1.9-1 3.2.1-1 3.2.1-1 3.2.2-1 3.2.3-1

. 3.2.4-1 REACTOR COOLANT SYSTEM (RCS) 3.4.1-1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits.........

3.4.1-1 RCS Minimum Temperature for Criticality...........

3.4.2-1 RCS Pressure and Temperature (P/T) Limits.........

3.4.3-1 RCS Loops-MODES 1 and 2.....

.. 3.4.4-1 RCS Loops-MODE 3........

.. 3.4.5-1 RCS Loops-MODE 4........

.. 3.4.6-1 RCS Loops-MODE 5, Loops Filled...............

.. 3.4.7-1 RCS Loops-MODE 5, Loops Not Filled..............

3.4.8-1 Pressurizer...........

3.4.9-1 Amendments 231/212, i

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS 3.4 3.4.10 3.4.11 3.4.12 3.4.13 3.4.14 3.4.15 3.4.16 3.4.17 3.4.18 3.4.19 3.5 3.5.1 3.5.2 3.5.3 3.5.4 3.5.5 3.5.6 3.6 3.6.1 3.6.2 3.6.3 3.6.4 3.6.5 3.6.6 3.6.7 3.6.8 3.6.9 3.7 3.7.1 3.7.2 3.7.3 3.7.4 3.7.5 3.7.6 3.7.7 3.7.8 3.7.9 CONTAINMENT SYSTEMS..............

Containment..............

Containment Air Locks........

Containment Isolation Valves Containment Pressure Containment Air Temperature.

Quench Spray (QS) System Recirculation Spray (RS)

System Chemical Addition System Hydrogen Recombiners PLANT SYSTEMS..........................

Main Steam Safety Valves (MSSVs)

Main Steam Trip Valves (MSTVs)

Main Feedwater Isolation Valves (MFIVs),

Main Feedwater Pump Discharge Valves (MFPDVs),

Main Feedwater Regulating Valves (MFRVs),

and Main Feedwater Regulating Bypass Valves (MFRBVs)

Steam Generator Power Operated Relief Valves (SG PORVs)

Auxiliary Feedwater (AFW)

System Emergency Condensate Storage Tank (ECST)

Secondary Specific Activity..............

Service Water (SW)

System..............

Ultimate Heat Sink (UHS)

REACTOR COOLANT SYSTEM (RCS)

(continued)

Pressurizer Safety Valves...............

Pressurizer Power Operated Relief Valves (PORVs)...................

Low Temperature Overpressure Protection (LTOP)

System RCS Operational LEAKAGE.

RCS Pressure Isolation Valve (PIV) Leakage RCS Leakage Detection Instrumentation.....

RCS Specific Activity..................

RCS Loop Isolation Valves...............

RCS Isolated Loop Startup...............

RCS Loops-Test Exceptions...............

EMERGENCY CORE COOLING SYSTEMS (ECCS).........

Accumulators ECCS-Operating ECCS-Shutdown.

Refueling Water Storage Tank (RWST)......

Seal Injection Flow..............

Boron Injection Tank (BIT)..............

3.6.1-1 3.6.1-1 3.6.2-1 3.6.3-1 3.6.4-1 3.6.5-1 3.6.6-1 3.6.7-1 3.6.8-1 3.6.9-1 3.7.1-1 3.7.1-1 3.7.2-1

... 3.7.3-1 3.7.4-1 3.7.5-1 3.7.6-1 3.7.7-1 3.7.8-1 3.7.9-1 Amendments 231/212, North Anna Units 1 and 2

..3.4.10-1

.3.4.11-1 3.4.12-1 3.4.13-1 3.4.14-1

.3.4.15-1 3.4.16-1 3.4.17-1 3.4.18-1

.3.4.19-1 3.5.1-1 3.5.1-1 3.5.2-1 3.5.3-1 3.5.4-1

... 3.5.5-1

- - - 3.5.6-1 i i

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS 3.7 3.7.10 3.7.11 3.7.12 3.7.13 3.7.14 3.7.15 3.7.16 3.7.17 3.7.18 3.7.19 3.8 3.8.1 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.8.8 3.8.9 3.8.10 3.9 3.9.1 3.9.2 3.9.3 3.9.4 3.9.5 3.9.6 3.9.7 4.0 4.1 4.2 4.3 ELECTRICAL POWER SYSTEMS AC Sources-Operating AC Sources-Shutdown.

Diesel Fuel Oil and Starting Air DC Sources-Operating DC Sources-Shutdown....

Battery Cell Parameters............

Inverters-Operating....

Inverters-Shutdown Distribution Systems-Operating Distribution Systems-Shutdown........

REFUELING OPERATIONS Boron Concentration....

Primary Grade Water Flow Path Isolation Valves-MODE6................

Nuclear Instrumentation.............

Containment Penetrations Residual Heat Removal (RHR) and Coolant Circulation-High Water Level Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level.......

Refueling Cavity Water Level DESIGN FEATURES......................

Site Location......................

Reactor Core Fuel Storage PLANT SYSTEMS (continued)

Main Control Room/Emergency Switchgear Room (MCR/ ESGR) Emergency Ventilation System (EVS)-MODES 1, 2, 3, and 4 Main Control Room/Emergency Switchgear Room (MCR/ESGR) Air Conditioning System (ACS)

Emergency Core Cooling System (ECCS)

Pump Room Exhaust Air Cleanup System (PREACS)

Main Control Room/Emergency Switchgear Room (MCR/ESGR) Bottled Air System.........

Main Control Room/Emergency Switchgear Room (MCR/ESGR)

Emergency Ventilation System (EVS)-During Movement of Recently Irradiated Fuel Assemblies Fuel Building Ventilation System (FBVS)

Fuel Storage Pool Water Level............

Fuel Storage Pool Boron Concentration.......

Spent Fuel Pool Storage............

Component Cooling Water (CC)

System........

3.9.1-1 3.9.1-1 S....

. 3.9.2-1 S....

. 3.9.3-1 S....

. 3.9.4-1 S....

. 3.9.5-1 S....

. 3.9.6-1 S....

. 3.9.7-1 S....

. 4.0-1 S....

. 4.0-1 North Anna Units 1 and 2

...3.7.10-1

...3.7.11-1

...3.7.12-1

...3.7.13-1

. *3.7.14-1 3.7.15-1 3.7.16-1

.**3.7.17-1

.*.3.7.18-1

3.7.19-1 3.8.1-1 3.8.1-1 3.8.2-1 3.8.3-1 3.8.4-1

.*..3.8.5-1

.3.8.6-1

... 3.8.7-1 3.8.8-1 3.8.9-1

.*.3.8.10-1 Amendments 231/212, iii

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility...........

5.1-1 5.2 Organization........

.5.2-1 5.3 Unit Staff Qualifications.......................

5.3-1 5.4 Procedures.........

5.4-1 5.5 Programs and Manuals......

5.5-1 5.6 Reporting Requirements......

5.6-1 5.7 High Radiation Area.........

5.7-1 North Anna Units 1 and 2 Amendments 231/212, iv

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions NOTE The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term ACTIONS ACTUATION LOGIC TEST AXIAL FLUX DIFFERENCE (AFD)

CHANNEL CALIBRATION Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in conjunction with each possible interlock logic state required for OPERABILITY of a logic circuit and the verification of the required logic output.

The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices.

AFD shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel.

The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

North Anna Units 1 and 2 Amendments 231/212, 1.1-1

Definitions 1.1 1.1 Definitions CHANNEL CHECK CHANNEL OPERATIONAL TEST (COT)

CORE ALTERATION CORE OPERATING LIMITS REPORT (COLR)

DOSE EQUIVALENT 1-131 A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps.

CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844,

AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites."

North Anna Units 1 and 2 Amendments 231/212, 1.1-2

Definitions 1.1 1.1 Definitions E-AVERAGE DISINTEGRATION ENERGY ENGINEERED SAFETY FEATURE (ESF) RESPONSE TIME LEAKAGE E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives > 15 minutes, making up at least 95% of the total noniodine activity in the coolant.

The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

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 (SG) to the Secondary System; (continued)

North Anna Units 1 and 2 Amendments 231/212, 1.1-3

Definitions 1.1 1.1 Definitions

b. Unidentified LEAKAGE LEAKAGE (continued)

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

c. Pressure Boundary LEAKAGE MASTER RELAY TEST MODE OPERABLE-OPERABILITY PHYSICS TESTS LEAKAGE (except SG LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.

A MASTER RELAY TEST shall consist of energizing all master relays in the channel required for channel OPERABILITY and verifying the OPERABILITY of each required master relay. The MASTER RELAY TEST shall include a continuity check of each associated required slave relay. The MASTER RELAY TEST may be performed by means of any series of sequential, overlapping, or total steps.

A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

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

PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a. Described in Chapter 14, Initial Tests and Operation, of the UFSAR; (continued)

North Anna Units 1 and 2 Amendments 231/212, 1.1-4

Definitions 1.1 1.1 Definitions PHYSICS TESTS (continued)

QUADRANT POWER TILT RATIO (QPTR)

RATED THERMAL POWER (RTP)

REACTOR TRIP SYSTEM (RTS)

RESPONSE TIME SHUTDOWN MARGIN (SDM)

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

QPTR shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2893 MWt.

The RTS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RTS trip setpoint at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

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

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. 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 nominal zero power design level.

North Anna Units 1 and 2 Amendments 231/212, 1.1-5

Definitions 1.1 1.1 Definitions SLAVE RELAY TEST STAGGERED TEST BASIS THERMAL POWER TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT)

A SLAVE RELAY TEST shall consist of energizing all slave relays in the channel required for channel OPERABILITY and verifying the OPERABILITY of each required slave relay. The SLAVE RELAY TEST shall include a continuity check of associated required testable actuation devices. The SLAVE RELAY TEST may be performed by means of any series of sequential, overlapping, or total steps.

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 TADOT shall consist of operating the trip actuating device and verifying the OPERABILITY of all devices in the channel required for trip actuating device OPERABILITY. The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the necessary accuracy.

The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps.

Amendments 231/212, North Anna Units 1 and 2 1.1-6

Definitions 1.1 Table 1.1-1 (page 1 of 1)

MODES REACTIVITY

% RATED AVERAGE REACTOR CONDITION THERMAL COOLANT TEMPERATURE MODE TITLE (keff)

POWER(a)

(OF) 1 Power Operation

> 0.99

> 5 NA 2

Startup

> 0.99

5 NA 3

Hot Standby

< 0.99 NA

Ž 350 4

Hot Shutdown(b)

< 0.99 NA 350 > Tavg > 200 5

Cold Shutdown(b)

< 0.99 NA

200 6

Refueling(c)

NA NA NA Excluding decay heat.

All reactor vessel head closure bolts fully tensioned.

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

Amendments 231/212, North Anna Units 1 and 2 (a)

(b)

(c) 1.1-7

Intentionally Blank

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes 1ogical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.

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

North Anna Units 1 and 2 PURPOSE Amendments 231/212, 1.2-1

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES The following examples illustrate the use of logical connectors.

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

LCO not met.

A.1 Verify...

AND A.2 Restore...

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

North Anna Units 1 and 2 Amendments 231/212, 1.2-2

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

LCO not met.

A.1 Trip...

OR A.2.1 Verify AND A.2.2.1 Reduce OR A.2.2.2 Perform...

OR A.3 Align...

This example represents a more complicated use of logical connectors. Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND.

Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative c-hoices, only one of which must be performed.

North Anna Units 1 and 2 Amendments 231/212, 1.2-3

Intentionally Blank

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

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

The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of 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 LCO. 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 LCO Applicability.

If situations are discovered that require entry into more 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 time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be 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.

(continued)

North Anna Units 1 and 2 PURPOSE Amendments 231/212, 1.3-1

Completion Times 1.3 1.3 Completion Times DESCRIPTION However, when a subsequent train, subsystem, component, or (continued) 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 extensions do 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.

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 B in Example 1.3-3 may not be extended.

North Anna Units 1 and 2 Amendments 231/212, 1.3-2

Completion Times 1.3 1.3 Completion Times 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.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met.

B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Condition B has two Required Actions. Each has its own separate Completion Time. Each is referenced to the time that Condition B Required Action Completion Time is entered.

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

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

time allowed North Anna Units 1 and 2 EXAMPLES Amendments 231/212, 1.3-3

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump to 7 days inoperable.

OPERABLE status.

B. Required B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met.

B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a pump is declared inoperable, Condition A is entered.

If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

When a second pump is declared inoperable while the first pump is still inoperable, Condition A is not re-entered for the second pump.

LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump.

The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition A.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.

(continued)

North Anna Units 1 and 2 Amendments 231/212, 1.3-4

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

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

> 7 days.

North Anna Units 1 and 2 Amendments 231/212, 1.3-5

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore Function X 7 days Function X train to OPERABLE train status.

AND inoperable.

10 days from discovery of failure to meet the LCO B. One B.1 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y train to OPERABLE train status.

AND inoperable.

10 days from discovery of failure to meet the LCO C. One C.1 Restore Function X 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function X train to OPERABLE train status.

inoperable.

OR AND C.2 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months One train to OPERABLE Function Y status.

train inoperable.

(continued)

North Anna Units 1 and 2 Amendments 231/212, 1.3-6

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e.,

initial entry into Condition A).

The Completion Times of Conditions A and B are modified by a logical connector with a separate 10 day Completion Time measured from the time it was discovered the LCO was not met.

In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO.

The separate Completion Time modified by the phrase "from discovery of failure to meet the LCO" is designed to prevent indefinite continued operation while not meeting the LCO.

This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock".

In this instance, the Completion Time "time zero" is specified as commencing at the time the LCO was initially not met, instead of at the time the associated Condition was entered.

North Anna Units 1 and 2 Amendments 231/212, 1.3-7

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves to OPERABLE inoperable, status.

B. Required B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met.

B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis.

Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (including the extension) expires while one or more valves are still inoperable, Condition B-is entered.

North Anna Units 1 and 2 Amendments 231/212, 1.3-8

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-5 ACTIONS

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

Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met.

B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve.

If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are (continued)

North Anna Units 1 and 2 Amendments 231/212, 1.3-9

Completion Times 1.3 1.3 Completion Times EXAMPLES North Anna Units 1 and 2 EXAMPLE 1.3-5 (continued) tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

SR 3.x.x.x.

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.

B. Required B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated Completion Time not met.

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance.

The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed, and the Required Action is not met within the Completion Time (plus (continued)

Amendments 231/212, 1.3-10

Completion Times 1.3 1.3 Completion Times EXAMPLES Required Action A.1 has two Completion Completion Time begins at the time the and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" performance of Required Action A.1.

Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Condition is entered interval begins upon (continued)

North Anna Units 1 and 2 EXAMPLE 1.3-6 (continued) the extension allowed by SR 3.0.2), Condition B is entered.

If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.

EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One subsystem A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, subsystem isolated.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

B. Required B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met.

B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Amendments 231/212, 1.3-11

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

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

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

North Anna Units 1 and 2 Amendments 231/212,,

1.3-12

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

DESCRIPTION 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.

(continued)

North Anna Units 1 and 2 Amendments 231/212, 1.4-1

Frequency 1.4 1.4 Frequency DESCRIPTION (continued)

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 discusses these special situations.

EXAMPLES 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.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK.

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 (continued)

North Anna Units 1 and 2 Amendments 231/212, 1.4-2

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued) 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 interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise 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, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of SR 3.0.4.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits.

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

Ž 25% RTP AND 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

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

(continued)

North Anna Units 1 and 2 Amendments 231/212, 1.4-3

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)

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 25% 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.

EXAMPLE 1.4-3 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 Ž 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 Ž 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 Ž 25% RTP.

(continued)

North Anna Units 1 and 2 Amendments 231/212, 1.4-4

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued)

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.

EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY NOTE-------------

Only required to be met in MODE 1.

Verify leakage rates are within limits.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Surveillance do not have 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 the 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 3.0.2 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.

North Anna Units 1 and 2 Amendments 231/212, 1.4-5

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-5 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be performed in MODE 1.

Perform complete cycle of the valve.

7 days The interval continues, whether or not the unit operation is in MODE 1, 2, or 3 (the assumed 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.

North Anna Units 1 and 2 Amendments 231/212, 1.4-6

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-6 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be met in MODE 3.

Verify parameter is within limits.

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 while 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.

North Anna Units 1 and 2 Amendments 231/212, 1.4-7

Intentionally Blank

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR; and the following SLs shall not be exceeded.

2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained greater than or equal to the 95/95 DNBR criterion for the DNB correlations and methodologies specified in Section 5.6.5.

2.1.1.2 The peak fuel centerline temperature shall be maintained

< 47000F.

2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained 5 2735 psig.

2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

North Anna Units 1 and 2 Amendments 231/212, 2.0-1

Intentionally Blank

LCO APPLICABILITY 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a. MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b.

MODE 4 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c.

MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.

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 specific condition in the Applicability for an unlimited period of

time, (continued)

North Anna Units 1 and 2 Amendments 231/212, 3.0-1

LCO APPLICABILITY 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 (continued)

b. After performance of a risk evaluation, consideration of the results, determination of the acceptability of the MODE change, and establishment of risk management actions, if appropriate, or

c. When a specific value or parameter allowance has been approved by the NRC.

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.

LCO 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, 3, and 4.

LCO 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 testing required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.14, "Safety Function Determination Program (SFDP)." 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 support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

North Anna Units 1 and 2 Amendments 231/212, 3.0-2

LCO APPLICABILITY 3.0 3.0 LCO APPLICABILITY LCO 3.0.7 Test Exception LCOs 3.1.9 and 3.4.19 allow specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional.

When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

North Anna Units 1 and 2 Amendments 231/212, 3.0-3

SR APPLICABILITY 3.0 3.0 SURVEILLANCE REQUIREMENT (SR)

APPLICABILITY SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

Surveillances may be performed by any series of sequential, overlapping, or total steps.

The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per.

." basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

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. 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.

(continued)

North Anna Units 1 and 2 SR 3.0.1 SR 3.0.2 SR 3.0.3 Amendments 231/212, 3.0-4

SR APPLICABILITY 3.0 3.0 SR APPLICABILITY SR 3.0.3 When the Surveillance is performed within the delay period (continued) 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. When an LCO is not met, entry into a MODE or other specific condition in the Applicability shall only be made:

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

time,

b. After performance of a risk evaluation, consideration of the results, determination of the acceptability of the MODE change, and establishment of risk management actions, if appropriate, or

c. When a specific value or parameter allowance has been approved by the NRC.

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 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, 3 and 4.

North Anna Units 1 and 2 Amendments 231/212, 3.0-5

Intentionally Blank

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

LCO

3.1.1 APPLICABILITY

SDM shall be within the limits provided in the COLR.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

SDM not within limit.

A.1 Initiate boration to 15 minutes restore SDM to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within limits.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months North Anna Units 1 and 2 Amendments 231/212, 3.1.1-1

Intentionally Blank

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

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Measured core A.1 Re-evaluate core 7 days reactivity not within design and safety

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

AND A.2 Establish appropriate 7 days 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.

North Anna Units 1 and 2 Amendments 231/212, 3.1.2-1

Core Reactivity 3.1.2 SURVEILLANCE REQUIREMENTS NOTE---------------

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

Verify measured core reactivity is within

+/- 1% Ak/k of predicted values.

FREQUENCY Once prior to entering MODE 1 after each refuel i ng AND NOTE -----

Only required after 60 EFPD 31 EFPD thereafter North Anna Units 1 and 2 SR 3.1.2.1 SURVEILLANCE 3.1.2-2 I

i Amendments 231/212,

MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.3 APPLICABILITY:

The MTC shall be maintained within the limits specified in the COLR. The uper limit specified in the COLR shall be

0.6 x 10-Ak/k/°F when < 70% RTP, and

0.0 Ak/k/°F when

Ž70% RTP.

MODE 1 and MODE 2 with keff Ž 1.0 for the upper MTC limit, MODES 1, 2, and 3 for the lower MTC limit.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

MTC not within upper A.1 Establish 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months limit.

admi ni strati ve withdrawal limits for control banks to maintain MTC within limit.

B.

Required Action and B.1 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 of Condition A not met.

C.

MTC not within lower C.1 Be in MODE 4.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within upper limit.

Once prior to entering MODE 1 after each refuel i ng North Anna Units 1 and 2 Amendments 231/212, 3.1.3-1

MTC 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.1.3.2

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

1. Not required to be performed until 7 effective full power days (EFPD) after reaching the equivalent of an equilibrium RTP all rods out (ARO) boron concentration of 300 ppm

2. If the MTC is more negative than the 300 ppm Surveillance limit (not LCO limit) specified in the COLR, SR 3.1.3.2 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.

3. SR 3.1.3.2 need not MTC measured at the equilibrium RTP-ARO of

60 ppm is less 60 ppm Surveillance the COLR.

be repeated if the equivalent of boron concentration negative than the limit specified in Verify MTC is within lower limit.

North Anna Units 1 and 2 FREQUENCY Once each cycle I

Amendments 231/212, 3.1.3-2

Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO

3.1.4 APPLICABILITY

All shutdown and control rods shall be OPERABLE.

AND Individual indicated rod positions shall be within 12 steps of their group step counter demand position.

NOTE When THERMAL POWER is

50% RTP, the indicated position of each rod as determined by its individual rod position indicator may be within 24 steps from its group step counter demand position for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

This NOTE is not applicable for control rods known to be greater than 12 steps from the rod group step counter demand position.

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more rod(s)

A.1.1 Verify SDM to be 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, within the limits provided in the COLR.

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

AND A.2 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months North Anna Units 1 and 2 Amendments 231/212, 3.1.4-1

Rod Group Alignment Limits 3.1.4 CONDITION REQUIRED ACTION COMPLETION TIME B.

One rod not within alignment limits.

Verify SDM to be within the limits provided in the COLR.

OR B.1.2 Initiate boration to restore SDM to within limit.

AND B.2.1 Reduce THERMAL POWER to

75% RTP.

OR B.2.2.1 Perform SR 3.2.1.1.

AND B.2.2.2 Perform SR 3.2.2.1.

AND B.3 Re-evaluate safety analyses and confirm results remain valid for duration of operation under these conditions.

B.1.1 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 not met.

North Anna Units 1 and 2 ACTIONS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 2 hours 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 72 hours 5 days Amendments 231/212, 3.1.4-2

Rod Group Alignment Limits 3.1.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. More than one rod not D.1.1 Verify SDM to be 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within alignment within the limit

limit, provided in the COLR.

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

AND D.2 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months alignment limit.

SR 3.1.4.2 Verify rod freedom of movement 92 days (trippability) by moving each rod not fully inserted in the core Ž 10 steps in either direction.

SR 3.1.4.3 Verify rod drop time of each rod, from the Prior to reactor 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 Ž 500°F; and

b. All reactor coolant pumps operating.

North Anna Units 1 and 2 Amendments 231/212, 3.1.4-3

Intentionally Blank

Shutdown Bank Insertion 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.5 APPLICABILITY:

Each shutdown bank shall be within insertion limits specified in the COLR.

MODES 1 and 2.

NOTE-This LCO is not applicable while performing SR 3.1.4.2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more shutdown A.1.1 Verify SDM to be 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months banks not within within the limits limits for reasons provided in the COLR.

other than Condition B.

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

AND A.2 Restore shutdown banks 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to within limits.

North Anna Units 1 and 2 Limits 3.1.5 Amendments 231/212, 3.1.5-1

Shutdown Bank Insertion Limits 3.1.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

One shutdown bank B.1 Verify SDM to be Once per inserted

18 steps within the limits 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months below the insertion provided in the COLR.

limit and immovable.

AND AND B.2 Restore the shutdown 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Each control and bank to within shutdown rod within insertion limit.

limits of LCO 3.1.4.

AND Each control bank within the insertion limits of LCO 3.1.6.

C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each shutdown bank is within the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months insertion limits specified in the COLR.

North Anna Units 1 and 2 3.1.5-2 Amendments 231/212,

Control Bank Insertion Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Control Bank Insertion Limits LCO

3.1.6 APPLICABILITY

Control banks shall be within the insertion, sequence, and overlap limits specified in the COLR.

MODE 1, MODE 2 with keff Ž 1.0.

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

This LCO is not applicable while performing SR 3.1.4.2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control bank sequence A.1.1 Verify SDM to be 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or overlap limits not within the limits met.

provided in the COLR.

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

AND A.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.

B.

Control bank insertion B.1.1 Verify SDM to be 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limits not met for within the limits reasons other than provided in the COLR.

Condition C.

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 SDM to within limit.

AND (continued)

North Anna Units 1 and 2 Amendments 231/212, 3.1.6-1

Control Bank Insertion Limits 3.1.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.2 Restore control 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months bank(s) to within limits.

C.

Control bank A, B, C.1 Verify SDM to be Once per or C inserted within the limits 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

< 18 steps below the provided in the COLR.

insertion limit and immovable.

AND AND C.2 Restore the control 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months bank to within Each control and insertion limit.

shutdown rod within limits of LCO 3.1.4.

AND Each shutdown bank within the insertion limits of LCO 3.1.5.

D.

Required Action and D.1 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 insertion limits prior to specified in the COLR.

achieving criticality North Anna Units 1 and 2 Amendments 231/212, 3.1.6-2

Control Bank Insertion Limits 3.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.2 Verify each control bank is within the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months insertion limits specified in the COLR.

SR 3.1.6.3 Verify each control bank not fully 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months withdrawn fr-om the core is within the sequence and overlap limits specified in the COLR.

North Anna Units 1 and 2 Amendments 231/212, 3.1.6-3

Intentionally Blank

Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Rod Position Indication (RPI) 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 demand position indicator.

CONDITION REQUIRED ACTION COMPLETION TIME A.

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

with inoperable position indicators by using movable incore detectors.

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

North Anna Units 1 and 2 3.1.7-1 Amendments 231/212,

Rod Position Indication 3.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

More than one RPI per B.1 Place the control rods Immediately group inoperable, under manual control.

AND B.2 Monitor and record RCS Once per 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Tavg.

AND B.3 Verify the position of Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the rods with inoperable position indicators indirectly by using the movable incore detectors.

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

C.

One or more rods with C.1 Verify the position 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable position indirectly of the rods indicators have been with inoperable moved in excess of position indicators by 24 steps in one using movable incore direction since the detectors.

last determination of the rod's position.

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

North Anna Units 1 and 2 Amendments 231/212, 3.1.7-2

Rod Position Indication 3.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.

One demand position D.1.1 Verify by Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months indicator per bank administrative means inoperable for one or all RPIs for the more banks.

affected banks are OPERABLE.

AND D.1.2 Verify the most Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months withdrawn rod and the least withdrawn rod of the affected banks are

12 steps apart.

OR D.2 Reduce THERMAL POWER 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to

50% RTP.

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.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Perform CHANNEL CALIBRATION of each RPI.

18 months North Anna Units 1 and 2 Amendments 231/212, 3.1.7-3

Intentionally Blank

Primary Grade Water Flow Path Isolation Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Primary Grade Water Flow Path Isolation Valves LCO

3.1.8 APPLICABILITY

Each valve used to isolate primary grade water flow paths shall be secured in the closed position.

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

Primary grade water flow path isolation valves may be opened under administrative control for planned boron dilution or makeup activities.

MODES 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE --------- A.1 Suspend positive Immediately Required Action A.3 reactivity additions.

must be completed whenever Condition A AND is entered.

A.2 Secure valves in 15 minutes closed position.

One or more valves not secured in closed AND position.

A.3 Perform SR 3.1.1.1.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Verify each valve in the affected flow path Within that isolates primary grade water flow 15 minutes paths is locked, sealed, or otherwise following a secured in the closed position.

boron dilution or makeup activity North Anna Units 1 and 2 3.1.8-1 Amendments 231/212,

Intentionally Blank

PHYSICS TESTS Exceptions-MODE 2 3.1.9 3.1 REACTIVITY CONTROL SYSTEMS 3.1.9 PHYSICS TESTS Exceptions-MODE 2 LCO 3.1.9 During the performance of PHYSICS TESTS, the requirements of LCO LCO LCO LCO LCO 3.1.3, 3.1.4, 3.1.5, 3.1.6, 3.4.2, "Moderator Temperature Coefficient (MTC)";

"Rod Group Alignment Limits";

"Shutdown Bank Insertion Limits";

"Control Bank Insertion Limits"; and "RCS Minimum Temperature for Criticality" may be suspended and the number of required channels for LCO 3.3.1, "RTS Instrumentation," Functions 2, 3, and 18.d, may be reduced to "3" required channels, provided:

a. RCS lowest loop average temperature is Ž 531'F;

b.

SDM is within the limits provided in the COLR; and

c. THERMAL POWER is

5% RTP.

APPLICABILITY:

During PHYSICS TESTS initiated in MODE 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

SDM not within limit.

A.1 Initiate boration to 15 minutes restore SDM to within limit.

AND A.2 Suspend PHYSICS TESTS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months exceptions.

B.

THERMAL POWER not B.1 Open reactor trip Immediately within limit, breakers.

C.

RCS lowest loop C.1 Restore RCS lowest 15 minutes average temperature loop average not within limit, temperature to within limit.

North Anna Units 1 and 2 3.1.9-1 Amendments 231/212,

PHYSICS TESTS Exceptions-MODE 2 3.1.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3.

15 minutes associated Completion Time of Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.9.1 Perform a 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 Table 3.3.1-1.

PHYSICS TESTS SR 3.1.9.2 Verify the RCS lowest loop average 30 minutes temperature is _Ž 5310F.

SR 3.1.9.3 Verify THERMAL POWER is < 5% RTP.

30 minutes SR 3.1.9.4 Verify SDM to be within the limits provided 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in the COLR.

North Anna Units 1 and 2 Amendments 231/212, 3.1.9-2

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

LCO 3.2.1 FQ(Z), as approximated by Fm(Z), shall be within the limits specified in the COLR.

APPLICABILITY:

MODE 1.

ACTIONS CONDITION IREQUIRED ACTION I COMPLETION TIME A.

Fm(Z) not within limit.

A.1 Reduce AFD limits Ž 1%

for each 1% Fm(Z) exceeds limit.

OR A.2.1 Reduce THERMAL POWER

Ž 1% RTP for each 1%

FM(Z) exceeds limit.

AND A.2.2 Reduce Power Range Neutron Flux-High trip setpoints Ž 1% for each 1%, F*m(Z) exceeds limit.

AND A.2.3 Reduce Overpower AT trip setpoints Ž 1%

for each 1% Fm(Z) exceeds limit.

AND A.2.4 Perform SR 3.2.1.1.

15 minutes after each Fm(Z) determi nation 15 minutes after each FQM(Z) determination 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each FQM(Z) determination 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each FQM(Z) determination Prior to increasing THERMAL POWER above the limit of Required Action A.2.1 North Anna Units 1 and 2 i ____________________________

.1 3.2.1-1 Amendments 231/212,

FQ(Z) 3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and B.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS NOTE ----------------

During power escalation, THERMAL POWER may be increased until a power level for extended operation has been achieved, at which a power distribution map is obtained.

North Anna Units 1 and 2 Amendments 231/212, 3.2.1-2

FQ(Z) 3.2.1 SURVEILLANCE REQUIREMENTS SR 3.2.1.1 SURVEILLANCE

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

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

If FM(Z) measurements indicate maximum over z L K(Z)]

has increased since the previous evaluation of Fm(Z):

a. Increase Fm(Z) by the appropriate factor and verify Fm(Z) is still within limits; or

b. Repeat SR 3.2.1.1 once per 7 EFPD until two successive flux maps indicate maximum over z I K(Z) has not increased.

Verify Fm(Z) is within limit.

FREQUENCY Once after each refueling prior to THERMAL POWER exceeding 75% RTP 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

Ž 10% RTP, the THERMAL POWER at which FQ(Z) was last verified AND 31 EFPD thereafter North Anna Units 1 and 2 3.2.1-3 Amendments 231/212,

Intentionally Blank

FNH 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNH)

LCO 3.2.2 FAH shall be within the limits specified in the COLR.

APPLICABILITY:

MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE --------- A.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Actions A.3 to < 50% RTP.

and A.4 must be completed whenever AND Condition A is entered.

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 to FAH not within limit.

_ 55% RTP.

AND A.3 Perform SR 3.2.2.1.

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

North Anna Units 1 and 2 Amendments 231/212, 3.2.2-1

FNH 3.2.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.4

NOTE --------

THERMAL POWER does not have to be reduced to comply with this Required Action.

Perform SR 3.2.2.1.

Prior to THERMAL POWER exceeding 50% RTP AND Prior to THERMAL POWER exceeding 75% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER reaching

> 95% RTP B.

Required Action and B.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify FH is within limits specified in Once after each the COLR.

refueling prior to THERMAL POWER exceeding 75% RTP AND 31 EFPD thereafter North Anna Units 1 and 2 Amendments 231/212, 3.2.2-2

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

LCO 3.2.3 The AFD in % flux difference units 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 Ž 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

AFD not within limits.

A.1 Reduce THERMAL POWER 30 minutes to < 50% RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD within limits for each OPERABLE 7 days excore channel.

North Anna Units 1 and 2 Amendments 231/212, 3.2.3-1

Intentionally Blank

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

LCO

3.2.4 APPLICABILITY

The QPTR shall be

1.02.

MODE 1 with THERMAL POWER > 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

QPTR not within limit.

A.1 Reduce THERMAL POWER 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after

Ž 3% from RTP for each each QPTR 1% of QPTR > 1.00.

determination AND A.2 Determine QPTR.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND A.3 Perform SR 3.2.1.1 and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after SR 3.2.2.1.

achieving equilibrium Conditions from a THERMAL POWER reduction per Required Action A.1 AND Once per 7 days thereafter AND (continued)

North Anna Units 1 and 2 Amendments 231/212, 3.2.4-1

QPTR 3.2.4 ACTIONS CONDITION

[

REQUIRED ACTION COMPLETION TIME A.

(continued)

A.4 Reevaluate safety analyses and confirm results remain valid for duration of operation under this condition.

AND A.5

NOTES------

1. Perform Required Action A.5 only after Requi red Action A.4 is completed.

2. Required Action A.6 shall be completed whenever Required Action A.5 is performed.

Normalize excore detectors to restore QPTR to within limits.

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

I North Anna Units 1 and 2 Amendments 231/212, 3.2.4-2

QPTR 3.2.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.6

NOTE------

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

Perform SR 3.2.1.1 and Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.2.2.1.

after achieving equilibrium Conditions at RTP not to exceed 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 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 3.2.4.1

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

1. With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER *_

75% RTP, the remaining three power range channels can be used for calculating QPTR.

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

Verify QPTR is within limit by calculation. 7 days North Anna Units 1 and 2 Amendments 231/212, 3.2.4-3

QPTR 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.2

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after input from one or more Power Range Neutron Flux channels are inoperable with THERMAL POWER > 75% RTP.

Verify QPTR is within limit using the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months movable incore detectors.

North Anna Units 1 and 2 Amendments 231/212, 3.2.4-4

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO

3.3.1 APPLICABILITY

The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

According to Table 3.3.1-1.

NOTE Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

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

B.

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

inoperable.

OR B.2 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months C.

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

OR C.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 (continued)

North Anna Units 1 and 2 ACTIONS Amendments 231/212, 3.3.1-1

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

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

D.

One Power Range Neutron Flux-High channel inoperable.

NOTE---------

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

D.1.1 Place channel in trip.

AND D.1.2 Reduce THERMAL POWER to

75% RTP.

OR D.2.1 Place channel in trip.

AND

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

Only required to be performed when the Power Range Neutron Flux input to QPTR is inoperable.

D.2.2 Perform SR 3.2.4.2.

OR D.3 Be in MODE 3.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 78 hours 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 78 hours North Anna Units 1 and 2 ACTTANS I

Amendments 231/212, 3.3.1-2

RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E.

One channel NOTE---------

inoperable.

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

E.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR E.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months F.

One Intermediate Range F.1 Reduce THERMAL POWER 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Neutron Flux channel to < P-6.

inoperable.

OR F.2 Increase THERMAL POWER 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to > P-1O.

G.

Two Intermediate Range ----------- NOTE---------

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

G.1 Suspend operations Immediately involving positive 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.

North Anna Units 1 and 2 Amendments 231/212, 3.3.1-3

RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME H.

One Source Range

NOTE---------

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

H.1 Suspend operations Immediately involving positive reactivity additions.

I.

Two Source Range 1.1 Open Reactor Trip Immediately Neutron Flux channels Breakers (RTBs).

inoperable.

J.

One Source Range J.1 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.

North Anna Units 1 and 2 Amendments 231/212, 3.3.1-4

RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME K.

Required Source Range ------------ NOTE---------

Neutron Flux channel Plant temperature changes are inoperable, allowed provided the temperature change is accounted for in the calculated SDM.

K.1 Suspend operations Immediately involving positive reactivity additions.

AND K.2 Perform SR 3.1.1.1.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter L.

One channel NOTE---------

inoperable.

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

L.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR L.2 Reduce THERMAL POWER 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months to < P-7.

North Anna Units 1 and 2 Amendments 231/212, 3.3.1-5

RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME M. One Reactor Coolant

NOTE---------

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

M.1 Restore channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

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

N.

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.

N.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR N.2 Reduce THERMAL POWER 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months to < P-8.

0. One train inoperable.

NOTE---------

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

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

OR 0.2 Be in MODE 3.

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months North Anna Units 1 and 2 Amendments 231/212, 3.3.1-6

RTS Instrumentation 3.3.1 CONDITION I

REQUIRED ACTION COMPLETION TIME P.

One RTB train inoperable.

NOTES---------

1. One train may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing, provided the other train is OPERABLE.

2. One RTB may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for maintenance on undervoltage or shunt trip mechanisms, provided the other train is OPERABLE.

3. One RTB train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for concurrent surveillance testing of the RTB and automatic trip logic, provided the other train is OPERABLE.

P.1 Restore train to OPERABLE status.

OR P.2 Be in MODE 3.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 7 hours Q.

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

OR Q.2 Be in MODE 3.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months North Anna Units 1 and 2 ACTIONS Amendments 231/212, 3.3.1-7

RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME R.

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

OR R.2 Be in MODE 2.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months S.

One trip mechanism S.1 Restore inoperable 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable for one trip mechanism to RTB.

OPERABLE status.

OR S.2 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2

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

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

Compare results of calorimetric heat 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months balance calculation to power range channel output. Adjust power range output if calorimetric heat balance calculation result exceeds power range channel output by more than +2% RTP.

North Anna Units 1 and 2 Amendments 231/212, 3.3.1-8

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.3

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

Not required to be performed until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after THERMAL POWER is A 15% RTP.

Compare results of the incore detector 31 effective measurements to Nuclear Instrumentation full power days System (NIS) AFD. Adjust NIS channel if (EFPD) absolute difference is A 3%.

SR 3.3.1.4

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

This Surveillance must be performed on the reactor trip bypass breaker immediately after placing the bypass breaker in service.

Perform TADOT.

31 days on a STAGGERED TEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST.

31 days on a STAGGERED TEST BASIS SR 3.3.1.6

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

Verification of setpoint is not required.

Perform TADOT.

92 days SR 3.3.1.7

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

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

Perform COT.

92 days North Anna Units 1 and 2 3.3.1-9 Amendments 231/212,

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVILLACE RQUIRMENT SURVEILLANCE t

SR 3.3.1.8

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

This Surveillance shall include verification that interlocks P-6 and P-1O are in their required state for existing unit conditions.

Perform COT.

SR 3.3.1.9 NOTES

1. Adjust NIS channel if absolute difference A 3%.

2. Not required to be performed until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after THERMAL POWER is A 50% RTP.

Compare results of the excore channels to incore detector measurements.

FREQUENCY NOTE ----

Only required when not performed wi thin previous 92 days Prior to reactor startup AND Four hours after reducing power below P-6 for source range instrumentation AND Twelve hours after reducing power below P-1O for power and intermediate range instrumentation AND Once per 92 days thereafter 92 EFPD North Anna Units 1 and 2 i

Amendments 231/212, 3.3.1-10

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.10 ------------------- NOTE----------------

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

Perform CHANNEL CALIBRATION.

18 months SR 3.3.1.11 NOTE---------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

18 months SR 3.3.1.12 Perform CHANNEL CALIBRATION.

18 months SR 3.3.1.13 Perform COT.

18 months SR 3.3.1.14 -------------------NOTE ----------------

Verification of setpoint is not required.

Perform TADOT.

18 months SR 3.3.1.15 ------------------- NOTE----------------

Verification of setpoint is not required.

Perform TADOT.

Prior to exceeding the P-8 interlock whenever the unit has been in MODE 3, if not performed within the previous 31 days North Anna Units 1 and 2 Amendments 231/212, 3.3.1-11

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.16 -------------------NOTE ----------------

Neutron detectors are excluded from response time testing.

Verify RTS RESPONSE TIME is within limits.

18 months on a STAGGERED TEST BASIS North Anna Units 1 and 2 Amendments 231/212, 3.3.1-12

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 5)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

1. Manual Reactor Trip

2. Power Range Neutron Flux

a. High

b. Low 1, 2 3 (a).

4(a),

5(a) 1, 2 I(b), 2

3. Power Range Neutron Flux Rate

a. High Positive Rate

b. High Negative Rate

4. Intermediate Range Neutron Flux

5. Source Range Neutron Flux 1, 2

1. 2 1 (b),

2 (c) 2 (d) 3 (a),

4 (a),

5 (a) 3(e), 4(e). 5(e) 4 4

E SR 3.3.1.7 SR 3.3.1.11 E

SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16 2

F, G SR SR SR 2

H, I SR SR SR SR 2

I,. J SR SR SR SR 1

K SR SR 3.3.1.1 3.3.1.8 3.3.1.11 3.3.1.1 3.3.1.8 3.3.1.11 3.3.1.16 3.3.1.1 3.3.1.7 3.3.1.11 3.3.1.16 3.3.1.1 3.3.1.11 (a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

Below the P-10 (Power Range Neutron Flux) interlocks.

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

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

With the Rod Control System incapable of rod withdrawal.

In not provide reactor trip but does provide indication.

this condition, source range Function does North Anna Units 1 and 2 B

C SR SR 2

2 4

4 3.3.1.14 3.3.1.14 3.3.1.1 3.3.1.2 3.3.1.3 3.3.1.7 3.3.1.11 3.3.1.16 3.3.1.1 3.3.1.8 3.3.1.11 3.3.1.16 NA NA

_< 110% RTP 5; 26% RTP D

SR SR SR SR SR SR E

SR SR SR SR

5.5% RTP with time constant

Ž 2 sec 5 5.5% RTP with time constant

Ž 2 sec 5 40% RTP 5 1.3 E5 cps

1.3 E5 cps NA (b)

(c)

(d)

(e)

Amendments 231/212, 3.3.1-13

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 5)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

6. Overtemperature AT

7. Overpower AT 1, 2 1, 2 3

3

8. Pressurizer Pressure

a. Low

b. High

9. Pressurizer Water Level-High

10. Reactor Coolant Flow-Low

11. Reactor Coolant Pump (RCP)

Breaker Position

12. Undervoltage RCPs

13. Underfrequency RCPs

14. Steam Generator (SG) Water Level-Low Low 1(f)

1.

1 (f) 1, 2 3

3 3

3 per loop 1 per RCP 1 per bus 1 per bus 3 per SG E

SR SR SR SR SR SR E

SR SR SR L

SR SR SR SR E

SR SR SR SR L

SR SR SR SR 3.3.1.1 3.3.1.3 3.3.1.7 3.3.1.9 3.3.1.12 3.3.1.16 3.3.1.1 3.3.1.7 3.3.1.12 3.3.1.1 3.3.1.7 3.3.1.10 3.3.1.16 3.3.1.1 3.3.1.7 3.3.1.10 3.3.1.16 3.3.1.1 3.3.1.7 3.3.1.10 3.3.1.16 3.3.1.1 3.3.1.7 3.3.1.10 3.3.1.16 M

SR 3.3.1.14 L

SR SR SR L

SR SR SR E

SR SR SR SR 3.3.1.6 3.3.1.10 3.3.1.16 3.3.1.6(g) 3.3.1.10 3.3.1.16 3.3.1.1 3.3.1.7 3.3.1.10 3.3.1.16 (f)

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

(g)

Required to be performed for Unit 2 only.

North Anna Units 1 and 2 Refer to Note I (Page 3.3.1-16)

Refer to Note 2 (Page 3.3.1-17)

Ž 1860 psig

! 2370 psig

93%

Ž 89%

NA

_> 2870 V

>- 56 Hz

> 17%

Amendments 231/212, 3.3.1-14

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 5)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

15. SG Water Level-Low Coincident with Steam Flow/Feedwater Flow Mismatch

16. Turbine Trip

a. Low Auto Stop Oil Pressure

b. Turbine Stop Valve Closure

17. Safety Injection (SI) Input from Engineered Safety Feature Actuation System (ESFAS)

18. Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, P-6

b.

Low Power Reactor Trips Block, P-7

c. Power Range Neutron Flux, P-8

d. Power Range Neutron Flux, P-10

e. Turbine Impulse Pressure, P-13

19. Reactor Trip Breakers(i)

20. Reactor Trip Breaker Undervoltage and Shunt Trip Mechanisms

21. Automatic Trip Logic 1, 2 1, 2 1 (h) 1 (h) 1, 2 2(d) 1 1, 2 1

1, 2 3(a), 4(a), 5 (a) 1, 2 3(a), 4(a), 5(a) 1, 2 3(a), 4(a), 5(a) 2 per SG 2 per SG 3

4 2 trains 2

1 per train 4

4 2

2 trains 2 trains 1 each per RTB 1 each per RTB 2 trains 2 trains E

SR SR SR E

SR SR SR N

SR SR N

SR SR 0

SR Q

SR SR R

SR R

SR SR Q

SR SR R

SR SR P

SR C

SR S

SR 3.3.1.1 3.3.1.7 3.3.1.10 3.3.1.1 3.3.1.7 3.3.1.10 3.3.1.10 3.3.1.15 3.3.1.10 3.3.1.15 3.3.1.14 3.3.1.11 3.3.1.13 3.3.1.5 3.3.1.11 3.3.1.13 3.3.1.11 3.3.1.13 3.3.1.10 3.3.1.13 3.3.1.4 3.3.1.4 3.3.1.4

Ž 24%

42.5% full steam flow at RTP S40 psig a 0% open NA

Ž 3E-11 amp NA

31% RTP

Ž 7% RTP 5 11% RTP

11% turbine power NA NA NA C

SR 3.3.1.4 NA 0

C SR SR 3.3.1.5 3.3.1.5 NA NA With Rod Control System capable of rod withdrawal or one or more Below the P-6 (Intermediate Range Neutron Flux) interlocks.

Above the P-8 (Power Range Neutron Flux) interlock.

rods not fully inserted.

(i)

Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

North Anna Units 1 and 2 (a)

(d)

(h)

Amendments 231/212, 3.3.1-15

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 5)

Reactor Trip System Instrumentation Note 1: Overtemperature AT The Overtemperature AT Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2.0% of AT span.

AT_- ATo K,-

K2( G+ r2s) T-T'] + K3(P - P') - f 1(AI)1 Where:

AT is measured RCS AT, OF.

ATo is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec-.

T is the measured RCS average temperature, OF.

T' is the nominal Tavg at RTP,

[*]OF.

P is the measured pressurizer pressure, psig P'

is the nominal RCS operating pressure,

_Ž

[*] psig K, < [*]

ŽI

> [*] sec K2 _ [*]/OF r2 - [*] sec f 1(AI)

= [*]{[*]% -

(qt -

qb)}

0% of RTP

[*]{(qt - qb)

- [*3}

Where qt and qb are percent RTP in of the core, respectively, and qt POWER in percent RTP.

K3 >_ [*]/psig when qt -qb

< [*]% RTP when [*]% RTP _ qt - qb - [*]% RTP when qt -qb

> [*]% RTP the upper and lower halves

+ qb is the total THERMAL The values denoted with [*] are specified in the COLR.

North Anna Units 1 and 2 Amendments 231/212, 3.3.1-16

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 5)

Reactor Trip System Instrumentation Note 2: Overpower AT The Overpower AT Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of AT span.

AT*<ATO{K 4 -K5[1 3 s] T-K6[TL-JT ] -f2(AI)

Where:

AT is measured RCS AT, °F.

ATo is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, IF.

T' is the nominal Tavg at RTP,

[*]OF.

K4 -< [*]

K5 _ [*]/OF for increasing Tavg K6 _ [*]/IF when T > T'

[*]/OF for decreasing Tavg

[*]/OF when T *__ T' r3 < [*] sec f 2 (AI)

= [*]

The values denoted with [*] are specified in the COLR.

North Anna Units 1 and 2 Amendments 231/212, 3.3.1-17

Intentionally Blank

ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO

3.3.2 APPLICABILITY

The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

According to Table 3.3.2-1.

ACTIONS NOTE Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

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

B.

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

OR B.2.1 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND B.2.2 Be in MODE 5.

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months North Anna Units 1 and 2 Amendments 231/212, 3.3.2-1

ESFAS Instrumentation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

One train inoperable.

C.1

NOTE --------

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

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

OR C.2.1 Be in MODE 3.

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months AND C.2.2 Be in MODE 5.

60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months D.

One channel D.1

NOTE --------

inoperable.

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

Place channel in trip.

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

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months North Anna Units 1 and 2 Amendments 231/212, 3.3.2-2

ESFAS Instrumentation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E.

One Containment E.1

NOTE------

Pressure channel One additional channel inoperable.

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 bypass.

OR E.2.1 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND E.2.2 Be in MODE 4.

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months F.

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

OR F.2.1 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND F.2.2 Be in MODE 4.

60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months North Anna Units 1 and 2 Amendments 231/212, 3.3.2-3

ESFAS Instrumentation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G.

One train inoperable.

G.1

NOTE------

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

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

OR G.2.1 Be in MODE 3.

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months AND G.2.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months H.

One Main Feedwater H.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Pumps trip channel OPERABLE status.

inoperable.

OR H.2 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months I.

One channel 1.1

NOTE------

inoperable.

One additional 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 bypass.

OR 1.2.1 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND 1.2.2 Be in MODE 5.

108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months North Anna Units 1 and 2 3.3.2-4 Amendments 231/212,

ESFAS Instrumentation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME J.

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

OR J.2.1 Be in MODE 3.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND J.2.2 Be in MODE 4.

13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months SURVEILLANCE REQUIREMENTS NOTE--------------------

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

SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.2.2 Perform ACTUATION LOGIC TEST.

31 days on a STAGGERED TEST BASIS SR 3.3.2.3 Perform MASTER RELAY TEST.

31 days on a STAGGERED TEST BASIS SR 3.3.2.4 Perform COT 92 days North Anna Units 1 and 2 Amendments 231/212, 3.3.2-5

ESFAS Instrumentation 3.3.2 SURVEILLANCE FREQUENCY SR 3.3.2.5 NOTE---------------

Not required to be performed for SLAVE RELAYS if testing would:

1. Result in an inadvertent Reactor Trip System or ESFAS Actuation if accompanied by a single failure in the Safeguard Test Cabinet;

2. Adversely affect two or more components in one or more ESFAS system(s); or

3. Create a reactivity, thermal, or hydraulic transient condition in the Reactor Coolant System.

Perform SLAVE RELAY TEST.

92 days SR 3.3.2.6 NOTE---------------

Verification of relay setpoints not required.

Perform TADOT.

92 days SR 3.3.2.7

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

Verification of setpoint not required for manual initiation functions.

Perform TADOT.

18 months SR 3.3.2.8 NOTE---------------

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

Perform CHANNEL CALIBRATION.

18 months North Anna Units 1 and 2 Amendments 231/212, 3.3.2-6

ESFAS Instrumentation 3.3.2 SURVEILLANCE FREQUENCY SR 3.3.2.9

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

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after SG pressure is Ž 1005 psig.

Verify ESFAS RESPONSE TIMES are within 18 months on a limit.

STAGGERED TEST BASIS SR 3.3.2.10 ----------------- NOTE---------------

Verification of setpoint not required.

Perform TADOT.

Once per reactor trip breaker cycle North Anna Units 1 and 2 Amendments 231/212, 3.3.2-7

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 1 of 4)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE NODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

1. Safety Injection

a. Manual Initiation 1, 2, 3, 4 2

B SR 3.3.2.7 NA

b. Automatic Actuation Logic 1, 2, 3, 4 2 trains C

SR 3.3.2.2 NA and Actuation Relays SR 3.3.2.3 SR 3.3.2.5

c. Containment Pressure-High 1, 2. 3 3

D SR 3.3.2.1

_ 17.7 psia SR 3.3.2.4 SR 3.3.2.8 SR 3.3.2.9

d. Pressurizer Pressure-Low-Low

1. 2, 3(a)

D SR 3.3.2.1 2! 1770 psig SR 3.3.2.4 SR 3.3.2.8 SR 3.3.2.9

e. High Differential Pressure 1, 2, 3 3 per steam D

SR 3.3.2.1

5 112 psid Between Steam Lines line SR 3.3.2.4 SR 3.3.2.8 SR 3.3.2.9

f. High Steam Flow in Two Steam 1, 2, 3 (b) 2 per steam D

SR 3.3.2.1 (c)

Lines line SR 3.3.2.4 SR 3.3.2.8 SR 3.3.2.9 Coincident with 1, 2, 3(b) 1 per loop D

SR 3.3.2.1

- 542*F Tavg-Low Low SR 3.3.2.4 SR 3.3.2.8 SR 3.3.2.9

g. High Steam Flow in Two Steam 1, 2, 3 (b) 2 per steam D

SR 3.3.2.1 (c)

Lines line SR 3.3.2.4 SR 3.3.2.8 SR 3.3.2.9 Coincident with Steam Line 1, 2, 3(b) 1 per steam D

SR 3.3.2.1

_ 585 psig Pressure-Low line SR 3.3.2.4 SR 3.3.2.8 SR 3.3.2.9 (a) Above the P-11 (Pressurizer Pressure) interlock.

(b)

Above the P-12 (Tavg--ow Low) interlock.

(c)

Less than or equal to a function defined as AP corresponding to 42% full steam flow below 20% load, and AP increasing linearly from 42% full steam flow at 20% load to 111% full steam flow at 100%- load, and AP corresponding to 111% full steam flow above 100% load.

North Anna Units 1 and 2 Amendments 231/212, 3.3.2-8

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page Engineered Safety Feature Actuation 2 of 4)

System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

2. Containment Spray

a. Manual Initiation

b. Automatic Actuation Logic and Actuation Relays

c. Containment Pressure High High

3. Containment Isolation

a. Phase A Isolation (1) Manual Initiation (2) Automatic Actuation Logic and Actuation Relays (3) Safety Injection

b. Phase B Isolation (1) Manual Initiation (2) Automatic Actuation Logic and Actuation Relays (3) Containment Pressure High High 1, 2, 3. 4 1, 2, 3, 4 1, 2, 3 1, 2, 3, 4 1, 2, 3, 4 Refer to Function requirements.

2 per train, 2 trains 2 trains 4

2 2 trains B

C SR SR SR SR E

SR SR

- SR SR B

C 1 (Safety Injection) for SR SR SR SR al I 3.3.2.7 3.3.2.2 3.3.2.3 3.3.2.5 3.3.2.1 3.3.2.4 3.3.2.8 3.3.2.9 3.3.2.7 3.3.2.2 3.3.2.3 3.3.2.5 initiation NA NA

5 28.45 psia NA NA functions and Refer to Function 2.a (Containment Spray-Manual Initiation) for all functions and requirements.

1, 2, 3, 4 2 trains C

SR 3.3.2.2 NA SR 3.3.2.3 SR 3.3.2.5 Refer to Function 2.c (Containment Spray-Containment Pressure High High) for all functions and requirements.

North Anna Units 1 and 2 Amendments 231/212, 3.3.2-9

ESFAS Instrumentation 3.3.2 Engineered Safe Table 3.3.2-1 (page 3 of 4) tv Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

4. Steam Line Isolation

a. Manual Initiation 1, 2 (d),

3 (d) 2 per steam line F

SR 3.3.2.7

b. Automatic Actuation Logic and Actuation Relays

c. Containment Pressure Intermediate High High

d. High Steam Flow in Two Steam Lines Coincident with Tavg-Low Low

e. High Steam Flow in Two Steam Lines Coincident with Steam Line Pressure-Low

5. Turbine Trip and Feedwater Isolation

a. Automatic Actuation Logic and Actuation Relays

b.

SG Water Level-High High (P-14) 1, 2 (d),

3 (d) 2 trains 1, 2 (d),

3 (d) 3 1, 2 (d),

3 (d) 2 per steam line 1,

2 (d),

3 (b)(d) 1 per loop 1, 2 (d),

3 (d) 2 per steam line 1, 2,(d) 3 (d) 1 per steam line 1, 2(e),

3 (e) 2 trains 1, 2 (e),

3 (e) 3 per SG G

SR SR SR D

SR SR SR SR D

SR SR SR SR 3.3.2.2 3.3.2.3 3.3.2.5 3.3.2.1 3.3.2.4 3.3.2.8 3.3.2.9 3.3.2.1 3.3.2.4 3.3.2.8 3.3.2.9 3.3.2.1 3.3.2.4 3.3.2.8 3.3.2.9 3.3.2.1 3.3.2.4 3.3.2.8 3.3.2.9 3.3.2.1 3.3.2.4 3.3.2.8 3.3.2.9 G

SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.5 D

SR SR SR SR 3.3.2.1 3.3.2.4 3.3.2.8 3.3.2.9

c. Safety Injection Refer to Function 1 (Safety Injection) requirements.

for all initiation functions and (b)

Above the P-12 (Tavg-Low Low) interlock.

(c)

Less than or equal to a function defined as AP corresponding to 42% full steam flow below 20% load, and AP increasing linearly from 42% full steam flow at 20% load to 111% full steam flow at 100% load, and AP corresponding to 111% full steam flow above 100% load.

(d)

Except when all MSTVs are closed and de-activated.

(e) Except when all Main Feedwater Pump Discharge Valves or all MFIVs, MFRVs, and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

North Anna Units 1 and 2 NA NA f-18.5 psia (c)

_> 542°F (c)

_ 585 psig NA

!- 76%

v Amendments 231/212, 3.3.2-10

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 4)

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

6. Auxiliary Feedwater

a. Automatic Actuation Logic 1, 2. 3 2 trains G

SR 3.3.2.2 NA and Actuation Relays SR 3.3.2.3 SR 3.3.2.5

b. SG Water Level-Low Low 1, 2. 3 3 per SG D

SR 3.3.2.1

_ 17%

SR 3.3.2.4 SR 3.3.2.8 SR 3.3.2.9

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

d. Loss of Offsite Power 1, 2, 3 1 per bus, F

SR 3.3.2.6

Ž2184 V 2 buses SR 3.3.2.8 SR 3.3.2.9

e. Trip of all Main Feedwater 1, 2 2 per pump H

SR 3.3.2.7 NA Pumps SR 3.3.2.9

7. Automatic Switchover to Contai nment Sump

a. Automatic Actuation Logic 1, 2. 3, 4 2 trains C

SR 3.3.2.2 NA and Actuation Relays SR 3.3.2.3 SR 3.3.2.5

b. Refueling Water Storage Tank 1, 2, 3, 4 4

1 SR 3.3.2.1

_ 18.4% and (RWST) Level-Low Low SR 3.3.2.4

_< 20.4%

SR 3.3.2.8 SR 3.3.2.9 Coincident with Safety Refer to Function 1 (Safety Injection) for all initiation functions and Injection requirements.

8. ESFAS Interlocks

a. Reactor Trip, P-4 1, 2. 3 1 per train, F

SR 3.3.2.10 NA 2 trains

b. Pressurizer Pressure, P-11 1, 2, 3 3

J SR 3.3.2.1

_ 2010 psig SR 3.3.2.8

c. Tavg-Low Low, P-12 1, 2, 3 1 per loop J

SR 3.3.2.1

_> 542°F and SR 3.3.2.8

< 545*F North Anna Units 1 and 2 Amendments 231/212, 3.3.2-11

Intentionally Blank

PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM)

Instrumentation LCO

3.3.3 APPLICABILITY

The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

MODES 1, 2, and 3.

NOTE Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Functions A.1 Restore required 30 days with one required channel to OPERABLE channel inoperable, status.

B.

Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.6.

not met.

C.

One or more Functions C.1 Restore one channel to 7 days with two required OPERABLE status.

channels inoperable.

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 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months North Anna Units 1 and 2 ACTIONS Amendments 231/212, 3.3.3-1

PAM Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS NOTE ----------------

SR 3.3.3.1 and SR 3.3.3.3 apply to each PAM instrumentation Function in Table 3.3.3-1 except SR 3.3.3.3 does not apply to Items 10 and 12. SR 3.3.3.2 applies only to Item 12. SR 3.3.3.4 applies only to Item 10.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.3.2 Perform CHANNEL CALIBRATION.

92 days SR 3.3.3.3 NOTE Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

18 months SR 3.3.3.4 Perform TADOT.

18 months North Anna Units 1 and 2 Amendments 231/212, 3.3.3-2

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 1)

Post Accident Monitoring Instrumentation FUNCTION REQUIRED CHANNELS

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

Power Range Neutron Flux Source Range Neutron Flux Reactor Coolant System (RCS) Hot Leg Temperature (Wide Range)

RCS Cold Leg Temperature (Wide Range)

RCS Pressure (Wide Range)

Inadequate Core Cooling Monitoring (ICCM) System 6.a. Reactor Vessel Level Instrumentation System (RVLIS) 6.b. RCS Subcooling Margin Monitor 6.c.1 Core Exit Temperature-Quadrant 1 6.c.2 Core Exit Temperature-Quadrant 2 6.c.3 Core Exit Temperature-Quadrant 3 6.c.4 Core Exit Temperature-Quadrant 4 Containment Sump Water Level (Wide Range)

Containment Pressure Containment Pressure (Wide Range)

Penetration Flow Path Containment Isolation Valve Position Containment Area Radiation (High Range)

Containment Hydrogen Analyzers Pressurizer Level Steam Generator (SG) Water Level (Wide Range)

SG Water Level (Narrow Range)

Emergency Condensate Storage Tank Level SG Pressure High Head Safety Injection Flow (a)

Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b)

Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) A channel consists of two core exit thermocouples (CETs).

North Anna Units 1 and 2 2

2 2

2(c) 2 (c) 2(c) 2 (c) 2 2

2 2 per penetration flow path(a)(b) 2 2

2 2

2 per SG 2

Amendments 231/212, 3.3.3-3

Intentionally Blank

Remote Shutdown 3.3 INSTRUMENTATION 3.3.4 Remote Shutdown System LCO 3.3.4 APPLICABILITY:

The Remote Shutdown System Functions shall be OPERABLE.

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 30 days Functions inoperable.

Function 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 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.4.2 Verify each required control circuit and 18 months transfer switch is capable of performing the intended function.

North Anna Units 1 and 2 System 3.3.4 Amendments 231/212, 3.3.4-1

Remote Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.3 Perform CHANNEL CALIBRATION for each 18 months required instrumentation channel.

North Anna Units 1 and 2 Amendments 231/212, 3.3.4-2

LOP EDG Start Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Loss of Power (LOP)

Emergency Diesel Generator (EDG)

Start Instrumentation LCO

3.3.5 APPLICABILITY

Three channels per bus of the loss of voltage Function and three channels per bus of the degraded voltage Function for the following 4160 VAC buses shall be OPERABLE:

a. The Train H and Train J buses; and

b. One bus on the other unit for each required shared component.

MODES 1, 2, 3, and 4, When associated EDG is required to be OPERABLE by LCO 3.8.2, "AC Sources-Shutdown."

ACTIONS

- NOTE Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Functions A.1 NOTE --------

with one channel per The inoperable channel bus inoperable.

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.

Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.

One or more Functions B.1 Restore all but one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with two or more channel to OPERABLE channels per bus status.

inoperable.

North Anna Units 1 and 2 Amendments 231/212, 3.3.5-1

LOP EDG Start Instrumentation 3.3.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Enter applicable Immediately associated Completion Condition(s) and Time not met.

Required Action(s) for the associated EDG made inoperable by LOP EDG start instrumentation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1

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

Verification of setpoint is not required.

Perform TADOT for LCO 3.3.5.a and 92 days LCO 3.3.5.b Functions.

SR 3.3.5.2 Perform CHANNEL CALIBRATION with Allowable 18 months Values as follows:

a. Loss of voltage Allowable ValuesŽ 2935 V and

3225 V with a time delay of 2 +/-1 seconds for LCO 3.3.5.a and LCO 3.3.5.b Functions.

b. Degraded voltage Allowable Values

> 3720 V and

3772 V with:

1. A time delay of 7.5 +/-1.5 seconds with a Safety Injection (SI) signal for LCO 3.3.5.a Function; and

2. A time delay of 56 +/-7 seconds without an SI signal for LCO 3.3.5.a and LCO 3.3.5.b Functions.

SR 3.3.5.3 Verify ESF RESPONSE TIMES are within limit 18 months on a for LCO 3.3.5.a and LCO 3.3.5.b Functions.

STAGGERED TEST BASIS North Anna Units 1 and 2 Amendments 231/212, 3.3.5-2

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits LCO 3.4.1 APPLICABILITY:

RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

a. Pressurizer pressure is greater than or equal to the limit specified in the COLR;

b. RCS average temperature is less than or equal to the limit specified in the COLR; and

c. RCS total flow rate : 295,000 gpm and is greater than or equal to the limit specified in the COLR.

MODE 1.

NOTE-Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5% RTP per minute; or

b. THERMAL POWER step > 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A..One or more RCS DNB A.1 Restore RCS DNB 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months parameters not within parameter(s) to within

limits, limit.

B.

Required Action and B.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

North Anna Units 1 and 2 Amendments 231/212, 3.4.1-1

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is greater than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or equal to the limit specified in the COLR.

SR 3.4.1.2 Verify RCS average temperature is less than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or equal to the limit specified in the COLR.

SR 3.4.1.3 Verify RCS total flow rate is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2 295,000 gpm and is greater than or equal to the limit specified in the COLR.

SR 3.4.1.4

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

Not required to be performed until 30 days after Ž 90% RTP.

Verify by precision heat balance that RCS 18 months total flow rate is Ž 295,000 gpm and is greater than or equal to the limit specified in the COLR.

North Anna Units 1 and 2 Amendments 231/212, 3.4.1-2

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 Ž 541F.

APPLICABILITY:

MODE 1, MODE 2 with keff Ž_ 1.0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Tav in one or more A.1 Be in MODE 2 with 30 minutes RCloops not within keff < 1.0.

limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each loop Ž 541F.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months North Anna Units 1 and 2 Amendments 231/212, 3.4.2-1

Intentionally Blank

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO

3.4.3 APPLICABILITY

RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in Figures 3.4.3-1 and 3.4.3-2 (Unit 1) and Figures 3.4.3-3 and 3.4.3-4 (Unit 2) with:

a. A maximum heatup of 60°F in any one hour period;

b. A maximum cooldown of 100OF in any one hour period; and

c. A maximum temperature change of 10OF in any one hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE--------- A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.

shall be completed whenever this AND Condition is entered.

A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for Requirements of LCO continued operation.

not met in MODE 1, 2, 3, or 4.

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 with RCS 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months pressure < 500 psig.

North Anna Units 1 and 2 Amendments 231/212, 3.4.3-1

RCS P/T Limits 3.4.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. --------- NOTE --------- C.1 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 in continued operation.

other than 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 30 minutes RCS heatup and cooldown rates are within limits.

North Anna Units 1 and 2 Amendments 231/212, 3.4.3-2

RCS P/T Limits 3.4.3 Material Property Basis Limiting Material: Circumferential Weld Seam Limiting ART at 32.3 EFPY: 1/4-T, 218.5 Deg. F 3/4-T, 195.6 Deg. F

-- *,i-i_* *

-Lee*-Limitt!

2000.00 2500.00 1 i A/

.0 11111__

SM...

Unacceptable 100 Operation 1000.00 I IT Acceptable

)

Hemt~up Rates-------___

-(Fhr)

Operation,

-+

so

-117 1 1 1 1 I I 1

500.00--

0.00..

0 50 100 150 200 250 300 350 Wide Range Cold Leg Temperature (Deg. F)

Figure 3.4.3-1 (page 1 of 1)

Unit 1 RCS Heatup Limitations Heatup Rates up to 60°F/hr, Applicable for the first 32.3 EFPY, Including Margins for Instrumentation Errors North Anna Units 1 and 2 Amendments 231/212, 3.4.3-3

RCS P/T Limits 3.4.3 Material Property Basis Limiting Material: Circumferential Weld Seam Limiting ART at 32.3 EFPY: 1/4-T, 218.5 Deg. F 3/4-T, 195.6 Deg. F 2500.00 1 H I NI K

I r

0_

11 Opeaton I

I-1

=-

Unacceptable _ceta2 SOperation O

io I

-__I K K-j11 4 i/*i Acceptable (Fo~dor)*

1 Operation (Flhr) 500.00 20 100

[

_ I___

__~

~:

~

1~t 4-4-4 0

50 100 150 200 250 300 350 Wide Range Cold Leg Temperature (Deg. F)

Figure 3.4.3-2 (page 1 of 1)

Unit 1 RCS Cooldown Limitations Cooldown Rates up to 1000F/hr, Applicable for the first 32.3 EFPY, Including Margins for Instrumentation Errors North Anna Units 1 and 2 Amendments 231/212, 3.4.3-4

RCS P/T Limits 3.4.3 Material Property Basis Limiting Material: Lower Shell Plate Limiting ART at 34.3 EFPY: 1/4-T, 218.5 Deg. F 314-T, 195.6 Deg. F 2500.00-~

'I ILeak!

Test 2000.00e I

iI s

S1500.00

.J Unac'ceptable

""0_

Operation I

/I o

1I

/Y I

o=1000.00-*

Iiii--T-- z i

Acceptabe

("thr"p )

,_1Operation 20 I

40 500.00 -

,I 0.00 :::4pt

H I

I 0.0 Ti" 1

0 50 100 150 200 250 300 350 Wide Range Cold Leg Temperature (Deg. F)

Figure 3.4.3-3 (page 1 of 1)

Unit 2 RCS Heatup Limitations Heatup Rates up to 60°F/hr, Applicable for the first 34.3 EFPY, Including Margins for Instrumentation Errors North Anna Units 1 and 2 3.4.3-5 Amendments 231/212,

RCS P/T Limits 3.4.3 Material Property Basis Limiting Material: Lower Shell Plate Limiting ART at 34.3 EFPY: 1/4-T, 218.5 Deg. F 3/4-T, 195.6 Deg. F S -

U S S -

S -

5 -

S -

5 5***

F -

F * * -

2500.00 2000.00

0.

0 0 1500.00 0

50.0 00 a.,

-i o* 1000.00 500.00 0.00 50 100 150 200 250 300 350 Wide Range Cold Leg Temperature (Deg. F)

Figure 3.4.3-4 (page 1 of 1)

Unit 2 RCS Cooldown Limitations Cooldown Rates up to 1000F/hr, Applicable for the first 34.3 EFPY, Including Margins for Instrumentation Errors North Anna Units 1 and 2 1

I I

Iiiii

'1 M

1I I ll Ili TTl HH WH 1V TT I/ 1 1H K

1-1 Z

I I

Th Unacceptable i

Operation S-K-

Acceptable Cooldown Rates

-Operation c1

-0I0 40I II N

0 Amendments 231/212, 3.4.3-6

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 APPLICABILITY

Three RCS loops shall be OPERABLE and in operation.

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of LCO A.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months North Anna Units 1 and 2 Amendments 231/212, 3.4.4-1

Intentionally Blank

RCS Loops-MODE 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops-MODE 3 LCO 3.4.5 APPLICABILITY:

Two RCS loops shall be OPERABLE, and one RCS loop shall be in operation.

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

All reactor coolant pumps may be removed from operation for

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 10OF below saturation temperature.

MODE 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One required RCS loop A.1 Restore required RCS 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable, loop to OPERABLE status.

B.

Required Action and B.1 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 A not met.

North Anna Units 1 and 2 Amendments 231/212, 3.4.5-1

RCS Loops-MODE 3 3.4.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

Two required RCS loops C.1 Place the Rod Control Immediately inoperable.

System in a condition incapable of rod OR withdrawal.

Required RCS loop not AND in operation.

C.2 Suspend operations Immediately that would cause introduction into the RCS, coolant with boron concentration less than required to meet SDM of LCO 3.1.1.

AND C.3 Initiate action to Immediately restore one RCS loop to OPERABLE status and operation.

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

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.5.2 Verify steam generator secondary side water 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months levels are Ž 17% for required RCS loops.

SR 3.4.5.3

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

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and 7 days indicated power are available to the required pump not in operation.

North Anna Units 1 and 2 Amendments 231/212, 3.4.5-2

RCS Loops-MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops-MODE 4 LCO 3.4.6 Two loops consisting of any residual heat removal (RHR) loop shall be in operation.

combination loops shall of RCS loops and be OPERABLE, and one NOTE-

1. All reactor coolant pumps (RCPs) and RHR pumps may be removed from operation for _*

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 10OF below saturation temperature.

2.

No RCP shall be started with any RCS cold leg temperature 235 0F (Unit 1),

270°F (Unit 2) unless the secondary side water temperature of each steam generator (SG) is

_5 50°F above each of the RCS cold leg temperatures.

APPLICABILITY:

MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One required loop A.1 Initiate action to Immediately inoperable, restore a second loop to OPERABLE status.

AND A.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 North Anna Units 1 and 2 Amendments 231/212, 3.4.6-1

RCS Loops-MODE 4 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

Two required loops B.1 Suspend operations Immediately inoperable, that would cause introduction into the OR RCS, coolant with boron concentration Required loop not in less than required to operation.

meet SDM of LCO 3.1.1.

AND B.2 Initiate action to Immediately restore one loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify required RHR or RCS loop is in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operation.

SR 3.4.6.2 Verify SG secondary side water levels are 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Ž 17% for required RCS loops.

SR 3.4.6.3

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

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and 7 days indicated power are available to the required pump not in operation.

North Anna Units 1 and 2 Amendments 231/212, 3.4.6-2

RCS Loops-MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops-MODE 5, Loops Filled LCO 3.4.7 One residual heat removal (RHR) loop shall be OPERABLE and in operation, and either:

a. One additional RHR loop shall be OPERABLE; or

b. The secondary side water level of one steam generator (SG) shall be Ž 17%.

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

1. The RHR pump of the loop in operation may be removed from operation for

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 10OF below saturation temperature.

2. One required RHR loop may be inoperable for up to 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.

3. No reactor coolant pump shall be started with one or more RCS cold leg temperatures

235°F (Unit 1), 270°F (Unit

2) unless the secondary side water temperature of each SG is

50°F above each of the RCS cold leg temperatures.

4. All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY:

MODE 5 with RCS loops filled.

North Anna Units 1 and 2 Amendments 231/212, 3.4.7-1

RCS Loops-MODE 5, Loops Filled 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One required RHR loop A.1 Initiate action to Immediately inoperable, restore a second RHR loop to OPERABLE AND status.

One RHR loop OPERABLE.

OR A.2 Initiate action to Immediately restore required SG secondary side water level to within limits.

B.

Required SG with B.1 Initiate action to Immediately secondary side water restore a second RHR level not within loop to OPERABLE limits.

status.

AND OR One RHR loop OPERABLE.

B.2 Initiate action to Immediately restore required SG secondary side water level to within limits.

C.

No required RHR loops C.1 Suspend operations Immediately OPERABLE.

that would cause introduction into the OR RCS, coolant with boron concentration Required RHR loop not less than required to in operation.

meet SDM of LCO 3.1.1.

AND C.2 Initiate action to Immediately restore one RHR loop to OPERABLE status and operation.

North Anna Units 1 and 2 Amendments 231/212, 3.4.7-2

RCS Loops-MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required RHR loop is in operation.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.7.2 Verify SG secondary side water level is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

> 17% in required SG.

SR 3.4.7.3

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

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and 7 days indicated power are available to the required RHR pump not in operation.

North Anna Units 1 and 2 Amendments 231/212, 3.4.7-3

Intentionally Blank

RCS Loops-MODE 5, Loops Not 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops-MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.

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

1. All RHR pumps may be removed from operation for

15 minutes when switching from one loop to another provided:

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

b. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet SDM of LCO 3.1.1; and

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

2. One RHR loop surveillance OPERABLE and APPLICABILITY:

may be inoperable for

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for testing provided that the other RHR loop is in operation.

MODE 5 with RCS loops not filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One required RHR loop A.1 Initiate action to Immediately inoperable, restore RHR loop to OPERABLE status.

North Anna Units 1 and 2 Filled 3.4.8 Amendments 231/212, 3.4.8-1

RCS Loops-MODE 5, Loops Not Filled 3.4.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

No required RHR loop B.1 Suspend operations Immediately OPERABLE.

that would cause introduction into the OR RCS, coolant with boron concentrati on Required RHR loop not less than required to in operation.

meet SDM of LCO 3.1.1.

AND B.2 Initiate action to Immediately restore one RHR loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify required RHR loop is in operation.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.8.2

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

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and 7 days indicated power are available to the required RHR pump not in operation.

North Anna Units 1 and 2 Amendments 231/212, 3.4.8-2

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

a. Pressurizer water level

93%; and

b. Two groups of pressurizer heaters OPERABLE with the capacity of each group Ž 125 kW and capable of being powered from an emergency bus.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Pressurizer water A.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months level 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 MODE 4.

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

One required group of B.1 Restore required group 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pressurizer heaters of pressurizer heaters inoperable, to OPERABLE status.

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 North Anna Units 1 and 2 Amendments 231/212, 3.4.9-1

Pressurizer 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is

93%.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.9.2 Verify capacity of each required group of 18 months pressurizer heaters is Ž 125 kW.

North Anna Units 1 and 2 Amendments 231/212, 3.4.9-2

Pressurizer Safety 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 APPLICABILITY:

Three pressurizer safety valves shall be OPERABLE with lift settings of 2485 psig, +2%/-3% average with no single valve outside +/-3%.

MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures > 2357F (Unit 1),

270°F (Unit 2).

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

The lift settings are not required to be within the LCO limits during MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions.

This exception is allowed for 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable.

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 OR B.2 Be in MODE 4 with any 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months RCS cold leg Two or more temperatures <

pressurizer safety 235 0F (Unit 1),

valves inoperable.

270°F (Unit 2).

North Anna Units 1 and 2 Valves 3.4.10 Amendments 231/212, 3.4.10-1

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 North Anna Units 1 and 2 Amendments 231/212, 3.4.10-2

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

LCO 3.4.11 APPLICABILITY:

Each PORV and associated block valve shall be OPERABLE.

MODES 1, 2, and 3.

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more PORVs A.1 Restore backup 14 days inoperable due to nitrogen supply to inoperable backup OPERABLE status.

nitrogen supply and capable of being manually cycled.

B.

One or more PORVs B.1 Close and maintain 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable for reason power to associated other than Condition A block valve.

and capable of being manually cycled.

C.

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

being manually cycled.

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

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

North Anna Units 1 and 2 Amendments 231/212, 3.4.11-1

Pressurizer PORVs 3.4.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. One block valve

NOTE--------

inoperable.

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

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

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

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 of Condition A, AND B, C, or D not met.

E.2 Be in MODE 4.

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

Two PORVs inoperable F.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and not capable of being manually cycled.

AND F.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months North Anna Units 1 and 2 Amendments 231/212, 3.4.11-2

Pressurizer PORVs 3.4.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G.

Two block valves G.1

NOTE------

inoperable.

Required Action G.1 does not apply when block valve is inoperable solely as a result of complying with Required Action C.2.

Restore one block 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months valve to OPERABLE status.

H.

Required Action and H.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 G AND not met.

H.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 3.4.11.1 Verify PORV backup nitrogen supply pressure 7 days is within limit.

SR -3.4.11.2 ----------------- NOTES--------------

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 block 92 days valve.

North Anna Units 1 and 2 Amendments 231/212, 3.4.11-3

Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.3 ------------------

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

Only required to be performed in MODES 1 and 2.

Perform a complete cycle of each PORV.

18 months SR 3.4.11.4 Perform a complete cycle of each solenoid 18 months control valve and check valve on the accumulators in PORV control systems.

North Anna Units 1 and 2 Amendments 231/212, 3.4.11-4

LTOP System 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP)

System LCO 3.4.12 An LTOP System shall be OPERABLE with a maximum of one charging pump and one low head safety injection (LHSI) pump capable of injecting into the RCS and the accumulators isolated, with power removed from the isolation valve operators, and one of the following pressure relief capabilities:

a. Two power operated relief valves (PORVs) with lift settings of:

1.

500 psig (Unit 1),

415 psig (Unit 2) when any RCS cold leg temperature *235 0F (Unit 1), 270°F (Unit 2); and

2.

395 psig (Unit 1),

375 psig leg temperature

150OF (Unit (Unit 2) when any RCS cold 1),

130OF (Unit 2).

b. The RCS depressurized and an RCS vent of Ž 2.07 square inches.

NOTES-

1. Two charging pumps may be made capable of injecting for

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for pump swapping operations.

2. Accumulator isolation with power removed from the isolation valve operators is only required when accumulator pressure is greater than the PORV lift setting.

APPLICABILITY:

MODE 4 when any RCS cold leg temperature is 270°F (Unit 2),

MODE 5, MODE 6 when the reactor vessel head is on.

2350F (Unit 1),

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Two LHSI pumps capable A.1 Initiate action to Immediately of injecting into the verify a maximum of RCS.

one LHSI pump is capable of injecting into the RCS.

North Anna Units 1 and 2 Amendments 231/212, 3.4.12-1

LTOP System 3.4.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

Two or more charging B.1 Initiate action to Immediately pumps capable of verify a maximum of injecting into the one charging pump is RCS.

capable of injecting into the RCS.

C. -------- NOTE --------- C.1 Isolate affected Immediately Only applicable when accumulator.

accumulator pressure is greater than PORV AND lift setting.

C.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months affected accumulator An accumulator not isolation valve isolated.

operators.

OR Power available to one or more accumulator isolation valve operators.

D.

Required Action and D.1 Increase RCS cold leg 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion temperature to > 2357F Time of Condition C (Unit 1),

270°F not met.

(Unit 2).

OR D.2 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months accumulator to less than PORV lift setting.

E.

One required PORV E.1 Restore required PORV 7 days inoperable in MODE 4.

to OPERABLE status.

F.

One required PORV F.1 Restore required PORV 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable in MODE 5 to OPERABLE status.

or 6.

North Anna Units 1 and 2 Amendments 231/212, 3.4.12-2

LTOP System 3.4.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G.

Two required PORVs G.1 Depressurize RCS and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable, establish RCS vent of

Ž2.07 square inches.

OR Required Action and associated Completion Time of Condition A, B, D, E, or F not met.

OR LTOP System inoperable for any reason other than Condition A, B, C, D, E, or F.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify a maximum of one LHSI pump is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months capable of injecting into the RCS.

SR 3.4.12.2 Verify a maximum of one charging pump is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months capable of injecting into the RCS.

SR 3.4.12.3 ----------------- NOTE---------------

Only required to be met if accumulator pressure is greater than PORV lift setting.

Verify each accumulator is isolated and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months power is removed from the accumulator isolation valve operator.

North Anna Units 1 and 2 3.4.12-3 Amendments 231/212,

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.4 Verify required RCS vent Ž 2.07 square 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for inches open.

unlocked open vent valve(s)

AND 31 days for other vent paths SR 3.4.12.5 Verify PORV block valve is open for each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months required PORV and PORV keyswitch is in AUTO.

SR 3.4.12.6 Verify required PORV backup nitrogen supply 7 days pressure is within limit.

SR 3.4.12.7 ----------------- NOTE---------------

Not required to be met until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after decreasing RCS cold leg temperature to 2350F (Unit 1), 270°F (Unit 2).

Perform a COT on each required PORV, 31 days excluding actuation.

SR 3.4.12.8 Perform CHANNEL CALIBRATION for each 18 months required PORV actuation channel.

North Anna Units 1 and 2 Amendments 231/212, 3.4.12-4

RCS Operational 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE;

d. 1 gpm total primary to secondary LEAKAGE through all steam generators (SGs); and

e. 500 gallons per any one SG.

APPLICABILITY:

day primary to secondary LEAKAGE through MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

RCS LEAKAGE not within A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limits for reasons within limits.

other than pressure boundary LEAKAGE.

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 Pressure boundary LEAKAGE exists.

North Anna Units 1 and 2 LEAKAGE 3.4.13 Amendments 231/212, 3.4.13-1

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

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

Verify RCS operational LEAKAGE is within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limits by performance of RCS water inventory balance.

SR 3.4.13.2 Verify steam generator tube integrity is in In accordance accordance with the Steam Generator Tube with the Steam Surveillance Program.

Generator Tube Surveillance Program North Anna Units 1 and 2 Amendments 231/212, 3.4.13-2

RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 APPLICABILITY:

Leakage from each RCS PIV required to be tested shall be within limit.

MODES 1, 2, and 3, MODE 4, except any required valves in the residual heat removal (RHR) flow path when in, or during the transition to or from, the RHR mode of operation.

ACTIONS NOTES ----

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for inoperable by an inoperable PIV.

systems made CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more flow paths A.1 Restore RCS PIV 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with leakage from one leakage to within or more required RCS limit.

PIVs not within limit.

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 Compl eti on Time for 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 North Anna Units 1 and 2 Amendments 231/212, 3.4.14-1

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.14.1

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

1. Not required to be performed in MODES 3 and 4.

2. Not required to be performed on any RCS PIVs required to be tested located in the RHR flow path when in the shutdown cooling mode of operation.

3. 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.

Verify leakage from each RCS PIV required to be tested is equivalent to

0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure Ž 2215 psig and

2255 psig.

FREQUENCY In accordance with the Inservice Testing Program, and 18 months AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months AND Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months fol l owing valve actuation due to automatic or manual action or flow through the valve

.1 __________________________

North Anna Units 1 and 2 3.4.14-2 Amendments 231/212,

RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 APPLICABILITY:

The following RCS leakage detection instrumentation shall be OPERABLE:

a. One containment sump (level or discharge flow) monitor; and

b. One containment atmosphere radioactivity monitor (gaseous or particulate).

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Required containment A.1

NOTE------

sump monitor Not required until inoperable.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Perform SR 3.4.13.1.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND A.2 Restore required 30 days containment sump monitor to OPERABLE status.

North Anna Units 1 and 2 Amendments 231/212, 3.4.15-1

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

Required containment B.1.1 Analyze grab samples Once per atmosphere of the containment 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months radioactivity monitor atmosphere.

inoperable.

OR B.1.2 -------- NOTE------

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

Perform SR 3.4.13.1.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.2 Restore required 30 days containment atmosphere radioactivity monitor to OPERABLE status.

C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND C.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. All required monitors D.1 Enter LCO 3.0.3.

Immediately inoperable.

North Anna Units 1 and 2 Amendments 231/212, 3.4.15-2

RCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment atmosphere radioactivity monitor.

SR 3.4.15.2 Perform COT of the required containment 92 days atmosphere radioactivity monitor.

SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required 18 months containment sump monitor.

SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required 18 months containment atmosphere radioactivity monitor.

North Anna Units 1 and 2 Amendments 231/212, 3.4.15-3

Intentionally Blank

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 APPLICABILITY:

The specific activity of the reactor coolant shall be within limits.

MODES 1 and 2, MODE 3 with RCS average temperature (Tavg)

Ž 500'F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

DOSE EQUIVALENT 1-131 A.1 Verify DOSE EQUIVALENT Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

> 1.0 UCi/gm.

1-131 within the acceptable region of Figure 3.4.16-1.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.

B. Gross specific B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months activity of the Tavg < 500 0F.

reactor coolant not within limit.

C. Required Action and C.1 Be in-MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Tavg < 5000 F.

Time of Condition A not met.

OR DOSE EQUIVALENT 1-131 in the unacceptable region of Figure 3.4.16-1.

North Anna Units 1 and 2 Amendments 231/212, 3.4.16-1

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS SURVE I LLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant gross specific 7 days activity _ 100/E pCi/gm.

SR 3.4.16.2 ------------------ NOTE--------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 14 days 1-131 specific activity 5 1.0 pCi/gm.

AND 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 SR 3.4.16.3 ------------------ NOTE--------------

Not required to be performed until 31 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for A 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Determine I from a sample taken in MODE 1 184 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for A 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

North Anna Units 1 and 2 Amendments 231/212, 3.4.16-2

RCS Specific Activity 3.4.16 (26%, 25)

N

'-4 I-F-

LL.

I-.

C-ILtj

.- I LaJ k-0' 0

F-20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 3.4.16-1 (page 1 of 1)

Reactor Coolant DOSE EQUIVALENT 1-131 Specific Activity Limit Versus Percent of RATED THERMAL POWER North Anna Units 1 and 2 300.0 250.0 200.0 150.0 100.0 50.0 0.0 UNACCEPTABL OPERATION A 'CEPTABLE OPERATION 100%,

(8--%,60)

Amendments 231/212, 3.4.16-3

Intentionally Blank

RCS Loop Isolation Valves 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 RCS Loop Isolation Valves LCO 3.4.17 APPLICABILITY:

Each RCS hot and cold leg loop isolation valve shall be open with power removed from each isolation valve operator.

MODES 1, 2, 3, and 4.

NOTE Separate Condition entry is allowed for each RCS loop isolation valve.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Power available to one A.1 Remove power from loop 30 minutes or more loop isolation i sol ati on valve valve operators.

operators.

B.

NOTE B.1 Maintain valve(s)

Immediately All Required Actions closed.

shall be completed whenever this AND Condition is entered.

B.2 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months One or more RCS loop AND isolation valves closed.

B.3 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVE I LLANCE FREQUENCY SR 3.4.17.1 Verify each RCS loop isolation valve is Once prior to open.

removing power to the valve operator North Anna Units 1 and 2 ACTIONS 3.4.17-1 Amendments 231/212,

RCS Loop Isolation Valves 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.2 Verify power removed from each RCS loop 31 days isolation valve.

North Anna Units 1 and 2 Amendments 231/212, 3.4.17-2

RCS Isolated Loop Startup 3.4.18 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.18 RCS Isolated Loop Startup LCO 3.4.18 Each RCS isolated loop shall remain isolated with both loop isolation valves closed and power removed from the valve operators unless:

a. The isolated loop is filled and:

1. The boron concentration of the isolated loop is Ž the boron concentration required to meet SDM of LCO 3.1.1 or the boron concentration of LCO 3.9.1 prior to opening the hot leg isolation valve;

2. The hot leg isolation valve has been open with recirculation line flow of Ž 125 gpm for Ž 90 minutes prior to opening the cold leg isolation valve; and

3. The cold leg temperature of the isolated loop is

20°F below the highest cold leg temperature of the operating loops prior to opening the cold leg isolation valve; or

b. The isolated loop is drained and:

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

Seal injection may be initiated to the RCP in the isolated, drained loop and continued during filling of the isolated loop from the active RCS volume provided:

1) The isolated loop is initially drained; and

2) The boron concentration of the seal injection source is Ž the boron concentration required to meet the SDM of LCO 3.1.1 or the boron concentration of LCO 3.9.1.

1. Pressurizer water level is maintained Ž 32% prior to and during the opening of the hot or cold leg isolation valves; and

2. The hot and cold leg isolation valves are fully open within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after the loop is filled.

North Anna Units 1 and 2 Amendments 231/212, 3.4.18-1

RCS Isolated Loop Startup 3.4.18 NOTE ----------------

A hot or cold leg isolation valve may be closed for up to two hours for valve maintenance or testing. If the isolation valve is not opened within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the loop shall be isolated.

APPLICABILITY:

MODES 5 and 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Isolated, filled loop A.1 Close hot and cold leg Immediately boron concentration isolation valves.

requirement not met when performing isolated loop startup in accordance with LCO 3.4.18.a.

B.

Isolated, filled loop B.1 Close cold leg Immediately recirculation line isolation valve.

flow Ž_ 125 gpm for

_>90 minutes with hot leg isolation valve open not established when performing isolated loop startup in accordance with LCO 3.4.18.a.

C.

Isolated, filled loop C.1 Close cold leg Immediately temperature isolation valve.

requirement not met when performing isolated loop startup in accordance with LCO 3.4.18.a.

North Anna Units 1 and 2 Amendments 231/212, 3.4.18-2

RCS Isolated Loop Startup 3.4.18 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Pressurizer level D.1 Close hot and cold leg Immediately requirement not met isolation valves.

during filling of an initially drained loop when performing isolated loop startup in accordance with LCO 3.4.18.b.

OR Seal injection boron concentrati on requirements not met during filling of an initially drained loop when performing isolated loop startup in accordance with LCO 3.4.18.b.

E.

Hot and cold leg E.1 Close hot and cold leg Immediately isolation valves not isolation valves.

fully open within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after filling OR an initially drained loop when performing E.2 Verify the boron Immediately isolated loop startup concentration is _> the in accordance with boron concentration LCO 3.4.18.b.

required to meet the SDM of LCO 3.1.1 or the boron concentration of LCO 3.9.1.

F.

Power available to one F.1 Remove power from the 30 minutes or more loop isolation loop isolation valve valve operators of operator(s).

closed hot or cold isolation valve(s) with LCO 3.4.18.a.1 or LCO 3.4.18.b.1 not met.

North Anna Units 1 and 2 Amendments 231/212, 3.4.18-3

RCS Isolated Loop Startup 3.4.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.18.1 ----------------- NOTE---------------

Only required to be met when utilizing the requirements of LCO 3.4.18.a.

Verify cold leg temperature of a filled, Within isolated loop is A 200F below the highest 30 minutes prior cold leg temperature of the operating to opening the

loops, cold leg isolation valve in isolated loop SR 3.4.18.2 ----------------- NOTE---------------

Only required to be met when utilizing the requirements of LCO 3.4.18.a.

Verify boron concentration of a filled, Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolated loop is greater than or equal to prior to opening boron concentration required to meet SDM of the hot or cold LCO 3.1.1 or the boron concentration of leg isolation LCO 3.9.1.

valve in isolated loop SR 3.4.18.3 ----------------- NOTE---------------

Only required to be met when utilizing the requirements of LCO 3.4.18.a.

Verify that hot leg isolation valve is open Within 30 with recirculation line flow A 125 gpm for minutes prior to A 90 minutes.

opening the cold leg isolation valve in filled, isolated loop North Anna Units 1 and 2 Amendments 231/212, 3.4.18-41

RCS Isolated Loop Startup 3.4.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.18.4 SR 3.4.18.5 NOTE---------------

Only required to be met when utilizing the requirements of LCO 3.4.18.b.

Verify that isolated loop is drained.

NOTES

1. Only required to be met when utilizing the requirements of LCO 3.4.18.b.

2. Only required to be met when using blended makeup flow as the source for RCP seal injection.

Verify the boron concentration of the source for RCP seal injection is

Žthe boron concentration required to meet the SDM of LCO 3.1.1 or the boron concentration of LCO 3.9.1.

FREQUENCY Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to filling an initially drained loop from the active RCS volume OR Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to initiating seal injection to the RCP in a drained loop Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to initiating RCP seal injection in the isolated loop AND Once per hour during filling of an initially drained loop from the active RCS volume North Anna Units 1 and 2 i

i Amendments 231/212, 3.4.18-5

RCS Isolated Loop Startup 3.4.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE 1-SR 3.4.18.6 ----------------- NOTE---------------

Only required to be met when utilizing the requirements of LCO 3.4.18.b.

Verify that the pressurizer level is Ž32%.

SR 3.4.18.7 ----------------- NOTE---------------

Only required to be met when utilizing the requirements of LCO 3.4.18.b.

Verify the boron concentration of the isolated loop is Žthe boron concentration required to meet the SDM of LCO 3.1.1 or the boron concentration of LCO 3.9.1.

FREQUENCY Prior to filling an initially drained loop from the active RCS volume AND Once per 15 minutes during the filling of an initially drained loop from the active RCS volume Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to fully opening the cold leg isolation valve or opening the hot leg isolation valve North Anna Units 1 and 2 Amendments 231/212, 3.4.18-6

RCS Loops-Test Exceptions 3.4.19 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.19 RCS Loops-Test Exceptions LCO 3.4.19 APPLICABILITY:

The requirements of LCO 3.4.4, "RCS Loops-MODES 1 and 2," may be suspended, with THERMAL POWER < P-7.

MODES 1 and 2 during startup and PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

THERMAL POWER Ž P-7.

A.1 Open reactor trip Immediately breakers.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.19.1 Verify THERMAL POWER is < P-7.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SR 3.4.19.2 Perform a COT for each power range neutron Prior to flux-low channel, intermediate range initiation of neutron flux channel, P-1O, and P-13.

startup and PHYSICS TESTS SR-3.4.19.3 Perform an ACTUATION LOGIC TEST on P-7.

Prior to initiation of startup and PHYSICS TESTS North Anna Units 1 and 2 Amendments 231/212, 3.4.19-1

Intentionally Blank

Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators LCO

3.5.1 APPLICABILITY

Three ECCS accumulators shall be OPERABLE.

MODES 1 and 2, MODE 3 with RCS pressure > 1000 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One accumulator A.1 Restore boron 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable due to concentration to boron concentration within limits.

not within limits.

B.

One accumulator B.1 Restore accumulator to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable for reasons OPERABLE status.

other than Condition A.

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 Reduce RCS pressure to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

1000 psig.

D. Two or more D.1 Enter LCO 3.0.3.

Immediately accumulators inoperable.

North Anna Units 1 and 2 Amendments 231/212, 3.5.1-1

Accumulators 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months fully open.

SR 3.5.1.2 Verify borated water volume in each 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months accumulator is 2 7580 gallons and

7756 gallons.

SR 3.5.1.3 Verify nitrogen cover pressure in each 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months accumulator is Ž 599 psig and

667 psig.

SR 3.5.1.4

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

For Unit 2, until the first entry into MODE 4 following the Unit 2 Fall 2002 refueling outage, the accumulator boron concentration acceptance criteria shall be

Ž 2200 ppm and

2400 ppm.

Verify boron concentration in each 31 days accumulator is Ž 2500 ppm and

2800 ppm.

AND NOTE -----

Only required to be performed for affected accumulators Once within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of Ž 50% of indicated level that is not the result of addition from the refueling water storage tank North Anna Units 1 and 2 Amendments 231/212, 3.5.1-2

Accumul ators 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.5 Verify power is removed from each 31 days accumulator isolation valve operator when RCS pressure is Ž 2000 psig.

North Anna Units 1 and 2 Amendments 231/212, 3.5.1-3

Intentionally Blank

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

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

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

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more trains A.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND B.2 Be in MODE 4.

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

Less than 100% of the C.1 Enter LCO 3.0.3.

Immediately ECCS flow equivalent to a single OPERABLE ECCS train available.

North Anna Units 1 and 2 Amendments 231/212, 3.5.2-1

ECCS-Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE I

FREQUENCY SR 3.5.2.1 Verify the following valves are in the listed position with power to the valve operator removed.

Unit 1 Number 1-SI-MOV-1890A 1-SI-MOV-1890B 1-SI-MOV-1836 1-SI-MOV-1869A 1-SI-MOV-1869B Position Function Closed Closed Closed Closed Closed LHSI LHSI HHSI Leg HHSI Leg HHSI Leg to Hot Leg to Hot Leg Pump to Cold Pump to Hot Pump to Hot Unit 2 Number 2-SI-MOV-2890A 2-SI-MOV-2890B 2-SI-MOV-2836 2-SI-MOV-2869A Position Function Closed Closed Closed Closed 2-SI-MOV-2869B Closed LHSI LHSI HHSI Leg HHSI Leg HHSI Leg to Hot Leg to Hot Leg Pump to Cold Pump to Hot Pump to Hot 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.5.2.2 Verify each ECCS manual, power operated, 31 days and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.2.3 Verify ECCS piping is sufficiently full of 92 days water.

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 North Anna Units 1 and 2 Amendments 231/212, 3.5.2-2

ECCS-Operati ng 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.5 Verify each ECCS automatic valve in the 18 months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.5.2.6 Verify each ECCS pump capable of starting 18 months automatically starts automatically on an actual or simulated actuation signal.

SR 3.5.2.7 Verify each ECCS throttle valve listed 18 months below is secured in the correct position.

Unit 1 Valve Number Unit 2 Valve Number 1-SI-188 2-SI-89 1-SI-191 2-SI-97 1-SI-193 2-SI-103 1-SI-203 2-SI-116 1-SI-204 2-SI-111 1-SI-205 2-SI-123 SR 3.5.2.8 Verify, by visual inspection, each ECCS 18 months train containment sump suction inlet is not restricted by debris and the suction inlet trash racks and screens show no evidence of structural distress or abnormal corrosion.

North Anna Units 1 and 2 Amendments 231/212, 3.5.2-3

Intentionally Blank

v t e Letter Sequence Other
TAC:MB0799, Nis Power Range Channel Daily SR TS Change to Address LOW Power Decalibration, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) TAC:MB0800, Nis Power Range Channel Daily SR TS Change to Address LOW Power Decalibration, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed)
Initiation Request, Request, Request, Request Acceptance... Administration Questions Answers Results Approval Other: ML020650715, ML020840253, ML021220053, ML021220061, ML021220067, ML021220088, ML021220108, ML021220166, ML021220192, ML021220214, ML021220221, ML021220224, ML021220254, ML021550518
MONTHYEAR2002-02-20 [Table View]

ML021220108

Text

3.1.1 APPLICABILITY

3.1.4 APPLICABILITY

3.1.6 APPLICABILITY

3.1.8 APPLICABILITY

3.2.4 APPLICABILITY

3.3.1 APPLICABILITY

3.3.2 APPLICABILITY

3.3.3 APPLICABILITY

3.3.5 APPLICABILITY

3.4.3 APPLICABILITY

3.4.4 APPLICABILITY

3.5.1 APPLICABILITY

Navigation menu

Search