ML14170A042

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Attachment 3 - TRM Developmental Revision D Changes (Mark-Up) for WBN Unit 2
ML14170A042
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 06/16/2014
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
Shared Package
ML14170A054 List:
References
Download: ML14170A042 (97)


Text

Definitions 1.1 (continued)

Watts Bar - Unit 2 1.1-1 Technical Requirements (developmental)

A 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 Requirements and Bases.

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

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known input. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions. 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. Whenever a sensing element is replaced, the next required CHANNEL CALIBRATION shall include an inplace cross calibration that compares the other sensing elements with the recently installed sensing element.

The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated.

CHANNEL CHECK 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.

Definitions 1.1 1.1 Definitions (continued)

(continued)

Watts Bar - Unit 2 1.1-2 Technical Requirements (developmental)

A Term Definition CHANNEL OPERATIONAL TEST (COT)

A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display, and trip functions. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or other 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.

ENGINEERED SAFETY FEATURE (ESF) RESPONSE TIME 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 the methodology for verification have been previously reviewed and approved by the NRC.

LEAKAGE LEAKAGE shall be:

a.

Identified LEAKAGE

1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;

Definitions 1.1 1.1 Definitions (continued)

Watts Bar - Unit 2 1.1-3 Technical Requirements (developmental)

AD Term Definition LEAKAGE (continued)

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) tube to the Secondary System;
b.

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

c.

Pressure Boundary LEAKAGE LEAKAGE (except SG tube LEAKAGE) through a non-isolable fault in an RCS component body, pipe wall, or vessel wall.

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

OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified 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).

QUADRANT POWER TILT RATIO (QPTR)

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 lower excore detector calibrated outputs, whichever is greater.

Definitions 1.1 1.1 Definitions (continued)

(continued)

Watts Bar - Unit 2 1.1-4 Technical Requirements (developmental)

B Term Definition RATED THERMAL POWER (RTP)

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.

REACTOR TRIP SYSTEM (RTS) RESPONSE TIME 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 the methodology for verification have been previously reviewed and approved by the NRC.

SHUTDOWN MARGIN (SDM)

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

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.

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

Definitions 1.1 1.1 Definitions (continued)

Watts Bar - Unit 2 1.1-5 Technical Requirements (developmental)

A Term Definition TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT)

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

Definitions 1.1 Watts Bar - Unit 2 1.1-6 Technical Requirements (developmental)

AD Table 1.1-1 (page 1 of 1)

MODES MODE TITLE REACTIVITY CONDITION (keff)

% RATED THERMAL POWER (a)

AVERAGE REACTOR COOLANT TEMPERATURE

(°F) 1 Power Operation 0.99

> 5 NA 2

Startup 0.99

< 5 NA 3

Hot Standby

< 0.99 NA 350 4

Hot Shutdown (b)

< 0.99 NA 350 > Tavg > 200 5

Cold Shutdown (b)

< 0.99 NA

< 200 6

Refueling (c)

NA NA NA (a)

Excluding decay heat.

(b)

All reactor vessel head closure bolts fully tensioned.

(c)

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

Completion Times 1.3 (continued)

Watts Bar - Unit 2 1.3-1 Technical Requirements (developmental)

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

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

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

If situations are discovered that require entry into more than one Condition at a time within a single TR (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.

Completion Times 1.3 1.3 Completion Times (continued)

Watts Bar - Unit 2 1.3-2 Technical Requirements (developmental)

A DESCRIPTION (continued)

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

a.

Must exist concurrent with the first inoperability; and

b.

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

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

a.

The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />," 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.

Completion Times 1.3 1.3 Completion Times (continued)

(continued)

Watts Bar - Unit 2 1.3-3 Technical Requirements (developmental)

A 3

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

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND B.2 Be in MODE 5.

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

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

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

Completion Times 1.3 1.3 Completion Times (continued)

Watts Bar - Unit 2 1.3-4 Technical Requirements (developmental)

A 3

EXAMPLES (continued)

EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump inoperable.

A.1 Restore pump to OPERABLE status.

7 days B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND B.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 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 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. TR 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 TR 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

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

While in TR 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has expired, TR 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.

Completion Times 1.3 1.3 Completion Times (continued)

Watts Bar - Unit 2 1.3-5 Technical Requirements (developmental)

A 3

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for > 7 days.

EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Function X train inoperable.

A.1 Restore Function X train to OPERABLE status.

7 days AND 10 days from discovery of failure to meet the TR B. One Function Y train inoperable.

B.1 Restore Function Y train to OPERABLE status 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 10 days from discovery of failure to meet the TR C. One Function X train inoperable.

C.1 Restore Function X train to OPERABLE status.

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

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

Completion Times 1.3 1.3 Completion Times (continued)

Watts Bar - Unit 2 1.3-6 Technical Requirements (developmental)

A 3

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 TR 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 TR. The separate Completion Time modified by the phrase "from discovery of failure to meet the TR" is designed to prevent indefinite continued operation while not meeting the TR. 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 TR was initially not met, instead of at the time the associated Condition was entered.

Completion Times 1.3 1.3 Completion Times (continued)

Watts Bar - Unit 2 1.3-7 Technical Requirements (developmental)

A 3

EXAMPLES (continued)

EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more valves inoperable.

A.1 Restore valve(s) to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND B.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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

Completion Times 1.3 1.3 Completion Times (continued)

Watts Bar - Unit 2 1.3-8 Technical Requirements (developmental)

A 3

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 valves inoperable.

A.1 Restore valve to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND B.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 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.

Completion Times 1.3 1.3 Completion Times (continued)

(continued)

Watts Bar - Unit 2 1.3-9 Technical Requirements (developmental)

AD 3

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable.

A.1 Perform TSR 3.x.x.x.

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

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 TSR 3.0.2, to each performance after the initial performance. The initial 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> interval. If Required Action A.1 is followed, and the Required Action is not met within the Completion Time (plus the extension allowed by TSR 3.0.2),

Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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.

Completion Times 1.3 1.3 Completion Times Watts Bar - Unit 2 1.3-10 Technical Requirements (developmental)

A EXAMPLES (continued)

EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One subsystem inoperable A.1 Verify affected subsystem isolated.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND A.2 Restore subsystem to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND B.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter" interval begins upon performance of Required Action A.1.

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

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

Boration Systems Flow Paths, Shutdown TR 3.1.1 Watts Bar - Unit 2 3.1-1 Technical Requirements (developmental)

A TR 3.1 REACTIVITY CONTROL SYSTEMS TR 3.1.1 Boration Systems Flow Paths, Shutdown TR 3.1.1 One of the following boron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergency power source:

a.

A flow path from an OPERABLE boric acid storage system, through the boric acid transfer pump, through a charging pump to the Reactor Coolant System (RCS), or

b.

A flow path from an OPERABLE RWST through a charging pump to the RCS.

APPLICABILITY:

MODES 4, 5, and 6.


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

For MODE 4, Technical Specification LCO 3.0.4.b is not applicable to ECCS high head (centrifugal charging) subsystem.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boration Systems flow path OPERABILITY requirements not met.

OR Boration Systems flow path not capable of being powered by an OPERABLE emergency power source.

A.1 Suspend CORE ALTERATIONS.

Immediately AND A.2 Suspend positive reactivity additions.

Immediately

Boration Systems Flow Paths, Shutdown TR 3.1.1 Watts Bar - Unit 2 3.1-2 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.1.1


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

Only required if the flow path from the boric acid storage tanks is required OPERABLE.

Verify temperature of the areas containing flow path components from the boric acid tanks is > 63°F.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> TSR 3.1.1.2 Verify, for the required OPERABLE flow path, that each manual, power operated, or automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

31 days

Boration Systems Flow Paths, Operating TR 3.1.2 Watts Bar - Unit 2 3.1-3 Technical Requirements (developmental)

AD TR 3.1 REACTIVITY CONTROL SYSTEMS TR 3.1.2 Boration Systems Flow Paths, Operating TR 3.1.2 Two of the following three boron injection flow paths shall be OPERABLE:

a.

One flow path from the boric acid tanks, through a boric acid transfer pump, through a charging pump to the Reactor Coolant System (RCS).

b.

Two flow paths from the Refueling Water Storage Tank (RWST),

through charging pumps to the RCS.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required flow path inoperable.

A.1 Restore required flow path to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR A.2.1 Be in MODE 3.

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND A.2.2 Borate to a SDM equivalent to > 1% k/k at 200°F.

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND A.2.3 Restore required path to OPERABLE status.

246 hours0.00285 days <br />0.0683 hours <br />4.06746e-4 weeks <br />9.3603e-5 months <br /> B. Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 4.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

Boration Systems Flow Paths, Operating TR 3.1.2 Watts Bar - Unit 2 3.1-3 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.2.1


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

Only required if the flow path from the boric acid tanks is required OPERABLE.

Verify temperature of the areas containing portions of the required flow path from the boric acid tanks is

> 63°F.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> TSR 3.1.2.2 Verify, for the required OPERABLE flow paths, each manual, power operated or automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

31 days TSR 3.1.2.3 Demonstrate that each automatic valve in the flow path actuates to its correct position on an actual or simulated actuation signal.

18 months TSR 3.1.2.4 Verify that the flow path from the boric acid tanks delivers > 35 gpm to the RCS.

18 months

Charging Pump, Shutdown TR 3.1.3 Watts Bar - Unit 2 3.1-5 Technical Requirements (developmental)

AD TR 3.1 REACTIVITY CONTROL SYSTEMS TR 3.1.3 Charging Pump, Shutdown TR 3.1.3 One charging pump in the boron injection flow path required by TR 3.1.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.

APPLICABILITY:

MODES 4, 5, and 6.


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

For MODE 4, Technical Specification LCO 3.0.4.b is not applicable to ECCS high head (centrifugal charging) subsystem.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required charging pump inoperable.

OR Required charging pump not capable of being powered by an OPERABLE emergency power source.

A.1 Suspend CORE ALTERATIONS.

Immediately AND A.2 Suspend positive reactivity additions.

Immediately TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.3.1 Verify required charging pump's developed head at the test flow point is >greater than or equal to the required developed head.

In accordance with Inservice Testing Program

Charging Pumps, Operating TR 3.1.4 Watts Bar - Unit 2 3.1-6 Technical Requirements (developmental)

AD TR 3.1 REACTIVITY CONTROL SYSTEMS TR 3.1.4 Charging Pumps, Operating TR 3.1.4 Two charging pumps shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required charging pump inoperable.

A.1 Restore required charging pump to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR A.2.1 Be in MODE 3.

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND A.2.2 Borate to a SDM equivalent to > 1% k/k at 200°F.

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND A.2.3 Restore required charging pump to OPERABLE status.

246 hours0.00285 days <br />0.0683 hours <br />4.06746e-4 weeks <br />9.3603e-5 months <br /> B. Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 4.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

Charging Pumps, Operating TR 3.1.4 Watts Bar - Unit 2 3.1-6 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.4.1 Verify required charging pump's developed head at the test flow point is > greater than or equal to the required developed head.

In accordance with Inservice Testing Program

Borated Water Sources, Shutdown TR 3.1.5 Watts Bar - Unit 2 3.1-8 Technical Requirements (developmental)

A TR 3.1 REACTIVITY CONTROL SYSTEMS TR 3.1.5 Borated Water Sources, Shutdown TR 3.1.5 One of the following borated water sources shall be OPERABLE as required by TR 3.1.1:

a.

A Boric Acid Storage System, or

b.

The Refueling Water Storage Tank (RWST).

APPLICABILITY:

MODES 4, 5, and 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required borated water source inoperable.

A.1 Suspend CORE ALTERATIONS.

Immediately AND A.2 Suspend positive reactivity additions.

Immediately

Borated Water Sources, Shutdown TR 3.1.5 Watts Bar - Unit 2 3.1-9 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS


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

1.

TSR 3.1.5.1, TSR 3.1.5.2 and TSR 3.1.5.3 are only required to be performed if the RWST is the required borated water source.

2.

TSR 3.1.5.4, TSR 3.1.5.5 and TSR 3.1.5.6 are only required to be performed if the Boric Acid Storage System is the required borated water source.

SURVEILLANCE FREQUENCY TSR 3.1.5.1


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

Only required when ambient air temperature is

< 60°F.

Verify RWST solution temperature is > 60°F.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSR 3.1.5.2 Verify RWST boron concentration is > 3,100 ppm.

7 days TSR 3.1.5.3 Verify RWST borated water volume is

> 62,900 gallons.

7 days TSR 3.1.5.4 Verify Boric Acid Tank (BAT) solution temperature is

> 63°F.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSR 3.1.5.5 Verify BAT boron concentration is > 6,120 ppm and 6,990 ppm.

7 days TSR 3.1.5.6 Verify BAT borated water volume is

> 5,300 100 gallons.

7 days

Borated Water Sources, Operating TR 3.1.6 Watts Bar - Unit 2 3.1-10 Technical Requirements (developmental)

A TR 3.1 REACTIVITY CONTROL SYSTEMS TR 3.1.6 Borated Water Sources, Operating TR 3.1.6 The following borated water sources shall be OPERABLE as required by TR 3.1.2:

a.

A Boric Acid Storage System, and

b.

The Refueling Water Storage Tank (RWST).

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required Boric Acid Storage System inoperable.

A.1 Restore Boric Acid Storage System, to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR A.2.1 Be in MODE 3.

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND A.2.2 Borate to a SDM equivalent to 1% k/k at 200°F.

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND A.2.3 Restore Boric Acid Storage System to OPERABLE status.

246 hours0.00285 days <br />0.0683 hours <br />4.06746e-4 weeks <br />9.3603e-5 months <br /> B. Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 4.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (continued)

Borated Water Sources, Operating TR 3.1.6 Watts Bar - Unit 2 3.1-11 Technical Requirements (developmental)

AD ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. RWST boron concentration not within limits.

OR RWST borated water temperature not within limits.

C.1 Restore RWST to OPERABLE status.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D. RWST inoperable for reasons other than Condition C.

D.1 Restore RWST to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> E. Required Action and associated Completion Time of Condition C or D not met.

E.1 Be in MODE 3 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND E.2 Be in MODE 4 with one or more RCS cold leg temperatures < 310°F.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.6.1


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

Only required when outside air temperature is

< 60°F or >105°F.

Verify RWST solution temperature is 60°F and 105°F.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSR 3.1.6.2 Verify RWST boron concentration is 3,100 ppm and 3,300 ppm.

7 days (continued)

Borated Water Sources, Operating TR 3.1.6 Watts Bar - Unit 2 3.1-12 Technical Requirements (developmental)

BD TECHNICAL SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.1.6.3 Verifiy RWST borated water volume is 370,000 gallons.

7 days TSR 3.1.6.4


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

Only required if the BAT is required OPERABLE.

Verify Boric Acid Tank (BAT) solution temperature is 63°F.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSR 3.1.6.5


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

Only required if the BAT is required OPERABLE.

Verify BAT boron concentration is in accordance with Figures 3.1.6A, 3.1.6B, and 3.1.6C.

7 days TSR 3.1.6.6


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

Only required if the BAT is required OPERABLE.

Verify BAT borated water volume is in accordance with Figures 3.1.6A, 3.1.6B, and 3.1.6C.

7 days

Borated Water Sources, Operating TR 3.1.6 Watts Bar - Unit 2 3.1-13 Technical Requirements (developmental)

BD TECHNICAL REQUIREMENTS FIGURE 3.1.6 BORIC ACID TANK LIMITS BASED ON RWST BORON CONCENTRATION

Borated Water Sources, Operating TR 3.1.6 Watts Bar - Unit 2 3.1-14 Technical Requirements (developmental)

BD 8000 8500 9000 9500 10000 10500 11000 11500 6000 6100 6200 6300 6400 6500 6600 6700 6800 6900 7000 7100 MINIMUM INDICATED STORED VOLUME IN BAT - GALLONS CONCENTRATION IN BAT - PPM BORON TECHNICAL REQUIREMENTS FIGURE 3.1.6A BORIC ACID TANK LIMITS BASED ON RWST BORON CONCENTRATION Level 1 RWST Concentration 2700 ppm B 2800 ppm B 2900 ppm B REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION RWST = 2800 ppm B RWST = 2700 ppm B RWST Concentration 6990 ppm MAXIMUM 6120 ppm MINIMUM Indicated values include additional 1,910 gal compensation for unusable vol, instrument error, and conservatism.

RWST 2900 ppm B DELETED

Borated Water Sources, Operating TR 3.1.6 Watts Bar - Unit 2 3.1-15 Technical Requirements (developmental)

BD 8000 8500 9000 9500 10000 10500 11000 11500 6000 6100 6200 6300 6400 6500 6600 6700 6800 6900 7000 7100 MINIMUM INDICATED STORED VOLUME IN BAT - GALLONS CONCENTRATION IN BAT - PPM BORON TECHNICAL REQUIREMENTS FIGURE 3.1.6B BORIC ACID TANK LIMITS BASED ON RWST BORON CONCENTRATION Level 2 RWST Concentration 3100 ppm B 3200 ppm B 3300 ppm B REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION RWST = 3200 ppm B RWST = 3100 ppm B RWST Concentration 6990 ppm MAXIMUM 6120 ppm MINIMUM Indicated values include additional 1,910 gal compensation for unusable vol, instrument error, and conservatism.

RWST 3300 ppm B DELETED

Borated Water Sources, Operating TR 3.1.6 Watts Bar - Unit 2 3.1-16 Technical Requirements (developmental)

BD 8000 8500 9000 9500 10000 10500 11000 11500 6000 6100 6200 6300 6400 6500 6600 6700 6800 6900 7000 7100 MINIMUM INDICATED STORED VOLUME IN BAT - GALLONS CONCENTRATION IN BAT - PPM BORON TECHNICAL REQUIREMENTS FIGURE 3.1.6C BORIC ACID TANK LIMITS BASED ON RWST BORON CONCENTRATION Level 3 RWST Concentration 3600 ppm B 3700 ppm B 3800 ppm B REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION RWST = 3700 ppm B RWST = 3600 ppm B RWST Concentration 6990 ppm MAXIMUM 6120 ppm MINIMUM Indicated values include additional 1,910 gal compensation for unusable vol, instrument error, and conservatism.

RWST = 3800 ppm B DELETED

ESFAS Instrumentation TR 3.3.2 Watts Bar - Unit 2 3.3-4 Technical Requirements (developmental)

A TR 3.3 INSTRUMENTATION TR 3.3.2 Engineered Safety Features Actuation System (ESFAS) Instrumentation TR 3.3.2 The ESFAS instrumentation channels and interlocks as shown in Technical Specification (TS) 3.3.2, Table 3.3.2-1; TS 3.3.5, LCO 3.3.5; TS 3.3.6, Table 3.3.6-1; and TS 3.6.9 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3.2-1 of this document.

APPLICABILITY:

As shown in TS 3.3.2, Table 3.3.2-1; TS 3.3.5 Applicability; TS 3.3.6 Applicability; and TS 3.6.9 Applicability.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Refer to TS 3.3.2, Table 3.3.2-1; TS 3.3.5 ACTIONS; TS 3.3.6 ACTIONS; and TS 3.6.9 ACTIONS.

A.1 Refer to TS 3.3.2, Table 3.3.2-1; TS 3.3.5 ACTIONS; TS 3.3.6 ACTIONS; and TS 3.6.9 ACTIONS.

Refer to TS 3.3.2, Table 3.3.2-1; TS 3.3.5 ACTIONS; TS 3.3.6 ACTIONS; and TS 3.6.9 ACTIONS.

TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.2.1 Verify ESFAS RESPONSE TIME of each ESFAS function is within the limits of Table 3.3.2-1.

18 months on a STAGGERED TEST BASIS

ESFAS Instrumentation TR 3.3.2 Watts Bar - Unit 2 3.3-5 Technical Requirements (developmental)

A Table 3.3.2-1 (Page 1 of 6)

Engineered Safety Features Actuation System Response Times INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

1.

Manual Initiation

a. Safety Injection (ECCS)

N/A

b. Containment Spray N/A
c. Phase "A" Isolation N/A
d. Phase "B" Isolation N/A
e. Containment Ventilation Isolation N/A
f. Steam Line Isolation N/A
g. Feedwater Isolation N/A
h. Auxiliary Feedwater N/A
i.

Essential Raw Cooling Water N/A

j.

CREVS Actuation N/A

k. Containment Air Return Fan N/A
l.

Component Cooling System N/A

m. Start Diesel Generators N/A
n. Reactor Trip N/A
2.

Containment Pressure - High

a. Safety Injection (ECCS)

< 27 (4) / 32 (14) / 37 (5)

1) Reactor Trip

< 2

2) Feedwater Isolation

< 8 (3)

3) Containment Isolation - Phase A (6)

< 12 (2) / 22 (1)

4) Containment Ventilation Isolation

< 6.0 (2) (11)

5) Auxiliary Feedwater Pumps

< 60 (10)

6) Essential Raw Cooling Water

< 47 (2) / 57 (1)

7) CREVS Actuation N/A (continued)

ESFAS Instrumentation TR 3.3.2 Watts Bar - Unit 2 3.3-6 Technical Requirements (developmental)

A Table 3.3.2-1 (Page 2 of 6)

Engineered Safety Features Actuation System Response Times INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

2.

Containment Pressure - High (continued)

8) Component Cooling System

< 50 (2) /60 (1)

9) Start Diesel Generators

< 12 (12)

3.

Pressurizer Pressure - Low

a. Safety Injection (ECCS)

< 27 (4) / 32 (14) / 37 (5)

1) Reactor Trip

< 2

2) Feedwater Isolation

< 8 (3)

3) Containment Isolation - Phase A (6)

< 12 (2) / 22 (1)

4) Containment Ventilation Isolation

< 6.0 (2) (11)

5) Auxiliary Feedwater Pumps

< 60 (10)

6) Essential Raw Cooling Water

< 47 (2) / 57 (1)

7) CREVS Actuation N/A
8) Component Cooling System

< 50 (2) / 60 (1)

9) Start Diesel Generators

< 12 (12)

4.

Steam Line Pressure Negative Rate - High

a. Steam Line Isolation

< 8

5.

Steam Line Pressure - Low

a. Safety Injection (ECCS)

< 27 (4) / 32 (14) / 37 (5)

1) Reactor Trip (from SI)

< 2

2) Feedwater Isolation

< 8 (3)

3) Containment Isolation-Phase "A"(6)

< 12(2) / 22(1)

(continued)

ESFAS Instrumentation TR 3.3.2 Watts Bar - Unit 2 3.3-7 Technical Requirements (developmental)

AD Table 3.3.2-1 (Page 3 of 6)

Engineered Safety Features Actuation System Response Times INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

5.

Steam Line Pressure - Low

4) Containment Ventilation Isolation

< 6.0 (2) (11)

5) Auxiliary Feedwater Pumps

< 60 (10)

6) Essential Raw Cooling Water

< 47 (2) / 57 (1)

7) CREVS Actuation N/A
8) Component Cooling System

< 50 (2) / 60 (1)

9) Start Diesel Generators

< 12 (12)

b. Steam Line Isolation

< 8

6.

Containment Pressure - High - High

a. Containment Spray

< 234 (13)

b. Containment Isolation-Phase "B"

< 68 (2) / 78 (1)

c. Steam Line Isolation

< 8

d. Containment Air Return Fans 480 < RT < 600
7.

Steam Generator Water Level - High - High

a. Turbine Trip

< 2.5

b. Feedwater Isolation

< 8 (3)

8.

Steam Generator Water Level - Low - Low

a. Motor-driven Auxiliary Feedwater Pumps

< 60 (7)

b. Turbine-driven Auxiliary Feedwater Pumps

< 60 (8)

9.

DELETEDNOT USED (continued)

ESFAS Instrumentation TR 3.3.2 Watts Bar - Unit 2 3.3-8 Technical Requirements (developmental)

A Table 3.3.2-1 (Page 4 of 6)

Engineered Safety Features Actuation System Response Times INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

10.

RWST Level-Low Coincident with Containment Sump Level -

High and Safety Injection Automatic Switchover to Containment Sump

< 250

11.

Loss-of-Offsite Power Auxiliary Feedwater Pumps

< 60

12.

Trip of All Main Feedwater Pumps Auxiliary Feedwater Pumps

< 60

13.

Auxiliary Feedwater Pump Suction Transfer on Suction Pressure - Low

a. Motor-driven Auxiliary Feedwater Pumps

< 47

b. Turbine-driven Auxiliary Feedwater Pumps

< 42

14.

Loss of Voltage/Degraded Voltage 6.9 kV Shutdown Board

< 12 (9)

15.

MSV Vault Room Water Level - High

a. North MSV Vault Room

< 8.5 (15)

b. South MSV Vault Room

< 8.5 (15)

ESFAS Instrumentation TR 3.3.2 Watts Bar - Unit 2 3.3-9 Technical Requirements (developmental)

A Table 3.3.2-1 (Page 5 of 6)

Engineered Safety Features Actuation System Response Times TABLE NOTATIONS (1)

Diesel generator starting and sequence loading delays included.

(2)

Diesel generator starting and sequence loading delay not included. Offsite power available.

(3)

Air operated valves.

(4)

Offsite power available - diesel generator starting and sequence loading delays not included. Response time limit includes the opening of valves to establish flowpath and bringing the pumps to full speed. The additional sequential transfer of CCP suction from the VCT to the RWST (RWST valves open, then the VCT valves close) is included.

(5)

Diesel generator starting and sequence loading delays included. Response time limit includes the opening of valves to establish flow path and bringing the pumps up to full speed. The additional sequential transfer of suction from the VCT to the RWST (RWST valves open, then VCT valves close) is included.

(6)

The following equipment are exceptions to the response time shown in the table and will have the following response times for the initiating signals and functions:

A. Fire Protection CIVs 22 (2) / 32 (1)

B. Ice Condenser CIVs 32 C. Excess Letdown Hx Supply CIV 68 (2 )/ 78 (1)

D. EGTS Fans 20 (2) / 30 (1)

E. Required for EGTS OPERABILITY

1. Fire Protection Secondary CIVs 20 (2) / 30 (1)
2. Secondary Containment Purge Isolation Valves 12.7 (2) / 22.7 (1)

F. Steam Generator Blowdown CIVs 17 (2) / 27 (1)

(7)

On 2/3 any steam generator and Trip Time Delay = 0 seconds.

(8)

On 2/3 in 2/4 steam generators and Trip Time Delay = 0 seconds.

(continued)

ESFAS Instrumentation TR 3.3.2 Watts Bar - Unit 2 3.3-10 Technical Requirements (developmental)

BD Table 3.3.2-1 (Page 6 of 6)

Engineered Safety Features Actuation System Response Times TABLE NOTATIONS (9)

The response time is measured from the time the 6.9 kV shutdown boards voltage exceeds the Setpoint until the time full voltage is returned for the loss of voltage sensors; or from the time the degraded voltage timers generate a signal to trip the feeder breakers and shed loads until the time full voltage is returned for the degraded voltage sensors.

(10) The Response Time for motor-driven AFW pumps includes the diesel generator starting and sequence loading delays. The Response Time for (steam) turbine driven AFW pumps does not include diesel generator starting and sequence loading delays.

(11) Containment purge valves only. Containment radiation monitor valves have a response time of 6.5 seconds.

(12) Diesel generator start time includes a reactor trip response time of 2 seconds.

(13) Includes diesel generator starting, containment spray pump sequence loading-delay/breaker closure, plus stroke time of 2-FCV-72-2 and 2-FCV-72-39.*

The containment integrity analysis of record was performed using 221 seconds for initiation of spray. However, Westinghouse document WAT-D-11264 has evaluated the initiation of spray at 234 seconds with the conclusion that the increase will have no effect on the results or conclusions of the Watts Bar LOCA and MSLB containment integrity analysis.

(14) Diesel generator starting and sequence loading delays included. Response time limit includes the opening of valves to establish flowpath and bring pumps to full speed. The additional sequential transfer of ECCS pump suction from the VCT to the RWST (RWST valves open) is included.

(15) Feedwater Isolation Valve (motor) and Feedwater Regulating Valve (air operated) response time includes an ESFAS signal response time of 2 seconds.

Power Distribution Monitoring System (PDMS)DELETED TR 3.3.3 Watts Bar - Unit 2 3.3-11 Technical Requirements (developmental)

BD TR 3.3 INSTRUMENTATION TR 3.3.3 Power Distribution Monitoring System (PDMS)DELETED TR 3.3.3 The PDMS shall be OPERABLE with:

a. THERMAL POWER >25% RTP, and
b. The required channel inputs from the plant computer for each function OPERABLE as defined in Table 3.3.3-1 APPLICABILITY:

When the PDMS is used for:

a.

Calibration of the Excore Neutron Flux Detection System, or

b.

Monitoring the QUADRANT POWER TILT RATIO, or

c.

Measurement of FH N and FQ(Z), or

d.

Verifying the position of a rod with inoperable position indicators.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

PDMS inoperable.

A.1


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

TR 3.0.3 is not applicable.

Restore the inoperable system to OPERABLE status.

Prior to using the system for incore power distribution measurement purposes.

Power Distribution Monitoring System (PDMS)DELETED TR 3.3.3 Watts Bar - Unit 2 3.3-12 Technical Requirements (developmental)

BD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.39.1 Perform CHANNEL CHECK for each required instrumentation channel specified in Table 3.3.3-1.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSR 3.3.39.2 Verify by administrative means that the surveillance requirements for each required channel specified in Table 3.3.3-1 areis satisfied.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSR 3.3.3.3


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

The initial calibration after each refueling requires

> 218 Self-Powered Detector Elements.

Once after each refueling AND 180 EFPD thereafter.

Perform PDMS calibration.

Power Distribution Monitoring System (PDMS)DELETED TR 3.3.3 Watts Bar - Unit 2 3.3-13 Technical Requirements (developmental)

BD Table 3.3.3-1 (Page 1 of 12)

Power Distribution Monitoring System (PDMS) Instrumentation FUNCTION REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS SURVEILLANCE TYPE

1. RCS Cold Leg Temperature 2(8)

SR 3.3.1.10(6)

SR 3.3.3.3(7)

CHANNEL CALIBRATION

2. Reactor Power 1(1)

SR 3.3.1.2(4)

SR 3.3.1.10(3)

Calorimetric Heat Balance CHANNEL CALIBRATION

3. Control Bank Position (per bank) 1(2)

SR 3.1.8.1 CHANNEL CHECK

4. Self-Powered Detector Elements

> 145 218 total (5) and

> 16 per core quadrant and

> 6 per top core quadrant and

> 6 per bottom core quadrant (1) Either secondary calorimetric power, average power range neutron flux power, or average RCS Loop T power (2) Either the Demand Position Indication or the average of the individual Rod Position Indications (3) Applies to average RCS Loop T power only (4) Not applicable to average RCS Loop T power (5) 145 Self-Powered Detector Elements are sufficient for incore power distribution measurements generated by the PDMS subsequent to the initial incore power distribution measurement in each operating cycle.

Power Distribution Monitoring System (PDMS)DELETED TR 3.3.3 Watts Bar - Unit 2 3.3-14 Technical Requirements (developmental)

BD Table 3.3.3-1 (Page 2 of 2)

Power Distribution Monitoring System (PDMS) Instrumentation (6) Applies to Narrow Range RTDs only.

(7) Applies to Wide Range RTDs only.

(8) Either Narrow Range or Wide Range RTDs.

Turbine Overspeed ProtectionDeleted TR 3.3.5 Watts Bar - Unit 2 3.3-18 Technical Requirements (developmental)

AD TR 3.3 INSTRUMENTATION TR 3.3.5 Turbine Overspeed ProtectionDeleted TR 3.3.5 At least one Turbine Overspeed Protection System shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.


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

Not applicable to MODES 2 and 3 when all main steam isolation valves are closed and all other steam flow paths to the turbine are isolated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One high pressure turbine steam inlet valve inoperable.

A.1.1 Verify the two high pressure turbine steam inlet valves on the same steam chest which are opposite the inoperable valve are OPERABLE.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND A.1.2 Restore inoperable valve to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR A.2.1 Verify the two high pressure turbine steam inlet valves on the same steam chest which are opposite the inoperable valve are OPERABLE.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

Turbine Overspeed ProtectionDeleted TR 3.3.5 Watts Bar - Unit 2 3.3-19 Technical Requirements (developmental)

AD ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.2 Remove the turbine from service by closing all the high pressure turbine steam inlet valves.

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> OR A.3 Close MSIVs.

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> B.

One reheat stop valve or one reheat intercept valve per low pressure turbine steam line inoperable.

B.1 Restore inoperable valve(s) to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR B.2 Close at least one valve in the affected steam line(s).

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> OR B.3 Isolate the turbine from the steam supply.

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> C.1.2 Restore inoperable value to OPERABLE status.

78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> C.

Turbine Overspeed Protection System inoperable for causes other than Condition A or Condition B.

C.1 Isolate the turbine from the steam supply system.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

Turbine Overspeed ProtectionDeleted TR 3.3.5 Watts Bar - Unit 2 3.3-20 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.5.1 Verify the Turbine Overspeed Protection System is OPERABLE in accordance with the Turbine Integrity Program With Turbine Overspeed Protection (TIPTOP).

In accordance with TIPTOP.

Hydrogen Monitor TR 3.3.8 Watts Bar - Unit 2 3.3-23 Technical Requirements (developmental)

B TR 3.3 INSTRUMENTATION 3.3.8 Hydrogen Monitor TR 3.3.8 The Hydrogen Monitor shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Hydrogen Monitor inoperable.

A.1 Restore monitor to OPERABLE status.

7 days B. Required Action and associated Completion Time of Condition A not met.

Initiate a Corrective Actions Program (CAP) document to develop plans and schedule for restoring the monitor to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

Hydrogen Monitor TR 3.3.8 Watts Bar - Unit 2 3.3-24 Technical Requirements (developmental)

BD SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.8.1 Perform CHANNEL CALIBRATION.

18 months

Power Distribution Monitoring System (PDMS)

TR 3.3.39 Watts Bar - Unit 2 3.3-11 Technical Requirements (developmental)

BD TR 3.3 INSTRUMENTATION TR 3.3.3 9 Power Distribution Monitoring System (PDMS)

TR 3.3.39 The PDMS shall be OPERABLE with:

a. THERMAL POWER >25% RTP, and
b. The required channel inputs from the plant computer for each function OPERABLE as defined in Table 3.3.39-1 APPLICABILITY:

When the PDMS is used for:

a.

Calibration of the Excore Neutron Flux Detection System, or

b.

Monitoring the QUADRANT POWER TILT RATIO, or

c.

Measurement of FH N and FQ(Z), or

d.

Verifying the position of a rod with inoperable position indicators.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

PDMS inoperable.

A.1


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

TR 3.0.3 is not applicable.

Restore the inoperable system to OPERABLE status.

Prior to using the system for incore power distribution measurement purposes.

Power Distribution Monitoring System (PDMS)

TR 3.3.39 Watts Bar - Unit 2 3.3-12 Technical Requirements (developmental)

BD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.39.1 Perform CHANNEL CHECK for each required instrumentation channel specified in Table 3.3.39-1.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSR 3.3.39.2 Verify by administrative means that the surveillance requirements for each required channel specified in Table 3.3.39-1 areis satisfied.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSR 3.3.3.3


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

The initial calibration after each refueling requires

> 218 Self-Powered Detector Elements.

Once after each refueling AND 180 EFPD thereafter.

Perform PDMS calibration.

Power Distribution Monitoring System (PDMS)

TR 3.3.39 Watts Bar - Unit 2 3.3-13 Technical Requirements (developmental)

BD Table 3.3.39-1 (Page 1 of 12)

Power Distribution Monitoring System (PDMS) Instrumentation FUNCTION REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS SURVEILLANCE TYPE

1. RCS Cold Leg Temperature 2(8)

SR 3.3.1.10(6)

SR 3.3.39.32(7)

CHANNEL CALIBRATION

2. Reactor Power 1(1)

SR 3.3.1.2(4)

SR 3.3.1.10(3)

Calorimetric Heat Balance CHANNEL CALIBRATION

3. Control Bank Position (per bank) 1(2)

SR 3.1.8.1 CHANNEL CHECK

4. Self-Powered Detector Elements

> 145 218 total (5) and

> 16 per core quadrant and

> 6 per top core quadrant and

> 6 per bottom core quadrant (1) Either secondary calorimetric power, average power range neutron flux power, or average RCS Loop T power (2) Either the Demand Position Indication or the average of the individual Rod Position Indications (3) Applies to average RCS Loop T power only (4) Not applicable to average RCS Loop T power (5) 145 Self-Powered Detector Elements are sufficient for incore power distribution measurements generated by the PDMS subsequent to the initial incore power distribution measurement in each operating cycle.

Power Distribution Monitoring System (PDMS)

TR 3.3.39 Watts Bar - Unit 2 3.3-14 Technical Requirements (developmental)

BD Table 3.3.9-1 (Page 2 of 2)

Power Distribution Monitoring System (PDMS) Instrumentation (6) Applies to Narrow Range RTDs only.

(7) Applies to Wide Range RTDs only.

(8) Either Narrow Range or Wide Range RTDs.

Reactor Vessel Head Vent SystemCS Vents TR 3.4.3 Watts Bar - Unit 2 3.4-5 Technical Requirements (developmental)

AD TR 3.4 REACTOR COOLANT SYSTEM (RCS)

TR 3.4.3 Reactor Vessel Head Vent SystemCS Vents TR 3.4.3 Two Reactor Vessel Head Vent System (RVHVS)Coolant System Vent (RCSV) paths shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One RCSV RVHVS path inoperable.

A.1 Initiate action to maintain the affected RCSV RVHVS path closed with power removed from the valve actuators.

Immediately AND A.2 Restore the inoperable path to OPERABLE status.

30 days B.

Two RCSV RVHVS paths inoperable.

B.1 Restore one RCSV RVHVS path to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C.

Required Action and associated Completion Time of Condition A or B not met.

C.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND C.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

Reactor Vessel Head Vent SystemCS Vents TR 3.4.3 Watts Bar - Unit 2 3.4-6 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.3.1 Verify that the upstream manual RCSV RVHVS isolation valves are is locked in the opened position.

18 months TSR 3.4.3.2 Operate each remotely controlled valve through at least one complete cycle of full travel from the control room.

In accordance with the Inservice Testing Program TSR 3.4.3.3 Verify flow through the RCSV RVHVS paths during venting.

18 months

Chemistry TR 3.4.4 Watts Bar - Unit 2 3.4-7 Technical Requirements (developmental)

AD TR 3.4 REACTOR COOLANT SYSTEM (RCS)

TR 3.4.4 Chemistry TR 3.4.4 The RCS Chemistry shall be maintained within the limits specified below:

PARAMETER STEADY STATE LIMIT TRANSIENT LIMIT DISSOLVED OXYGEN

< 0.10 ppm

< 1.00 ppm CHLORIDE

< 0.15 ppm

< 1.50 ppm FLUORIDE

< 0.15 ppm

< 1.50 ppm APPLICABILITY:

At all times.


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

With Tavg < 250°F, the dissolved oxygen limit is not applicable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more chemistry parameters not within Steady State Limits, in MODE 1, 2, 3, or 4.

A.1 Restore the parameter to within its Steady State Limit.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B.

One or more chemistry parameters not within the Transient Limits in MODES 1, 2, 3 and 4.

OR Required Action and associated Completion Time of Condition A not met.

B.1.

Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND B.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)

Chemistry TR 3.4.4 Watts Bar - Unit 2 3.4-8 Technical Requirements (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.


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

All Required Actions must be completed whenever this Condition is entered.

RCS chloride or fluoride concentration not within the Steady State Limits for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any condition other than MODES 1, 2, 3 and 4.

OR RCS chloride or fluoride concentration not within Transient Limits in any condition other than MODES 1, 2, 3 and 4.

C.1 Initiate action to reduce the pressurizer pressure to 500 psig.

Immediately AND C.2 Perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the RCS.

Prior to increasing the pressurizer pressure > 500 psig OR Prior to entry to MODE 4 AND C.3 Determine that the RCS remains acceptable for continued operation.

Prior to increasing the pressurizer pressure > 500 psig OR Prior to entry to MODE 4

Chemistry TR 3.4.4 Watts Bar - Unit 2 3.4-9 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.4.1


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

Not required with Tavg < 250°F.

Demonstrate by analysis that RCS dissolved oxygen concentration is < 0.10 ppm.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> TSR 3.4.4.2 Demonstrate by analysis that RCS chloride concentration is < 0.15 ppm.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> TSR 3.4.4.3 Demonstrate by analysis that RCS fluoride concentration is < 0.15 ppm.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

Piping System Structural Integrity TR 3.4.5 Watts Bar - Unit 2 3.4-10 Technical Requirements (developmental)

AD TR 3.4 REACTOR COOLANT SYSTEM (RCS)

TR 3.4.5 Piping System Structural Integrity TR 3.4.5 The structural integrity of ASME Code Class 1, 2, and 3 components in all systems shall be maintained in accordance with TSR 3.4.5.1 and TSR 3.4.5.2.

APPLICABILITY:

All MODES.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Structural integrity of any ASME Code Class 1 component(s) not within limits.

A.1 Restore structural integrity of affected component(s) to within limit.

Prior to increasing Reactor Coolant System temperature

> 50°F above the minimum temperature required by NDT considerations OR A.2 Isolate affected component(s).

Prior to increasing Reactor Coolant System temperature

> 50°F above the minimum temperature required by NDT considerations.

(continued)

Piping System Structural Integrity TR 3.4.5 Watts Bar - Unit 2 3.4-11 Technical Requirements (developmental)

A ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

Structural integrity of any ASME Code Class 2 component(s) not within limits.

B.1 Restore structural integrity of affected component(s) to within limit.

Prior to increasing Reactor Coolant System temperature to > 200°F.

OR B.2 Isolate affected component(s).

Prior to increasing Reactor Coolant System temperature to > 200°F.

C.

Structural integrity of any ASME Code Class 3 component(s) not within limits.

C.1 Enter applicable Conditions and Required Actions for the affected component.

Immediately AND C.2.1 Restore structural integrity of affected component(s) to within limit.

Within the Completion Time specified in the affected component LCO or TR.

OR C.2.2 Isolate affected component(s) from remaining system.

Within the Completion Time specified in the affected component LCO or TR.

Piping System Structural Integrity TR 3.4.5 Watts Bar - Unit 2 3.4-12 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.5.1 Inspect each reactor coolant pump flywheel according to the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

According to the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1 TSR 3.4.5.2 Verify the structural integrity of ASME Code Class 1, 2, and 3 components in all systems are in accordance with the Inservice Inspection Program.

In accordance with the Inservice Inspection Program

Ice Bed Temperature Monitoring System TR 3.6.1 Watts Bar - Unit 2 3.6-1 Technical Requirements (developmental)

AD TR 3.6 CONTAINMENT SYSTEMS TR 3.6.1 Ice Bed Temperature Monitoring System TR 3.6.1 The Ice Bed Temperature Monitoring System shall be OPERABLE with at least two OPERABLE RTD channels in the ice bed at each of three basic elevations: 10' 6", 30' 9" and 55' above the floor of the ice condenser, for each one-third of the ice condenser.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Ice Bed temperature not available in the main control room (Satellite Display System (SDS).

A.1 Monitor ice bed temperature at the local ice condenser temperature recorder (indicator) located in the Incore Instrumentation Roommonitoring panel (local panel).

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B.

Ice Bed Temperature Monitoring System inoperable (Integrated Computer System (ICS) -

Satellite Display System (SDS)).

AND Local ice condenser temperature monitoring panel inoperable - indicator located in the Incore B.1.1 Verify ice compartment lower inlet doors, intermediate deck doors, and top deck doors are closed.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND B.1.2 Verify last recorded mean ice bed temperature was

< 20°F and steady.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND

Ice Bed Temperature Monitoring System TR 3.6.1 Watts Bar - Unit 2 3.6-2 Technical Requirements (developmental)

AD Instrumentation Room.

B.1.3 Verify Ice Condenser Cooling System is OPERABLE with at least 21 air handling units, two glycol circulating pumps and three refrigerant units OPERABLE.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter (continued)

Ice Bed Temperature Monitoring System TR 3.6.1 Watts Bar - Unit 2 3.6-3 Technical Requirements (developmental)

AD ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

AND B.2.1 Restore Ice Bed Temperature Monitoring System to OPERABLE status.

30 days OR B.2.2 Restore local temperature monitoring panel recorder (indicator) located in the Incore Instrumentation Room to OPERABLE status.

30 days C.

Ice Bed Temperature Monitoring System inoperable.

AND Local ice condenser temperature monitoring panel recorder (indicator) located in the Incore Instrumentation Room inoperable.

AND Ice Condenser Cooling System inoperable.

C.1.1 Verify ice compartment lower inlet doors, intermediate deck doors, and top deck doors are closed.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND C.1.2 Verify last recorded mean ice bed temperature was

< 15°F and steady.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND C.2.1 Restore the Ice Condenser Cooling System to OPERABLE status.

6 days OR C.2.2 Restore Ice Bed Temperature Monitoring System to OPERABLE status.

6 days OR (continued)

Ice Bed Temperature Monitoring System TR 3.6.1 Watts Bar - Unit 2 3.6-4 Technical Requirements (developmental)

AD ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2.3 Restore local temperature monitoring panel recorder (indicator) located in the Incore Instrumentation Room to OPERABLE status.

6 days D.

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

D.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND D.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.6.1.1 Perform CHANNEL CHECK on the Ice Bed Temperature Monitoring System.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

Lower Compartment Cooling System TR 3.6.3 Watts Bar - Unit 2 3.6-6 Technical Requirements (developmental)

AD TR 3.6 CONTAINMENT SYSTEMS TR 3.6.3 Lower Compartment Cooling (LCC) System TR 3.6.3 Two LCC trains with two fans in each train shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One LCC fan inoperable.

A.1 Restore LCC fan to OPERABLE status.

7 days B.

Two LCC fans inoperable.

B.1 Restore at least one LCC fan to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C.

Required action and associated Completion Time of Conditions A or B not met.

OR More than two LCC fans inoperable.

C.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND C.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.6.3.1 Verify that each fan can be started from the control room and operates for > 15 minutes.

31 days

Steam Generator Pressure/Temperature Limitations TR 3.7.1 Watts Bar - Unit 2 3.7-1 Technical Requirements (developmental)

AD TR 3.7 PLANT SYSTEMS TR 3.7.1 Steam Generator Pressure/Temperature Limitations TR 3.7.1 The pressure of the primary and secondary side of each reactor and secondary coolants in the Steam Generators shall be 200 psig.

APPLICABILITY:

Whenever the temperature of the reactor or secondary coolant in any Steam Generator 70°F.


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

While this TR is not met, decreasing the temperature of the coolant in the primary or secondary of any steam generator to 70°F is not permitted.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.


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

All Required Actions must be completed whenever this Condition is entered.

Steam Generator pressure not within limits.

A.1 Reduce pressure to 200 psig.

30 minutes AND A.2 Perform an over-pressurization and structural integrity engineering evaluation to determine that the effect of the over-pressurization on the structural integrity of the Steam Generator remains acceptable for continued operation.

Prior to increasing Steam Generator coolant temperatures to > 200°F AND

Steam Generator Pressure/Temperature Limitations TR 3.7.1 Watts Bar - Unit 2 3.7-2 Technical Requirements (developmental)

AD A.3 Determine that the Steam Generator remains acceptable for continued operation.

Prior to increasing Steam Generator coolant temperatures to > 200°F

Steam Generator Pressure/Temperature Limitations TR 3.7.1 Watts Bar - Unit 2 3.7-3 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.1.1 Determine that the pressure of the primary reactor and the secondary side of each coolants in the Steam Generators is < 200 psig.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-5 Technical Requirements (developmental)

AD TR 3.7 PLANT SYSTEMS TR 3.7.3 Snubbers TR 3.7.3 All required* snubbers utilized on safety related systems shall be OPERABLE. For those snubbers utilized on non-safety related systems, each snubber shall be OPERABLE if a failure of that snubber or the failure of the non-safety related system would have an adverse effect on any safety related system.

APPLICABILITY:

MODES 1, 2, 3, and 4.

MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required*

snubber(s) removed from serviceinoperable.

A.1.1 Declare the supported system inoperableRestore snubber(s) to OPERABLE status.

72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />sImmediately OR A.1.2 Replace snubber(s).

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND A.2 Perform an engineering evaluation per Table 3.7.3-5 on the attached component.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR A.3 Perform an engineering evaluation demonstrating OPERABILITY of the supported system.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)

  • Required means the snubber performs a support function that is necessary for the supported TS system to perform its specified safety function.

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-6 Technical Requirements (developmental)

AD ACTIONS (continued)

B.

Required Action and associated Completion Time not metOne or more required* snubber(s) found inoperable.

B.1 Declare the supported component or supported system inoperable and enter the applicable LCO action statement for the supported system.

Immediately B.2 Perform an engineering evaluation per Table 3.7.3-5 Note 3 on the attached component.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C.

Required Action(s) and associated Completion TIme(s) not met.

C.1 Initiate a PER.

Immediately

  • Required means the snubber performs a support function that is necessary for the supported TS system to perform its specified safety function.

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-7 Technical Requirements (developmental)

A TECHNICAL SURVEILLANCE REQUIREMENTS


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

1.

Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.

2.

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

3.

As used herein, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.

SURVEILLANCE FREQUENCY TSR 3.7.3.1 Visually inspect each snubber in accordance with the acceptance criteria in Table 3.7.3-1.

In accordance with Table 3.7.3-2 TSR 3.7.3.2 Perform a transient event inspection of all hydraulic and mechanical snubbers in accordance with Table 3.7.3-3.

6 months following transient event TSR 3.7.3.3 Perform a functional test on a representative sample of snubbers in accordance with Table 3.7.3-4 to determine acceptance with criteria in Table 3.7.3-5.

Each refueling outage (continued)

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-8 Technical Requirements (developmental)

B TECHNICAL SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.7.3.4


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

1.

The maximum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history.

2.

Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE.

3.

The parts replacement shall be documented and the documentation shall be retained for the duration of the unit operating license.

Verify that the service life of hydraulic and mechanical snubbers has not been exceeded or will not be exceeded prior to the next scheduled surveillance inspection.

Each refueling outage

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-9 Technical Requirements (developmental)

AD Table 3.7.3-1 (Page 1 of 1)

Snubber Visual Inspection Acceptance Criteria

1. Visual inspection shall verify that:
a. There are no visible indications of damage or impaired OPERABILITY (See Note 6);
b. Attachments to the foundation or supporting structure are functional; and
c. Fasteners for attachment of the snubber to the component and to the snubber anchorage are functional.
2. Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that:
a. The cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and
b. The affected snubber is functionally tested in the as-found condition and determined OPERABLE per Table 3.7.3-5, Snubber Functional Testing Acceptance Criteria.
3. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable for determining the next inspection interval.
4. Snubbers which have been made inoperable as the result of unexpected transients, isolated damage or other such random events, when the provisions of Table 3.7.3-3 have been met and any other appropriate corrective action implemented, shall not be counted in determining the next visual inspection interval.
5. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.

5.6. Mechanical and hydraulic snubbers are considered OPERABLE (until proven otherwise by functional testing), unless they are disconnected at either end, experienced gross deformation of the snubber or structural support, or the hydraulic fluid level is empty for hydraulic snubbers.

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-10 Technical Requirements (developmental)

A Table 3.7.3-2 (Page 1 of 2)

Snubber Visual Inspection Surveillance Frequency NUMBER OF UNACCEPTABLE SNUBBERS Population or Category (Notes 1 and 2)

Column A Extended Interval (Notes 3 and 6)

Column B Repeat Interval (Notes 4 and 6)

Column C Reduce Interval (Notes 5 and 6) 1 0

0 1

80 0

0 2

100 0

1 4

150 0

3 8

200 2

5 13 300 5

12 25 400 8

18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1:

The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. These categories may be examined separately or jointly. However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.

Note 2:

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

(continued)

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-11 Technical Requirements (developmental)

A Table 3.7.3-2 (Page 2 of 2)

Snubber Visual Inspection Surveillance Frequency Note 3:

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

Note 4:

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

Note 5:

If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.

However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.

Note 6:

The provisions of TSR 3.0.2 are applicable for all inspection intervals up to and including 48 months.

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-12 Technical Requirements (developmental)

A Table 3.7.3-3 (Page 1 of 1)

Snubber Transient Event Inspection

1. An inspection shall be performed of all hydraulic and mechanical snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within six months following such an event.
2. In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using one of the following:
a. Manually induced snubber movement;
b. Evaluation of in-place snubber piston setting; or
c. Stroking the mechanical snubber through its full range of travel.

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-13 Technical Requirements (developmental)

AD Table 3.7.3-4 (Page 1 of 2)

Snubber Functional Testing Plan

1. The representative sample of snubbers shall include each type and shall be tested using Sample Plan A for hydraulic snubbers and Sample Plan B for mechanical snubbers.
2. The NRC Regional Administrator shall be notified in writing of any changes to the sample plan prior to the test period.

SAMPLE PLAN A

1. At least 10% of the total hydraulic snubber population shall be functionally tested either in-place or in a bench test.
2. For each hydraulic snubber of a type that does not meet the functional test acceptance criteria of Table 3.7.3-5, an additional 10% of hydraulic snubbers shall be functionally tested until no more failures are found or until all hydraulic snubbers have been functionally tested.

SAMPLE PLAN B

1. An initial representative sample of 37 mechanical snubbers shall be functionally tested in accordance with Figure 3.7.3-1. For each mechanical snubber type which does not meet the functional test acceptance criteria of Table 3.7.3-5, another sample of at least 19 snubbers shall be tested. The results from this sample plan shall be plotted using an "Accept" line which follows the equation N = 36.49 + 18.18C where C is the number of snubbers which do not meet functional test acceptance criteria. If the point plotted falls on or below the "Accept" line, testing of that type of snubber may be terminated. If the point plotted falls above the "Accept" line, testing must continue until the point falls in the "Accept" region or all mechanical snubbers have been tested.

(continued)

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-14 Technical Requirements (developmental)

AD Table 3.7.3-4 (Page 2 of 2)

Snubber Functional Testing Plan TABLE NOTES

1. Testing equipment failure during functional testing may invalidate that day's testing and allow that day's testing to resume anew at a later time provided all snubbers tested with the failed equipment during the day of equipment failure are retested.
2. The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing. The review shall ensure, as far as practicable, that they are representative of the various configurations, operating environments, range of size, and capacity of snubbers of each type.
3. Snubbers placed in the same location as snubbers which failed the previous functional test shall be retested at the time of the next functional test but shall not be included in the sample plan.
4. If during the functional testing, additional sampling is required due to failure of only one type of snubber, the functional test results shall be reviewed at that time to determine if additional samples should be limited to the type of snubber which has failed the functional testing.
5. Administrative controls are required for snubber removal for functional surveillance testing during plant operating Modes MODES 1 through 4.

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-15 Technical Requirements (developmental)

A Table 3.7.3-5 (Page 1 of 1)

Snubber Functional Testing Acceptance Criteria The snubber functional test shall verify that:

a. Activation (restraining action) is achieved within the specified range in both tension and compression.
b. Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range (Hydraulic Snubbers).
c. The force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel (Mechanical Snubbers).

TABLE NOTES

1. Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.
2. An engineering evaluation shall be made of each failure to meet the functional test criteria to determine the cause of the failure. The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of the type which may be subject to the same failure mode.
3. For snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached. The purpose of this engineering evaluation shall be to determine if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting the designed service.
4. If any snubber selected for functional testing either fails to lock up or fails to move, i.e.,

frozen-in-place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated in Table 3.7.3-4 for snubbers not meeting the functional test acceptance criteria.

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-16 Technical Requirements (developmental)

A 0

1 6

3 4

5 2

30 40 50 100 60 70 80 90 110 120 130 C

Continue testing region N = 36.49 + 18.18C Accept region N

N =

Total number of snubbers tested C =

Number of snubbers which do not meet functional test acceptance criteria FIGURE 3.7.3-1 Sample Plan B for Snubber Functional Test

Isolation Devices TR 3.8.1 Watts Bar - Unit 2 3.8-1 Technical Requirements (developmental)

A TR 3.8 ELECTRICAL POWER SYSTEMS TR 3.8.1 Isolation Devices TR 3.8.1 All circuit breakers actuated by fault currents that are used as isolation devices protecting 1E busses from non-qualified loads shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required circuit breakers inoperable.

A.1 Restore the inoperable circuit breaker(s) to OPERABLE status.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OR A.2.1 Trip or remove the inoperable circuit breaker(s).

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> AND A.2.2 Verify that inoperable circuit breaker(s) are tripped or removed.

Once per 7 days thereafter B.

Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND B.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

Isolation Devices TR 3.8.1 Watts Bar - Unit 2 3.8-2 Technical Requirements (developmental)

BD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.8.1.1


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

1. Molded case circuit breakers selected for functional testing shall be selected on a rotating basis.
2. The functional test shall be conducted by simulating a fault current with an approved test set and verifying that the molded case circuit breaker functions as designed.
3. For each molded-case circuit breaker found inoperable during functional tests, an additional representative sample of 10% of the defective type shall be functionally tested until no more failures are found or all of that type havethat type has been functionally tested.

Perform functional test on representative sample of 10% of each type of molded-case circuit breaker.

18 months TSR 3.8.1.2


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

1. Electrically-operated circuit breakers selected for functional testing shall be selected on a rotating basis.
2. The functional test shall be conducted by simulating a fault current with an approved test set and verifying that each electrically-operated circuit breaker functions as designed.
3. For each electrically-operated circuit breaker found inoperable during functional tests, an additional representative sample of 10% of the defective type shall be functionally tested until no more failures are found or all of that type havethat type has been functionally tested.

Perform functional test on representative sample of 10% of each type of electrically-operated circuit breaker.

18 months (continued)

Isolation Devices TR 3.8.1 Watts Bar - Unit 2 3.8-3 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.8.1.3 Perform a CHANNEL CALIBRATION of associated protective relays for medium voltage circuits (6.9 kV).

18 months TSR 3.8.1.4


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

For each circuit breaker found inoperable during functional tests, an additional representative sample of 10% of the defective type shall be functionally tested until no more failures are found or all of that type havethat type has been functionally tested.

Perform an integrated system functional test on each medium voltage (6.9 kV) breaker which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed.

18 months TSR 3.8.1.5 Inspect each circuit breaker and perform preventive maintenance in accordance with procedures prepared in conjunction with the manufacturer'smanufacturers and EPRI NP-7410-V3, Rev. 1 recommendations for electrically operated breakers and Class 1E MCCB.

72 months

Containment Penetration Conductor Overcurrent Protection Devices TR 3.8.2 Watts Bar - Unit 2 3.8-4 Technical Requirements (developmental)

A TR 3.8 ELECTRICAL POWER SYSTEMS TR 3.8.2. Containment Penetration Conductor Overcurrent Protection Devices TR 3.8.2.

All containment penetration conductor overcurrent protection devices shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more containment penetration conductor overcurrent protection devices inoperable.

A.1 Restore the protective device(s) to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR A.2.1 De-energize the circuit(s) by tripping the associated backup circuit breaker or removing the inoperable circuit breaker.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND A.2.2 Declare the affected system or component inoperable.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND A.2.3 Verify the backup circuit breaker to be tripped or the inoperable circuit breaker removed.

Once per 7 days thereafter (continued)

Containment Penetration Conductor Overcurrent Protection Devices TR 3.8.2 Watts Bar - Unit 2 3.8-5 Technical Requirements (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND B.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> TECHNICAL SURVEILLANCE REQUIREMENTS


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

1. All containment penetration conductor overcurrent protection devices listed in Drawing Series 45A710 (excluding fuses) shall be demonstrated OPERABLE by performance of the following Technical Surveillance Requirements.
2. Technical Surveillance Requirements 3.8.2.1 and 3.8.2.2 apply to at least one 6900-volt reactor coolant pump circuit such that all reactor coolant pump circuits are demonstrated OPERABLE at least once per 72 months.

SURVEILLANCE FREQUENCY TSR 3.8.2.1 Perform a CHANNEL CALIBRATION of associated protective relays for medium voltage circuits (6.9 kV).

18 months (continued)

Containment Penetration Conductor Overcurrent Protection Devices TR 3.8.2 Watts Bar - Unit 2 3.8-6 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.8.2.2


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

For each circuit breaker found inoperable during functional tests, an additional representative sample of 10% of the defective type shall be functionally tested until no more failures are found, or all of that type has been functionally tested.

Perform an integrated system functional test on each medium voltage (6.9 kV) breaker which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed.

18 months TSR 3.8.2.3


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

1. Molded case circuit breakers selected for functional testing shall be selected on a rotating basis.
2. The functional test shall be conducted by simulating a fault current with an approved test set and verifying that each circuit breaker functions as designed.
3. For each molded case circuit breaker found inoperable during functional tests, an additional representative sample of 10% of all the defective type shall be functionally tested until no more failures are found or all of that type have has been functionally tested.

Select and functionally test a representative sample of 10% of each type of molded case circuit breaker.

18 months (continued)

Containment Penetration Conductor Overcurrent Protection Devices TR 3.8.2 Watts Bar - Unit 2 3.8-7 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.8.2.4


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

1. Electrically-operated circuit breakers selected for functional testing shall be selected on a rotating basis.
2. The functional test shall be conducted by simulating a fault current with an approved test set and verifying that each electrically-operated circuit breaker functions as designed.
3. For each electrically-operated circuit breaker found inoperable during functional tests, an additional representative sample of 10% of the defective type shall be functionally tested until no more failures are found or all of that type havethat type has been functionally tested.

Perform functional test on representative sample of 10% of each type of electrically-operated circuit breaker.

18 months TSR 3.8.2.5 Inspect each circuit breaker and perform preventive maintenance in accordance with procedures prepared in conjunction with the manufacturer's and EPRI NP-7410-V3, Rev. 1 recommendations:

1.

For electrically operated breakers and Class 1E MCCB 72 months

2.

For non-Class 1E MCCB.

96 months

Motor-Operated Valves Thermal Overload Bypass Devices TR 3.8.3 Watts Bar - Unit 2 3.8-8 Technical Requirements (developmental)

A TR 3.8 ELECTRICAL POWER SYSTEMS TR 3.8.3 Motor-Operated Valves Thermal Overload Bypass Devices TR 3.8.3 The thermal overload bypass devices integral with the motor starter of each valve listed in Table 3.8.3-1 shall be OPERABLE.

APPLICABILITY:

Whenever the motor-operated valve is required to be OPERABLE.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Thermal overload protection not bypassed when required for one or more of the valves listed in Table 3.8.3-1.

A.1 Restore inoperable device to OPERABLE status.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OR A.2 Provide a means to bypass the thermal overload.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> B.

Required Action and associated Completion Time of Condition A not met.

B.1 Declare the affected valve(s) inoperable.

Immediately AND B.2 Apply the appropriate ACTION statement(s) of the affected system(s).

Immediately TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.8.3.1 Perform TADOT of the bypass circuitry.

18 months

Motor-Operated Valves Thermal Overload Bypass Devices TR 3.8.3 Watts Bar - Unit 2 3.8-9 Technical Requirements (developmental)

B Table 3.8.3-1 (Page 1 of 5)

Motor-Operated Valves Thermal Overload Devices Which Are Bypassed Under Accident Conditions VALVE NO.

FUNCTION 2-FCV-62-63 Isolation for Seal Water Filter 2-FCV-62-90 ECCS Operation 2-FCV-62-91 ECCS Operation 2-FCV-62-61 Containment Isolation 2-LCV-62-132 ECCS Operation 2-LCV-62-133 ECCS Operation 2-LCV-62-135 ECCS Operation 2-LCV-62-136 ECCS Operation 2-FCV-74-1 Open for Normal Plant Cooldown 2-FCV-74-2 Open for Normal Plant Cooldown 2-FCV-74-3 ECCS Operation 2-FCV-74-21 ECCS Operation 2-FCV-74-12 RHR Pump, Minimum flow -- Protects Pump 2-FCV-74-24 RHR Pump, Minimum flow -- Protects Pump 2-FCV-74-33 ECCS Operation 2-FCV-74-35 ECCS Operation 2-FCV-63-7 ECCS Operation 2-FCV-63-6 ECCS Operation 2-FCV-63-156 ECCS Flow Path 2-FCV-63-157 ECCS Flow Path 2-FCV-63-25 BIT Injection 2-FCV-63-26 BIT Injection 2-FCV-63-1 ECCS Operation 2-FCV-63-72 ECCS Flow Path from Containment Sump 2-FCV-63-73 ECCS Flow Path from Containment Sump 2-FCV-63-8 ECCS Flow Path 2-FCV-63-11 ECCS Flow Path (continued)

Motor-Operated Valves Thermal Overload Bypass Devices TR 3.8.3 Watts Bar - Unit 2 3.8-10 Technical Requirements (developmental)

B Table 3.8.3-1 (Page 2 of 5)

Motor-Operated Valves Thermal Overload Devices Which Are Bypassed Under Accident Conditions VALVE NO.

FUNCTION 2-FCV-63-93 ECCS Cooldown Flow Path 2-FCV-63-94 ECCS Cooldown Flow Path 2-FCV-63-172 ECCS Flow Path 2-FCV-63-5 ECCS Flow Path 2-FCV-63-47 Train Isolation 2-FCV-63-48 Train Isolation 2-FCV-63-4 SI Pump Minimum Flow 2-FCV-63-175 SI Pump Minimum Flow 2-FCV-63-3 SI Pump Minimum Flow 2-FCV-63-152 ECCS Recirculation 2-FCV-63-153 ECCS Recirculation 2-FCV-3-33 Quick Closing Isolation 2-FCV-3-47 Quick Closing Isolation 2-FCV-3-87 Quick Closing Isolation 2-FCV-3-100 Quick Closing Isolation 2-FCV-1-15 Steam Supply to Auxiliary FWP Turbine 2-FCV-1-16 Steam Supply to Auxiliary FWP Turbine 2-FCV-3-179A ERCW System Supply to Pump 2-FCV-3-179B ERCW System Supply to Pump 2-FCV-3-136A ERCW System Supply to Pump 2-FCV-3-136B ERCW System Supply to Pump 2-FCV-3-116A ERCW System Supply to Pump 2-FCV-3-116B ERCW System Supply to Pump 2-FCV-3-126A ERCW System Supply to Pump 2-FCV-3-126B ERCW System Supply to Pump 2-FCV-70-133 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-143 Isolation for Excess Letdown Heat Exchanger (continued)

Motor-Operated Valves Thermal Overload Bypass Devices TR 3.8.3 Watts Bar - Unit 2 3.8-11 Technical Requirements (developmental)

BD Table 3.8.3-1 (Page 3 of 5)

Motor-Operated Valves Thermal Overload Devices Which Are Bypassed Under Accident Conditions VALVE NO.

FUNCTION 2-FCV-70-92 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-90 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-87 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-89 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-140 Isolation for RCP Oil Coolers & Therm B 2-FCV-70-134 Isolation for RCP Oil Coolers & Therm B 2-FCV-67-123 CS Heat Exchanger Supply 2-FCV-67-125 CS Heat Exchanger Supply 2-FCV-67-124 CS Heat Exchanger Discharge 2-FCV-67-126 CS Heat Exchanger Discharge 2-FCV-67-146 CCWS CCS Heat Exchanger Throttling 2-FCV-67-83 Containment Isolation Lower 2-FCV-67-88 Containment Isolation Lower 2-FCV-67-87 Containment Isolation Lower 2-FCV-1-51 AFPT Trip and Throttle Valve 2-FCV-67-95 Containment Isolation Lower 2-FCV-67-96 Containment Isolation Lower 2-FCV-67-91 Containment Isolation Lower 2-FCV-67-103 Containment Isolation Lower 2-FCV-67-104 Containment Isolation Lower 2-FCV-67-99 Containment Isolation Lower 2-FCV-67-111 Containment Isolation Lower 2-FCV-67-112 Containment Isolation Lower 2-FCV-67-107 Containment Isolation Lower 2-FCV-67-130 Containment Isolation Lower 2-FCV-67-131 Containment Isolation Lower 2-FCV-67-295 Containment Isolation Lower (continued)

Motor-Operated Valves Thermal Overload Bypass Devices TR 3.8.3 Watts Bar - Unit 2 3.8-12 Technical Requirements (developmental)

B Table 3.8.3-1 (Page 4 of 5)

Motor-Operated Valves Thermal Overload Devices Which Are Bypassed Under Accident Conditions VALVE NO.

FUNCTION 2-FCV-67-134 Containment Isolation Lower 2-FCV-67-296 Containment Isolation Lower 2-FCV-67-133 Containment Isolation Lower 2-FCV-67-139 Containment Isolation Lower 2-FCV-67-297 Containment Isolation Lower 2-FCV-67-138 Containment Isolation Lower 2-FCV-67-142 Containment Isolation Lower 2-FCV-67-298 Containment Isolation Lower 2-FCV-67-141 Containment Isolation Upper 2-FCV-72-21 Containment Spray Pump Suction 2-FCV-72-22 Containment Spray Pump Suction 2-FCV-72-2 Containment Spray Isolation 2-FCV-72-39 Containment Spray Isolation 2-FCV-72-40 RHR Containment Spray Isolation 2-FCV-72-41 RHR Containment Spray Isolation 2-FCV-72-44 Containment Sump to Header A - Containment Spray 2-FCV-72-45 Containment Sump to Header B - Containment Spray 2-FCV-26-240 Containment Isolation 2-FCV-26-243 RCP Containment Spray Isolation 2-FCV-68-332 RCS PRZR Relief 2-FCV-68-333 RCS PRZR Relief 2-FCV-70-153 RHR Heat Exchanger B-B Outlet 2-FCV-70-156 RHR Heat Exchanger A-A Outlet 1-FCV-67-9A ERCW Strainer Backwash 2-FCV-67-9A ERCW Strainer Backwash 1-FCV-67-9B ERCW Strainer Flush 2-FCV-67-9B ERCW Strainer Flush (continued)

Motor-Operated Valves Thermal Overload Bypass Devices TR 3.8.3 Watts Bar - Unit 2 3.8-13 Technical Requirements (developmental)

BD Table 3.8.3-1 (Page 5 of 5)

Motor-Operated Valves Thermal Overload Devices Which Are Bypassed Under Accident Conditions VALVE NO.

FUNCTION 1-FCV-67-10A ERCW Strainer Backwash 2-FCV-67-10A ERCW Strainer Backwash 1-FCV-67-10B ERCW Strainer Flush 2-FCV-67-10B ERCW Strainer Flush 2-FCV-67-89 Containment Isolation 2-FCV-67-97 Containment Isolation 2-FCV-67-105 Lower Containment Isolation 2-FCV-67-113 Lower Containment Isolation 2-FCV-67-143 CCS Heat Exchanger Discharge 0-FCV-67-144 CCS Heat Exchanger Bypass 0-FCV-67-152 CCS Heat Exchanger Discharge 0-FCV-67-205 Nonessential Equipment Isolation 0-FCV-67-208 Station Service/Control Air Supply 2-FCV-70-183 Sample Heat Exchanger Header Outlet 2-FCV-70-100 RCP Oil Cooler Supply Containment Isolation 0-FCV-70-197 SFPCS Heat Exchanger Supply Header 2-FCV-70-215 Sample Heat Exchanger Header Inlet 2-FCV-74-8 RHR Isolation Bypass 2-FCV-74-9 1-FCV-70-153 0-FCV-70-194 1-FCV-67-66 2-FCV-67-66 1-FCV-67-67 2-FCV-67-67 1-FCV-67-143 1-FCV-67-146 RHR Isolation Bypass RHR Heat Exchanger B-B Outlet SFPCS Heat Exchanger Supply Header EDG Heat Exchanger 1A1 & 1A2 Supply EDG Heat Exchanger 2A1 & 2A2 Supply EDG Heat Exchanger 1B1 & 1B2 Supply EDG Heat Exchanger 2B1 & 2B2 Supply CCS Heat Exchanger Discharge CCS Heat Exchanger Throttling

Decay TimeDelete TR 3.9.1 Watts Bar - Unit 2 3.9-1 Technical Requirements (developmental)

AD TR 3.9 REFUELING OPERATIONS TR 3.9.1 Decay TimeDelete TR 3.9.1 The reactor shall be subcritical for > 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

APPLICABILITY:

During movement of irradiated fuel in the reactor vessel.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Reactor subcritical for

< 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

A.1 Suspend all operations involving movement of irradiated fuel in the reactor vessel.

Immediately TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.1.1 Verify the reactor has been subcritical for > 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> by confirming the date and time of subcriticality.

Prior to movement of irradiated fuel in the reactor vessel

Refueling Machine TR 3.9.3 Watts Bar - Unit 2 3.9-3 Technical Requirements (developmental)

A TR 3.9 REFUELING OPERATIONS TR 3.9.3 Refueling Machine TR 3.9.3 The Refueling Machine and Auxiliary Hoist shall be used for movement of fuel assemblies or drive shafts and shall be OPERABLE as follows:

a. The Refueling Machine shall have a capacity of 3150 pounds, and two electrical overload cutoff limits of 2650 pounds and 2800 pounds, respectively.
b. The Auxiliary Hoist shall have a capacity of 1200 pounds and a load indicator shall be used to indicate the lifting of loads > 1190 pounds.

APPLICABILITY:

During movement of fuel assemblies or drive shafts within the reactor pressure vessel.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Refueling Machine inoperable.

A.1 Suspend use of Refueling Machine from operations involving the movement of fuel assemblies within the reactor pressure vessel.

Immediately B.

Auxiliary Hoist inoperable.

B.1 Suspend use of Auxiliary Hoist from operations involving the movement of drive shafts within the reactor pressure vessel.

Immediately

Refueling Machine TR 3.9.3 Watts Bar - Unit 2 3.9-4 Technical Requirements (developmental)

AD TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.3.1 For each required Refueling Machine, perform a load test of 3150 pounds and demonstrate an automatic electrical load cutoff before the crane load is

> 2650 pounds. Demonstrate a second automatic electrical load cutoff before the crane load is

> 2800 pounds.

18 months TSR 3.9.3.2 For each required Auxiliary Hoist and associated load indicator, perform a load test of 1200 pounds.

Within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to start of movement of drive shafts movements within the reactor pressure vessel

Technical Requirements Control Program TR 5.1 Watts Bar - Unit 2 5.0-1 Technical Requirements (developmental)

AD 5.0 ADMINISTRATIVE CONTROLS 5.1 Technical Requirements Control Program This Program provides a means for controlling changes or additions to the Technical Requirements and their Bases.

a.

Introduction TVA has relocated certain information from the Watts Bar Unit 2 Technical Specifications to a separate controlled document based on the Westinghouse Owners Group MERITS Program and the Commissions Interim Policy Statement for improvement of Technical Specifications for nuclear power plants (52 FR 3788 of February 6, 1987). This information is now contained in a separate document called the Watts Bar Unit 2 Technical Requirements Manual (TRM). The following is a description of the administrative program for control, distribution, updating, and amending the information contained in the TRM.

5.1.1 Changes or additions to the Technical Requirements Manual (TRM) shall be made under appropriate administrative controls and reviews.

5.1.2 Licensees may make changes or additions to the TRM without prior NRC approval provided the changes have been determined not to be candidates for inclusion in the Technical Specifications (TS) and not to require NRC approval pursuant to 10 CFR 50.59. The changes to the TRM shall include the following:

a.

Include screening the change against the criteria contained in 10 CFR 50.36(c)(2)(ii).

b.

The change does not require NRC approval pursuant to 10 CFR 50.59.

5.1.3 The Technical Requirements Control Program shall contain provisions to ensure that changes or additions to the TRM are accurately reflected in the FSAR as appropriate.

5.1.4 Proposed changes or additions that do not meet the criteria of 5.1.2 shall be reviewed and approved by the NRC prior to implementation. Changes or additions to the TRM implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).