Text

Developmental Revision B - Technical Specifications 3.4 - Reactor Coolant System
	ML100550453
Person / Time
Site:	Watts Bar
Issue date:	02/02/2010
From:	; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML100550453 (0)
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RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 Watts Bar - Unit 2 3.4-1 (developmental)

A 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

a.

Pressurizer pressure 2214 psig;

b.

RCS average temperature 593.2°F; and

c.

RCS total flow rate 380,000 gpm (process computer or control board indication).

APPLICABILITY:

MODE 1.

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

Pressurizer pressure limit does not apply during:

a.

THERMAL POWER ramp > 5% RTP per minute; or

b.

THERMAL POWER step > 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS DNB parameters not within limits.

A.1 Restore RCS DNB parameter(s) to within limit.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. Required Action and associated Completion Time not met.

B.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 Watts Bar - Unit 2 3.4-2 (developmental)

B SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is 2214 psig.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.2 Verify RCS average temperature is 593.2°F.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.3 Verify RCS total flow rate is 380,000 gpm (process computer or control board indication).

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.4

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

Required to be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 90% RTP.

Verify by precision heat balance method that RCS total flow rate is 380,000 gpm.

18 months

RCS Minimum Temperature for Criticality 3.4.2 Watts Bar - Unit 2 3.4-3 (developmental)

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

APPLICABILITY:

MODE 1, MODE 2 with keff 1.0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tavg in one or more RCS loops not within limit.

A.1 Be in MODE 3.

30 minutes SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each loop 551°F.

NOTE---------

Only required if Tavg - Tref deviation alarm not reset and any RCS loop Tavg < 561°F.

30 minutes

RCS P/T Limits 3.4.3 Watts Bar - Unit 2 3.4-4 (developmental)

A 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in the PTLR.

APPLICABILITY:

At all times.

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

Required Action A.2 shall be completed whenever this Condition is entered.

Requirements of LCO not met in MODE 1, 2, 3, or 4.

A.1 Restore parameter(s) to within limits 30 minutes AND A.2 Determine RCS is acceptable for continued operation.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND B.2 Be in MODE 5 with RCS pressure < 500 psig 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. -----------NOTE-----------------

Required Action C.2 shall be completed whenever this Condition is entered.

Requirements of LCO not met any time in other than MODE 1, 2, 3, or 4.

C.1 Initiate action to restore parameter(s) to within limits.

Immediately AND C.2 Determine RCS is acceptable for continued operation.

Prior to entering MODE 4

RCS P/T Limits 3.4.3 Watts Bar - Unit 2 3.4-5 (developmental)

A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1

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

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

Verify RCS pressure, RCS temperature, and RCS heatup and cooldown rates are within the limits specified in the PTLR.

30 minutes

RCS Loops - MODES 1 and 2 3.4.4 Watts Bar - Unit 2 3.4-6 (developmental)

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

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of LCO not met.

A.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation.

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

RCS Loops - MODE 3 3.4.5 Watts Bar - Unit 2 3.4-7 (developmental)

A 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops - MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE, and either:

a.

Two RCS loops shall be in operation when the Rod Control System is capable of rod withdrawal; or

b.

One RCS loop shall be in operation when the Rod Control System is not capable of rod withdrawal.

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

All reactor coolant pumps may be de-energized for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a.

No operations are permitted that would cause reduction of the RCS boron concentration; and

b.

Core outlet temperature is maintained at least 10°F below saturation temperature.

APPLICABILITY:

MODE 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop inoperable.

A.1 Restore required RCS loop to OPERABLE status 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and associated Completion Time of Condition A not met B.1 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

RCS Loops - MODE 3 3.4.5 Watts Bar - Unit 2 3.4-8 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One required RCS loop not in operation, and reactor trip breakers closed and Rod Control System capable of rod withdrawal.

C.1 Restore required RCS loop to operation.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR C.2 De-energize all control rod drive mechanisms (CRDMs).

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D. All RCS loops inoperable.

OR No RCS loop in operation.

D.1 De-energize all CRDMs.

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

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

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loops are in operation 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.5.2 Verify steam generator secondary side water levels are 6% narrow range for required RCS loops.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.5.3 Verify correct breaker alignment and indicated power are available to the required pump that is not in operation.

7 days

RCS Loops - MODE 4 3.4.6 Watts Bar - Unit 2 3.4-9 (developmental)

B 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops - MODE 4 LCO 3.4.6 Two loops shall be OPERABLE, and consist of either:

a.

Any combination of RCS loops and residual heat removal (RHR) loops, and one loop shall be in operation, when the rod control system is not capable of rod withdrawal; or

b.

Two RCS loops, and both loops shall be in operation, when the rod control system is capable of rod withdrawal.

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

No RCP shall be started with any RCS cold leg temperature the COMS arming temperature specified in the PTLR unless the secondary side water temperature of each steam generator (SG) is 50°F above each of the RCS cold leg temperatures.

APPLICABILITY:

MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Only one RCS loop OPERABLE.

AND Two RHR loops inoperable.

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

AND No RCS loops OPERABLE.

B.1 Be in MODE 5.

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

RCS Loops - MODE 4 3.4.6 Watts Bar - Unit 2 3.4-10 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One required RCS loop not in operation, and reactor trip breakers closed and Rod Control System capable of rod withdrawal.

C.1 Restore required RCS loop to operation.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR C.2 De-energize all control rod drive mechanisms (CRDMs).

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D. Required RCS or RHR loops inoperable.

OR No required RCS or RHR loop in operation D.1 De-energize all CRDMs.

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

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

Immediately

RCS Loops - MODE 4 3.4.6 Watts Bar - Unit 2 3.4-11 (developmental)

A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify two RCS loop are in operation when the rod control system is capable of rod withdrawal.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.6.2 Verify one RHR or RCS loop is in operation when the rod control system is not capable of rod withdrawal.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.6.3 Verify SG secondary side water levels are greater than or equal to 6% narrow range for required RCS loops.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.6.4 Verify correct breaker alignment and indicated power are available to the required pump that is not in operation.

7 days

RCS Loops - MODE 5, Loops Filled 3.4.7 Watts Bar - Unit 2 3.4-12 (developmental)

B 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops - MODE 5, Loops Filled LCO 3.4.7 One residual heat removal (RHR) loop shall be OPERABLE and in operation, and either:

a.

One additional RHR loop shall be OPERABLE; or

b.

The secondary side water level of at least two steam generators (SGs) shall be greater than or equal to 6% narrow range.

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

1.

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

2.

No reactor coolant pump shall be started with one or more RCS cold leg temperatures the COMS arming temperature specified in the PTLR unless the secondary side water temperature of each SG is 50°F above each of the RCS cold leg temperatures.

3.

All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY:

MODE 5 with RCS loops filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop inoperable.

AND Required SGs secondary side water levels not within limits.

A.1 Initiate action to restore a second RHR loop to OPERABLE status Immediately OR A.2 Initiate action to restore required SG secondary side water levels to within limits Immediately (continued)

RCS Loops - MODE 5, Loops Filled 3.4.7 Watts Bar - Unit 2 3.4-13 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required RHR loops inoperable.

OR No RHR loop in operation.

B.1 Suspend all operations involving a reduction of RCS boron concentration.

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

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one RHR loop is in operation.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.7.2 Verify SG secondary side water level is greater than or equal to 6% narrow range in required SGs.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.7.3 Verify correct breaker alignment and indicated power are available to the required RHR pump that is not in operation 7 days

RCS Loops - MODE 5, Loops Not Filled 3.4.8 Watts Bar - Unit 2 3.4-14 (developmental)

A 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops - MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.

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

1.

All RHR pumps may be de-energized for 15 minutes when switching from one loop to another provided:

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

b. No operations are permitted that would cause a reduction of the RCS boron concentration; and

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

2.

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

APPLICABILITY:

MODE 5 with RCS loops not filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop inoperable.

A.1 Initiate action to restore RHR loop to OPERABLE status.

Immediately (continued)

RCS Loops - MODE 5, Loops Not Filled 3.4.8 Watts Bar - Unit 2 3.4-15 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required RHR loops inoperable.

OR No RHR loop in operation.

B.1 Suspend all operations involving reduction in RCS boron concentration Immediately AND B.2 Initiate action to restore one RHR loop to OPERABLE status and operation Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR loop is in operation.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.8.2 Verify correct breaker alignment and indicated power are available to the required RHR pump that is not in operation.

7 days

Pressurizer 3.4.9 Watts Bar - Unit 2 3.4-16 (developmental)

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

a.

Pressurizer water level 92%; and

b.

Two groups of pressurizer heaters OPERABLE with the capacity of each group 150 kW APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water level not within limit.

A.1 Be in MODE 3 with reactor trip breakers open.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND A.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B. One required group of pressurizer heaters inoperable.

B.1 Restore required group of pressurizer heaters to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Required Action and associated Completion Time of Condition B not met.

C.1 Be in MODE 3 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND C.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Pressurizer 3.4.9 Watts Bar - Unit 2 3.4-17 (developmental)

A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is 92%.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.9.2 Verify capacity of each required group of pressurizer heaters is 150 kW.

92 days

Pressurizer Safety Valves 3.4.10 Watts Bar - Unit 2 3.4-18 (developmental)

B 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Three pressurizer safety valves shall be OPERABLE with lift settings 2410 psig and 2560 psig.

APPLICABILITY:

MODES 1, 2, and 3.

MODE 4 with all RCS cold leg temperatures > the COMS arming temperature specified in the PTLR.

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

The lift settings are not required to be within the LCO limits during MODE 3 and MODE 4 with all RCS cold leg temperatures > the COMS arming temperature specified in the PTLR for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety valve inoperable.

A.1 Restore valve to OPERABLE status.

15 minutes B. Required Action and associated Completion Time not met.

OR Two or more pressurizer safety valves inoperable.

B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND B.2 Be in MODE 4 with any RCS cold leg temperature

< the COMS arming temperature specified in the PTLR.

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

Pressurizer Safety Valves 3.4.10 Watts Bar - Unit 2 3.4-19 (developmental)

A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE in accordance with the Inservice Testing Program.

Following testing, lift settings shall be within +/- 1% of the nominal lift setting of 2485 psig.

In accordance with the Inservice Testing Program

Pressurizer PORVs 3.4.11 Watts Bar - Unit 2 3.4-20 (developmental)

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

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

APPLICABILITY:

MODES 1, 2, and 3 ACTIONS

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

Separate Condition entry is allowed for each PORV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs inoperable and capable of being manually cycled.

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

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

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND B.3 Restore PORV to OPERABLE status 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (continued)

Pressurizer PORVs 3.4.11 Watts Bar - Unit 2 3.4-21 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve inoperable C.1 Place associated PORV in manual control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND C.2 Restore block valve to OPERABLE status 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND D.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Two PORVs inoperable and not capable of being manually cycled E.1 Close associated block valves.

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

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND E.3 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND E.4 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. Two block valves inoperable F.1 Place associated PORVs in manual control.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND F.2 Restore one block valve to OPERABLE status.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (continued)

Pressurizer PORVs 3.4.11 Watts Bar - Unit 2 3.4-22 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and associated Completion Time of Condition F not met.

G.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND G.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1

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

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

Perform a complete cycle of each block valve.

92 days SR 3.4.11.2 Perform a complete cycle of each PORV.

18 months

COMS 3.4.12 Watts Bar - Unit 2 3.4-23 (developmental)

B 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Cold Overpressure Mitigation System (COMS)

LCO 3.4.12 A COMS System shall be OPERABLE with a maximum of one charging pump and no safety injection pump capable of injecting into the RCS and the accumulators isolated and either a or b below.

a.

Two RCS relief valves, as follows:

1. Two power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR, or

2. One PORV with a lift setting within the limits specified in the PTLR and the RHR suction relief valve with a setpoint 436.5 psig and 463.5 psig.

b.

The RCS depressurized and an RCS vent capable of relieving >

475 gpm water flow.

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

1.

Two charging pumps may be made capable of injecting for less than or equal to one hour for pump swap operations.

2.

Accumulator may be unisolated when accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.

APPLICABILITY:

MODE 4 with any RCS cold leg temperature < the COMS arming temperature specified in the PTLR, MODE 5, and MODE 6 when the reactor vessel head is on

COMS 3.4.12 Watts Bar - Unit 2 3.4-24 (developmental)

B ACTIONS

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

LCO 3.0.4.b is not applicable when entering MODE 4.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more safety injection pumps capable of injecting into the RCS.

A.1 Initiate action to verify no safety injection pumps are capable of injecting into the RCS.

Immediately B. Two or more charging pumps capable of injecting into the RCS.

B.1 Initiate action to verify a maximum of one charging pump is capable of injecting into the RCS.

Immediately C. An accumulator not isolated when the accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

C.1 Isolate affected accumulator.

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

D.1 Increase RCS cold leg temperature to > the COMS arming temperature specified in the PTLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR D.2 Depressurize affected accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

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

COMS 3.4.12 Watts Bar - Unit 2 3.4-25 (developmental)

B (continued)

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One required RCS relief valve inoperable in MODE 4 with any RCS cold leg temperature < the COMS arming temperature specified in the PTLR.

E.1 Restore required RCS relief valve to OPERABLE status.

7 days F. One required RCS relief valve inoperable in MODE 5 or 6.

F.1 Restore required RCS relief valve to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months G. Two required RCS relief valves inoperable.

OR Required Action and associated Completion Time of Condition A, B, D, E, or F not met.

OR COMS inoperable for any reason other than Condition A, B, C, D, E, or F.

G.1 Depressurize RCS and establish RCS vent.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

COMS 3.4.12 Watts Bar - Unit 2 3.4-26 (developmental)

A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify no safety injection pumps are capable of injecting into the RCS.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entering MODE 4 from MODE 3 prior to the temperature of one or more RCS cold legs decreasing below 325°F.

AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter SR 3.4.12.2 Verify a maximum of one charging pump is capable of injecting into the RCS.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entering MODE 4 from MODE 3 prior to the temperature of one or more RCS cold legs decreasing below 325°F.

AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter SR 3.4.12.3 Verify each accumulator is isolated.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.12.4

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

Only required to be performed when complying with LCO 3.4.12.b.

Verify RCS vent open.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for unlocked open vent paths AND 31 days for locked open vent paths (continued)

COMS 3.4.12 Watts Bar - Unit 2 3.4-27 (developmental)

B SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.5 Verify PORV block valve is open for each required PORV.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months SR 3.4.12.6 Verify both RHR suction isolation valves are locked open with operator power removed for the required RHR suction relief valve.

31 days SR 3.4.12.7

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

Required to be met within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after decreasing RCS cold leg temperature to the COMS arming temperature specified in the PTLR.

Perform a COT on each required PORV, excluding actuation.

31 days SR 3.4.12.8 Perform CHANNEL CALIBRATION for each required PORV actuation channel.

18 months

RCS Operational LEAKAGE 3.4.13 Watts Bar - Unit 2 3.4-28 (developmental)

A 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a.

No pressure boundary LEAKAGE;

b.

1 gpm unidentified LEAKAGE;

c.

10 gpm identified LEAKAGE; and

d.

150 gallons per day primary-to-secondary LEAKAGE through any one steam generator (SG).

APPLICABILITY:

MODES 1, 2, 3, and 4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational LEAKAGE not within limits for reasons other than pressure boundary LEAKAGE or primary-to-secondary LEAKAGE.

A.1 Reduce LEAKAGE to within limits.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and associated Completion Time of Condition A not met.

OR Pressure boundary LEAKAGE exists.

OR Primary-to-secondary LEAKAGE not within limit.

B.1 Be in MODE 3.

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

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

RCS Operational LEAKAGE 3.4.13 Watts Bar - Unit 2 3.4-29 (developmental)

A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1

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

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

2. Not applicable to primary-to-secondary LEAKAGE.

Verify RCS operational LEAKAGE is within limits by performance of RCS water inventory balance.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months SR 3.4.13.2

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

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

Verify primary-to-secondary LEAKAGE is less than or equal to 150 gallons per day through any one SG.

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

RCS PIV Leakage 3.4.14 Watts Bar - Unit 2 3.4-30 (developmental)

A 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 Leakage from each RCS PIV shall be within limit.

APPLICABILITY:

MODES 1, 2, and 3, MODE 4, except valves in the residual heat removal (RHR) flow path when in, or during the transition to or from, the RHR mode of operation.

ACTIONS

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

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths with leakage from one or more RCS PIVs not within limit.

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

Each valve used to satisfy Required Action A.1 must have been verified to meet SR 3.4.14.1 and be in the reactor coolant pressure boundary.

A.1 Isolate the high pressure portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (continued)

RCS PIV Leakage 3.4.14 Watts Bar - Unit 2 3.4-31 (developmental)

A ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

AND A.2 Restore RCS PIV to within limits 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and associated Completion Time for Condition A not met.

B.1 Be in MODE 3.

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

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

RCS PIV Leakage 3.4.14 Watts Bar - Unit 2 3.4-32 (developmental)

A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1

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

1. Not required to be performed in MODES 3 and 4.

2. Not required to be performed on the RCS PIVs located in the RHR flow path when in the shutdown cooling mode of operation.

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

Verify leakage from each RCS PIV is equivalent to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure 2215 psig and 2255 psig.

In accordance with the Inservice Testing Program, and 18 months AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months AND Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve

RCS Leakage Detection Instrumentation 3.4.15 Watts Bar - Unit 2 3.4-33 (developmental)

B 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

1. One containment pocket sump level monitor; and

2. One lower containment atmosphere particulate radioactivity monitor.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required containment pocket sump level monitor inoperable.

A.1 Perform SR 3.4.13.1.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND A.2 Restore required containment pocket sump level monitor to OPERABLE status.

30 days B. Required containment atmosphere particulate radioactivity monitor inoperable.

B.1.1 Analyze grab samples of the containment atmosphere.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR B.1.2 Perform SR 3.4.13.1.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.2 Restore required containment atmosphere particulate radioactivity monitor to OPERABLE status.

30 days (continued)

RCS Leakage Detection Instrumentation 3.4.15 Watts Bar - Unit 2 3.4-34 (developmental)

B ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time not met.

C.1 Be in MODE 3.

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

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. All required monitors inoperable.

D.1 Enter LCO 3.0.3.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required containment atmosphere particulate radioactivity monitor.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.15.2 Perform COT of the required containment atmosphere particulate radioactivity level monitor.

92 days SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required containment pocket sump level monitor.

18 months SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required containment atmosphere particulate radioactivity monitor.

18 months

RCS Specific Activity 3.4.16 Watts Bar - Unit 2 3.4-35 (developmental)

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

APPLICABILITY:

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT I-131

> 0.265 Ci/gm.

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

LCO 3.0.4.c is applicable.

A.1 Verify DOSE EQUIVALENT I-131 21 Ci/gm.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND A.2 Restore DOSE EQUIVALENT I-131 to within limit.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months B. Gross specific activity of the reactor coolant not within limit.

B.1 Perform SR 3.4.16.2.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND B.2 Be in MODE 3 with Tavg < 500°F.

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

RCS Specific Activity 3.4.16 Watts Bar - Unit 2 3.4-36 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A not met.

OR DOSE EQUIVALENT I-131

> 21 Ci/gm.

C.1 Be in MODE 3 with Tavg < 500°F.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant gross specific activity

< 100/E Ci/gm.

7 days SR 3.4.16.2

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

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT I-131 specific activity 0.265 Ci/gm.

14 days AND Between 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period (continued)

RCS Specific Activity 3.4.16 Watts Bar - Unit 2 3.4-37 (developmental)

A SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.16.3

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

Required to be performed within 31 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Determine from a sample taken in MODE 1 after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

184 days

SG Tube Integrity 3.4.17 Watts Bar - Unit 2 3.4-38 (developmental)

A 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 Steam Generator (SG) Tube Integrity LCO 3.4.17 SG tube integrity shall be maintained AND All SG tubes satisfying the tube repair criteria shall be plugged in accordance with the Steam Generator Program.

APPLICABILITY:

MODES 1, 2, 3, and 4 ACTIONS

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

Separate Condition entry is allowed for each SG tube.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes satisfying the tube repair criteria and not plugged in accordance with the Steam Generator Program A.1 Verify tube integrity of the affected tube(s) is maintained until the next refueling outage or SG tube inspection 7 days AND A.2 Plug the affected tube(s) in accordance with the Steam Generator Program Prior to entering MODE 4 following the next refueling outage or SG tube inspection B. Required Action and associated Completion Time of Condition A not met OR SG tube integrity not maintained B.1 Be in MODE 3.

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

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

SG Tube Integrity 3.4.17 Watts Bar - Unit 2 3.4-39 (developmental)

A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify steam generator tube integrity in accordance with the Steam Generator Program.

In accordance with the Steam Generator Program SR 3.4.17.2 Verify that each inspected SG tube that satisfies the tube repair criteria is plugged in accordance with the Steam Generator Program.

Prior to entering MODE 4 following a SG tube inspection

ML100550453

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