ML100550623
| ML100550623 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar |
| Issue date: | 02/02/2010 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML100550623 (12) | |
Text
Safety Valves, Shutdown TR 3.4.1 Watts Bar - Unit 2 3.4-1 Technical Requirements (developmental)
A TR 3.4 REACTOR COOLANT SYSTEM (RCS)
TR 3.4.1 Safety Valves, Shutdown TR 3.4.1 One pressurizer Code safety valve shall be OPERABLE with a lift setting of 2410 psig and 2560 psig.
NOTE----------------------------------------------
The lift setting is not required to be within the TR limit during MODES 4 and 5 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for entry and operation into and exit from MODES 4 and 5 provided a preliminary cold setting was made prior to heatup.
APPLICABILITY:
MODES 4 and 5.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
No pressurizer Code safety valve OPERABLE.
A.1 Suspend all operations involving positive reactivity changes.
Immediately AND A.2 Place an OPERABLE Residual Heat Removal (RHR) loop into operation in the shutdown cooling mode.
Immediately
Safety Valves, Shutdown TR 3.4.1 Watts Bar - Unit 2 3.4-2 Technical Requirements (developmental)
A TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.1.1 Verify the required pressurizer safety valve 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 Temperature Limits TR 3.4.2 Watts Bar - Unit 2 3.4-3 Technical Requirements (
developmental)
A TR 3.4 REACTOR COOLANT SYSTEM (RCS)
TR 3.4.2 Pressurizer Temperature Limits TR 3.4.2 The pressurizer temperature shall be limited to:
- a. Heatup of 100°F in any 1-hour period, and
- b. Cooldown of 200°F in any 1-hour period.
APPLICABILITY:
At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
NOTE---------------
All Required Actions must be completed whenever this Condition is entered.
Pressurizer temperature not within limits.
A.1 Restore pressurizer temperature to within limits.
30 minutes AND A.2 Perform engineering evaluation to determine effects of the out-of-limit condition on the structural integrity of the pressurizer.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND A.3 Determine that the pressurizer remains acceptable for continued operation.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
Pressurizer Temperature Limits TR 3.4.2 Watts Bar - Unit 2 3.4-4 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 Reduce pressurizer pressure to < 500 psig.
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 3.4.2.1
NOTE------------------------------
Only required during system heatup or cooldown operations.
Determine that pressurizer temperatures are within limits.
30 minutes
RCS Vents TR 3.4.3 Watts Bar - Unit 2 3.4-5 Technical Requirements (
developmental)
A TR 3.4 REACTOR COOLANT SYSTEM (RCS)
TR 3.4.3 RCS Vents TR 3.4.3 Two Reactor Coolant System Vent (RCSV) paths shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One RCSV path inoperable.
A.1 Initiate action to maintain the affected RCSV 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 paths inoperable.
B.1 Restore one RCSV 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 />
RCS Vents TR 3.4.3 Watts Bar - Unit 2 3.4-6 Technical Requirements (
developmental)
A TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.3.1 Verify that the upstream manual RCSV isolation valves are 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 paths during venting.
18 months
Chemistry TR 3.4.4 Watts Bar - Unit 2 3.4-7 Technical Requirements (
developmental)
A 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)
A 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)
A 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 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)
A 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 are in accordance with the Inservice Inspection Program.
In accordance with the Inservice Inspection Program