ML19337A659
| ML19337A659 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck, Millstone File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/30/1980 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML19337A626 | List: |
| References | |
| TASK-2.E.1.1, TASK-2.E.1.2, TASK-TM TAC-11733, NUDOCS 8009290381 | |
| Download: ML19337A659 (2) | |
Text
.
O REACTOR COOLANT SYSTEM 3/4.4.4 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.4 The pressurizer shall be OPERABLE with a steam bubble and at least 130 kw of pressurizer heater capacity.
APPLICABILITY: MODES 1, 2, AND 3.
ACTION:
A.
With the pressurizer inoperable due to an inoperable emergency power supply to the pressurizer heaters either restore the inoperable emergency power supply within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
B.
With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the reactor trip breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in the HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.4.1 The pressurizer water volume shall be determined to be within its limit once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
MILLSTONE - UNIT 2 Jl4 4-4 8 0 0 9 2 9 03F/,
~
^
Pay 17, 1970 REACTOR COOLANT SYSTEM
?
BASES Dur' ng operation, all pressurizer code safety valves rest be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2750 The combined relief capacity of these valves is sufficient to psia.
limit the Reactor Coolant System pressure to within its Safety Limit of 2750 psia following a complete loss of turbine generator load while operating at RATED THERMAL POWER and assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e., no credit is taken for a direct reactor trip on the loss of turbine) and also assuming no operation of the pressurizer power operated relief valve or steam dump valves.
The power operated relief valves (PORVs) operate to relieve RCS pressure These relief valves below the setting of the pressurizer code safety valves.
have remotely operated block valves to provide a positive shutoff capability The electrical power for both the should a relief valve become inoperable.
relief valves and the block valves is capable of being supplied from an emergency power source to ense-e Ehe ability to seal this possible RCS leakage path.
3/4.4.4 PRESSURIZER A steam bubble in the pressurizer ensures that the RCS is not a hydraulically solid system and is capable of accommodating pressureThe surges during operation.
code safety valves and power operated relief valve against water relief.
The power operated relief valve and steam b'ubble function to relieve RCS Operation of the power operated pressure during all design transients.
relief valve in conjunction with a reactor trip on a Pressurizer--
Pressure-High signal, minimizes the undesirable opening of the spring-loaded pressurizer code safety valves.
The requirement that 130 kw of pressurizer heaters and their associated controls be capable of being supplied electrical power from an e:e.ergency b provides assurance that these heaters can be energized during a loss of offsite power condition to maintain natural circulation at HOT STANDBY.
i l
MILLSTONE - UNIT 2 8 3/4 4-2
_