ML19337A629
| ML19337A629 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck 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 8009290354 | |
| Download: ML19337A629 (5) | |
Text
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O DOCKET No. 50-213 ATTACHMENT 1 HADDAM NECK PLANT PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONS TMI-RELATED REQUIREMENTS
- SEPTEMBER, 1980 0920-oMI;
3.3 REACTOR COOLANT SYSTEM GPERATIONAL COMPONENTS Applicability:
Applies to the operating status of the reactor coolant system.
Objective:
To specify those limiting conditions for operation of the reactor coolant system which must be met to insure safe reactor operation.
Specification:
A.
At least one pressurizer code safety valve shall be in service whenever the reactor is suberitical and the reactor coolant system is above 375 F or 350 psig except during hydrostatic tests.
B.
One or more reactor coolant pumps or the residual heat removal system shall be in operation when changes are made in the boron concentration of the reactor coolant.
C.
The reactor shall not be critical unless the following conditions have been satisfied:
(1) Three self-actuated, spring loaded safety valves, having a combined relieving capability of 720,000 #/hr. shall be in service and shall be in accordance with Section VIII of the ASME Boiler and Pressure Code.
(2) Above 1 percent of Nominal Operating Power Level, at least one reactor coolant pump operating.
(3) Above 10 percent of Nominal Operating Power Level, at least three reactor coolant pumps operating.
(4) Above 65 percent of Nominal Operating Power Level. Four reactor coolant pump operating.
(5) Two steam generators are capable of performing their heat transfer function.
(6) Two power operated relief valves (PORV's) and their associated block valves shall be operable except that:
a.
With one or more PORV(s) i' operable, within n
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s);
otherwise, 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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-o b.
With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s); otherwise, 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 COLD SHUTIDWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
(7) -The pressurtzer shall be operable with at least 150 KW of pressurizer heater capacity.
With the pressurizer inoperable due to a.
the inoperability of both emergency power supplies 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 />. 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 />.
D.
Each steam generator in a non-isolated reactor coolant loop shall be restored to operable status prior to increasing Tave above 200 F.
When starting a reactor coolant pump, and the reactor coolant cold leg temperature in any non-isolated loop is at or below 340 F, the secondary water temperature of each non-isolated steam generator shall not be more than 20 F higher than the water temperature of each of the non-isolated reactor coolant cold legs.
E.
The RCS Overpre1sure Protection System (OPS) shall be in operation when the RCS temperature is below 340 F unless the RCS is-vented through a minimum opening of three (3) inches (nominal diameter) or i
its equivalent.
If one or more of the relief trains is taken out of service and the RC3 is not vented, the following actions shall be taken:
(1) With one relief train inoperable, either restore that train within 7 days, or depressurize and vent the RCS through a minimum 3 inch diameter or equivalent opening within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both relief trains have been restored to operable status.
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(2) With both relief trains inoperable, depressurize and vent the RCS through a minimum 3 inch diameter opening within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both relief l
t' rains have been restored to operable status.
(3) A 30 day report shall be prepared and submitted to the Commission if either actions (1) or (2) are used to mitigate inoperability of one or both relief trains.
i t
B nis:
Eac'n of the pressurizer code safety valves is designed to relieve 240,000 lbs per hr. of saturated steam at the valve set point.
They are described more fully in FDSA Section 5.2.2.
Below 375 F and 350 psig in the reactor' coolant system, the residual heat removal system can remove decay heat and thereby control system temperature and pressure.
If no decay heat were removed by any of the means available, the amount of steam which could be generated at safety valve relief pressure would be less than half the valves' capacity.
One valve
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therefore provides adequate defense against over-pressurization.
i When the boron concentration of the reactor coolant system is to be changed, the process must be uniform to prevent sudden reactivity changes in the reactor. Mixing of the reactor coolant will be sufficient to maintain a uniform boron concentration if at least one reactor coolant pump or one residual heat removal pump is running while the change is taking place. The residual heat removal pump will circulate the primary system volume in approximately one-half hour.
I All pressurizer code safety valves are to be in service prior to criticality to permit the design relieving flow to occur if required.
I Part C of the specification requires that a sufficient i
number of reactor coolant pumps be operating to provide core cooling in the event loss of flow occurs.
The flow provided in each case will keep DNB well above 1.30 ns d'.scussed in FDSA Section 10.3.2.
Therefore, cladding i
damage release of fission products to the reactor coolant cannot occur.
By limiting the temperature differential between the primary and secondary sides to twenty (20) degrees in f
Part D, the resulting pressure transient will be g
crevented by the RCS OPS (See Reference 1) from exceeding the limits in Specification 3.4.
As described in Reference (1), the RCS OPS, in conjunction with administrative controls, prevents exceeding the temperature and pressure limits in Specification 3.4 while RCS temperature is under
o 340 F, Considerations have been incorporated to 0
provide for the inoperability of one or more relief trains (relief valve, motor operated isolation valve, and associated instrumentation) when the RCS ops is required,to ')e operabic.
The power operrted relief valves (PORVs) operate to l
relieve RCS pressure below the setting of the pressurizer l
code safety valves. These relief valves have remotely operated block valves to provide a positive shutoff capability should a relief valve become inoperable.
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The electrical power for both the relief valves and the block valves is capable of being supplled from an emergency power source to ensure the ability I
to seal this possible RCS Icakage path.
l The requirement that (150) kw of pressurizer heaters and their associated controls be capable of being j
supplied electrical power from an emergency bus provides assurance that,these heaters can be energized during a loss of offsite power condition to maintain natural circulation at HOT STANDBY.
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