ML20010H338
| ML20010H338 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/17/1981 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20010H335 | List: |
| References | |
| NUDOCS 8109240358 | |
| Download: ML20010H338 (3) | |
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i DOCKET NO. 50-213 i
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i ATTACHMENT 1 i
i 4-I HADDAM NECK PLANT PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONS I
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,t SEPTEMBER, 1981 4
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8109240358 8109 7 POR ADOCK 057.0 i
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b.
Reactor Coolant Loop (2) and its associated steam generator and reactor coolant pump, c.
Reactor Coo! at Loop (3) and its associated steam generator and reactor coolant pump.
d.
Reactor Coolant Loop (4) and its associated hteam generator and reactor coolant pump, e.
Residual Heat Removal Loop (A)**
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Residual Heat Removal Loop (B)**
2.
At least one of the above coolant loops shall be in operation.***
a.
With less than the above reqcfred loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible; be in COLD SHUIDOWN within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
b.
With no coolant. loop in operation, suspend all oper.ations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.
H.
During the 1981 refueling outage with the reactor plant in Mode 3 and passing into Mode 4 the pro-visions of specification 3.3 F 2 and 3.3 G 2 need not be met for the purpose of demonstrating natural circulation cooldown and operator training in this aspect of operation.
Operating in this mode under the provisions of this paragraph will be performed in accordance with a Plant Operations Review Committee (PORC) approved procedure.
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As described in Reference (1), the RCS H 3, in-conjuction wito administrative controls, prevents c~;:eeding the temperature and pressure limits in Specification 3.4
.while RCS temperature is under 3400F Considerations have been incorporated to provide for the inoperability of one or mcre relief trains (relief valve, motor operated isolation valve, and associated instrumentation) when the RCS OPS is required to be operable.
In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removi g decay. heat; however, single failure considerations require that two loops be OPERABLE.
In MODES 4 and 5, a single' reactor coolant loop or RHR loop -
provides sufficient heat removal capability _for' removing decay heat; but-single failure considerations require that at least two loops be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE, this specification requires'two RHR loops to be OPERABLE.
The operation of one Reactor Coolant Pump or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron.
concentration reductions in the Reactor Coolant System.
The reactivity change rate associated with boron reduction-will, therefore, be within the capability of operator recognition and control.
The provisions of specification 3.3.H are desirable on a one time basis for ~ the purpose of demonstrating 'the reactor's ability to transfer decay heat and be cooled down while in natural circulation.
Since at_least two coolant loops will be available and since this procedure is a plant.ed maneuver, there is no undue hazard to the plant or public safety.
Reference (1) D. C. Switzer letter to A. Schwencer, dated September 7, 1977.
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