ML20148H404
| ML20148H404 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 04/14/1972 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20148H410 | List: |
| References | |
| NUDOCS 8011180302 | |
| Download: ML20148H404 (4) | |
Text
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Qt ATTACHMENT A J
(M CitANCE No. 97 TO THE TECllNICAL SPECIFICATIONS ow bi:
LICENSE NO. DPR-3 I
3 (d.
s YANKEE ATOMIC ELECTRIC COMPANY
),1 7 _.
DOCKET NO. 50-29 1.
Replace Sections D.2.a. (3) and (4) with the following:
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"(3)
At all times when the reactor is at operating temperature except for low power physics testing, sufficient boric acid shall be present in the main coolant system such J
that the reactor is not less than 4.3% delt.a k/k subcritical E
with the highest worth control rod stuck in the fully with-P.
drawn position.
"(4)
Sufficient boric acid will be added to the main coolant systen prior to cold shutdown to maintain the cold core p
with all control rods inserted at least 5*/. delta k/k suberitical.
Except for low power physics testing, this will be done before the temperature of the main coolant k
syste-has been reduced to a point where full insertion I
of all control rods would no longer render the reactor 4.37, delta k/k suberitical with the highest worth control h
rod stuck in the fully withdrawn position."
y 2.
Replace Section D.2.b. (5) with the following:
"(5)
Whenever there is a sustained outage of one of the 115 kV k
p$
lines because of maintenance or fault condition, the reactor power level shall be reduced to a level consistent with three loop operation as defined in (2) above."
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3.
Replace Sec tions D.2.c. (1), (2) and (3) with the following:
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"(1)
At rated power, F"q, the nuclear heat flux hot channel factor, f*
for the hottest point in the hottest channel shall not exceed 2.74 for zircaloy clad assemblies and 3.11 for stainless steci clad assemblics.
This value shall be checked every 1000 I[
equivalent full power hours of operation utilizing data derived fro, core instrumentation, t
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Replace Section D.2.e. (3) and add new Sections D.2.e. (4) and (5)
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as follows:
"(3)
Automatic initiation of the safety injection system, pumps and "c,
valves, shall be set to operate at a main coolant pressure not
.ldt less than 1700 psig.
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"(4) The minimum nitrogen overpressure on the Low Pressure Safety Injection Accumulator shall be 410 psig, j
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"(5) The Safety Injection System shall be maintained in
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readiness to inject borated water into the reactor l
at all times when the main coolant prei,aure is l
1000 psig or higher."
i 7.
Replace Table I " Reactor Protection Set Points" with the attached f
revised Table I.
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