ML20148H404

Change 97 to Tech Specs D.2 Re ECCS

ML20148H404
Person / Time
Site:	Yankee Rowe
Issue date:	04/14/1972
From:	US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML20148H410	List: ML20148H404
References
NUDOCS 8011180302
Download: ML20148H404 (4)

Text

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ATTACHMENT A Qt J (M

CitANCE No. 97 TO THE TECllNICAL SPECIFICATIONS $

ow LICENSE NO. DPR-3 bi: '

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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would no longer render the reactor 4.37, delta k/k suberitical with the highest worth control rod stuck in the fully withdrawn position."

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2. Replace Section D.2.b. (5) with the following:

"(5) Whenever there is a sustained outage of one of the 115 kV lines because of maintenance or fault condition, the reactor k

power level shall be reduced to a level consistent with p$g ,

three loop operation as defined in (2) above." 4 F8+

3. Replace Sec tions D.2.c. (1), (2) and (3) with the following: (h

"(1) At rated power, F"q, M

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 equivalent full power hours of operation utilizing data derived I fro, core instrumentation, [

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Replace Section D.2.e. (3) and add new Sections D.2.e. (4) and (5) $a as follows: ,j(

"(3) Automatic initiation of the safety injection system, pumps and valves, shall be set "c 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 . }

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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