ML19343A545
| ML19343A545 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/29/1972 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Vandenburg D YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8011140582 | |
| Download: ML19343A545 (3) | |
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DISTRIBUTION t.
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H. Shaprr, OGC d
N. Dube, DRL (5) g j J. Buchanan, ORNL 6 /.
FEB 2 91972 T. Laughlin, DTIE 2.l P
.i LA'ocket File Imket ::o. 50-29 DRL Reading
'H Branch Reading c.,[ll i
R. Boyd R. DeYoung f
Yankee Atomic Electric company ACRS (16),7IO.,
k ATTH: lir. Donald E. Vandenburg Vice ? resident D. Skovholt, A. Burger
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'estborour.h,l'assachusetts 015S1 R. Schemel, S. Teers Change No. 95 W
License ::o. D?R-3 sh Gen:.le=:n:
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.c Your letter of August 30, 1971, in response to our letter of July 20, 1971 Ft.
proposed that an additional specification be added to the Technical Spec-k k ifications appended to License No. DPR-3 for the Yankee reactor. The pro-f Rf posed change to the Technical Specifications would require surveillance of Icakage fren the prir.:ary cooling syste:a for the reactor.
h M.e During our evaluation of the proposed change, we found that it must be codified to include limiting conditions for operation. This modification, U.iich we have discussed with your staff, is necessary to rect our licensing requirements. We conclude that the proposed change, as modified, dcas not y
present significant harards conside. cations not described or implicit in the g
t:fety Analysis report and that the.c is reasonable assurance that the health gj and safety of the public vi".~
not be endangered.
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'e have designated the pror.ased change, as nodified, c: Chcnge ::o. 96.
gg rursuant to 10 CF:t 50.59,.:hange Fo. 96 as defined in Attachment A to this d's letter is hereby autho urca.
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Sincerely, 4$1 a
Donald J. Shovholt K.
Assistant D. rector for Rent.cor Operations y
Division of Reactor Licensing y.
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Enclosure:
,. c w Attcchont A - Change to the fg rechnicc1 specifications W:
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C. Dunne Blinn, Esquire Day, Herry & Heuard n.,p b
Counselors at Law
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[I OS 1 cnetitution Plar.a e.m I:crt! ford, Connectimt 06103
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t ATTACINENT A I.
' CHANGE NO. 96 TO THE TECHNICAL SPECIFICATIONS.
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LICENSE NO. DPR-3
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JANKEE ATOMIC ELECTRIC COMPANY-k.
DOCKET NO. 50-29 74t Under Specification D.2.d, add the following:
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(13) When the reactor is at power, a water inventory deter-L mination shall be performed at least once during each k-24-hour period for the purpose of calculating main
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coolant leakage from the primary system.
If the leak 4
rate -exceeds 1 gpm and if the source of-leakage is p
unidentified, the reactor shall be shut down and cool-O down shall be initiated within 12 ' hours.
If the source E
of leakage is identified and if the source is from I
valve packings, instrument fittings or similar primary
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n system boundaries not indicative of major component e
wall leakege, reactor operation may continue provided that the leak rate is not greater than 4 gpm.
If the Q
leak rate from these identified sources exceeds.4 gpm, fp the leak shr.11 be isolated from the remainder of the y
primary sys tem or, within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the reactor shall be shut dcen and cooldown shall be initiated.
If the I
leak rate exceeds 6 gpm, normal re.vtor shutdown and cooldown shall be initiated immedit;ely.
}P If radiochemical. analyses' indicate that steam generator secondary coolant iodine 131 concentration exceeds L
0.2 pCi/ml, a normal reactor shutdown will be initiated i
within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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If n...ter inventory-determination cannot b e performed, readings from the vapor container air particulate monitor g
will be used to. evaluate primary system integrity as follows:
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An unexplained increase of 30 cps in the air
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particulate monitor reading shall require an
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immediate investigation within the vapor container.
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An unexplained increase of 45 cps in the air
-g-particulate monitor' reading shall require bringing.the plant to a hot standby dondition 7
- to pennit primary system inspection.
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4 If. both Nethods for detemining main coolant' leakage
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become..ioperative and an hourly schedule of local
. sampling of vapor container air cannot be maintained, if
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the plant will be brought to a hot standby condition.
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