ML19329A579

From kanterella
Jump to navigation Jump to search
Submits Evaluation of two-pump Operation of Two Loop-4 Pump Reactors
ML19329A579
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 08/02/1971
From: Knighton G
US ATOMIC ENERGY COMMISSION (AEC)
To: Deyoung R
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8001070576
Download: ML19329A579 (1)


Text

m, fr

~

gtSt

'l UNITED STATES 3 f.L ATOMIC ENERGY COMMISSION

[d'I e

WASHINGTON. D.C.

20545 July 12, 1971 R. C. DeYoung, Assistant Director for Pressurized Water ;teactors, DRL TilRU: D. R. Muller, Chief, PWR Projects Branch #1, DRL TWO PUMP OPERATION OF TWO LOOP-4 PUMP REACTORS As part of OL Review for Calvert Cliffs the operation of the reactor coolant loop with 4, 3, and 2 reactor coolant pumps was evaluated.

One step of the review was to compare to other plants, and the second step was to perform in-house simplified calculations.

The results of these steps are as foolows:

I I

i PLANT Reactor Flow Rate (7) of 4 pump 4 pumps 3 pumps

  • l-each loop 2-one loop 1 pump Calvert Cliffs (BG6E 100 73 50 47 Calvert Cliffs (DRL) 100 72.5 45.6 27.6 18.5 Palisades (CPC) 100 71 46 46 Oconee (DPC) 100 74 49 42.8 21

\\

i Note that a significant difference was found between the manufacturers and DRL calculated flow with operation of 2 pumps in one loop.

supports the in-house calculated results.

Our judgement i

The in-house calculations used the basic flow resistance as symbolized in Fig. 1.

i i

I 1

N.

i

.i

'I

._w

..w,

.n.

i 6

i y

r I'IG.


._1_

_Calvert Cliffs Plant 2 pumps Operating In One Loop Rsre t Rr - Reactor Rsg - Steam Ger.erator 4

Rp - Pump P - Operating Iump t

Using Combustion engineering Flow vs liaad curve fot the dead pumps, and pressure drop approximations tlrough the reactorback-flow t and steam generators based on FSAR data, the flow through the reactor was determined as 27.6% of 4 pump flow rate.

i In an effort to determine the cause of the dif ferer ce in calculations, FIG. I was revised to FIG. 2 configuration.

This tepresents one possible error in the manufacturers codes.

3 FIG. 2

+

r

-Q'y**,'

--C

=

1

'A Rez Solving this configuration we find the reactor flow at 47.8 compared to the manufacturers value of 47%.

This configuration is physically impossible to achieve.

Since manufacturers find flows almost equal for either two pump operation, their Tech 1

Specs do not differentiate between the two.

O Since our calculations show the one condition flow much greater than the other, it is suggested that the Project Leaders be aware i

of this apparent, anomaly.

situation to their satisfaction.They may want to clarify their particular Careful flow testing in the field will provide conclusive answers required for rea tor safety.

l

}

s G. W.

nigh Project Leader

,j PWR froject raach #1 A

Division cf Reactor Licensing 4

I l

~... -

.