ML19308E043

Forwards Reactor Physics Tech Specs Questions from Core Performance Branch

ML19308E043
Person / Time
Site:	Crystal River
Issue date:	10/23/1973
From:	Stello V US ATOMIC ENERGY COMMISSION (AEC)
To:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8003200776
Download: ML19308E043 (4)

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9-R. C, DeYoung, Assistant Director for Prascurized Water Reactors, L REACTOR PETSICS TECm(ICAL SPECIFICATIONS QUESTIONS Plant Names

. Crystal River Unit 3 Licensing Stage OL Docket No.:

50-302 Responsible Branch FWR-4 and Project Manager B. Bucklar/

Requested Completion Data:

October 23, 1973 Tec:uical Reviw Dra:.ch Involved: Core ?crfornance 3 ranch Description of Review:

Technical Specifications Input A review of the reactor phycica of thu Crystal River Unit 3 Technic;d-Spacificatiens has been cetolated by the Core Parformance 2 ranch.

.t, encionura lists infornation and questions which arose fron this rsview.

The inbre.ation provided by cha Core Perfcznanco Branch in its reviaw of operctional parar.atars fev 2,abcoch & Wilcox redded planto (T.'.P.-605, 1 9 -1.0078) inut ales be ccanidend in tha Crystal River 3 Technical specificatina:3.

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o CRYSTAis RIVER 3 - TECHNICAL SPECIFICATIONS-INPUT.

'l.. The' following definitions should be included in the'Techdical~

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Specifications:

S tartup The reactor shall.be considered in the startup mode when the shutdown margin is reduced with the intent of going critical.

Refuelinz Period' Time between normal refuelings of the reactor,.not to exceed LS months without prior approval of the AEC.

Reac tor Protec tive Sys tem Locic This system utilizes reactor trip module relays (coils 'and contacts) in all four of the protective channels as shown in Figure 7-1 of the FSAR, to provide reactor trip signals for de-energizing the six control rod drive trip breakers. The control rod d::.ve trip breakers are arranged to provide a enemut-of-two times two logic.

Each element of the one-out-of-two times two logic is controlled by a separate. set of two' out of four logic contacts from the four-reactor protective.

channels.

Encineered Ss:ety Features System This system. tilizes relay contact output from individual channels arranged in three analog sub-sys tems 'and two two-out-of-three sub-

.'sys tems as showin in Figure 4 of the FSAR. The logic su'-system o

is wired to. provide. appropriate signals for the actuation of redundant -

Engineered Safety Features equipment on a two-of-three basis fo'r any given parameter.

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< A trip, test'is a. test of logic elements in a. protective channel to -

verify [their associated trip. action.

Heat Balance Calibration An adjus tment of the power range channel' aaplifiers ' output to-agree.

with theLeore thermal power asI determined byna heat balance on the secondary side of the steam generator considering all heat. losses

'and additions.

2.

Add the following statement to definition 15.1.10.

The quadrant power (ilt limits as a function of power are stated in Specification 15.3.5.2D.

3.

Add the following statements to definition L5.1.11.

Imbalance is monitored continuously by the Reactor Protective System 4

I using input from the power range channels.

Imbalance limits are defined in Specification 15.2.1 and imbalance'setpoints are defined in Specification 15.2.3.

4.

The following statements should be added to the specification part of 15.2.3.

The pump monitors shall produce a reactor trip for the following conditions:

a.

Loss of two pumps and reactor power level is greater than 557. of rated power.

b.

Loss of two pumps in one reactor cociant loop and reactor-power. Level is greater than 0.07. of rated power.

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.c.

Loss of one or-two pumps during two-pump; operation. -

H 5.- Why are the setpoints' of' the power versus'.~ ercent axial power p

l imbalance envelope given in' figure 15-4 much broader than those given in BAW-10075 by~B&W'for its rodded plants?. The power-versus imbalance limits given in BAW-10078 are based on LOCA-criteria. The' difference-I i

in rated power for Crystal 3 and other B&W rodded plants do.not. appear-to explain this difference.

-4 6.

In the bases of Specification 15.3.1.7, should the +0.05 X 10 be

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+0.5 X 10 ? The bases should also list all of the factors which will' be. used to correct the measured moderator coefficient.

7.

The line indicating the centrol rod withdrawal limit is missing on.

figure 15-SA.

.S.

Add the following sentence to specification 15.3.5.2-ES.

If an acceptable imbalance is not achieved with2.n four hours,

. reactor power _ shall be reduced until imbalance limits are met.

l 9.

Add the following statement to the bases of specification 15.3.5.2.

The quadrant tilt and axial imbalance monitoring in Specifications 15.3.5.2-06 and 15.3.5.2-E5,respectively normally will' be performed y

in. the' process cc=puter. The 'two hour frequency for monitoring thesc quantities. will provide adequate surveillance when the computer is.

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out of service.

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10. ' Xenon is misspelled in Specification 15.3.5~2-E4.

There are four occurrences.

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