ML20046A021

Proposed Tech Specs Pages 3/4 3-7 & 3/4 3-8,clarifying That Note (5) Applicable to Source & Intermediate Range Neutron Flux Instrumentation

ML20046A021
Person / Time
Site:	Davis Besse
Issue date:	07/15/1993
From:	CENTERIOR ENERGY
To:
Shared Package
ML20046A018	List: ML20046A017 ML20046A021
References
NUDOCS 9307230349
Download: ML20046A021 (2)

Text

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$$. REACTOR PROTECTIGB4 SYSTEN INSTRilHENTATION SilRVEll.IANCE REQllIHLHElffS 83

-ya CIIANNEI. MODES IN UllI4:18

.oa CualetEL CHANNEL. EINGCTIONAL SHRVEILI.ANCE

$$ FleICTieseAL ISIIT rJHNT Cal.ISEATION TEST _ RE001,etti._

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1. Namuel Beacter Trly N.A. N.A. S/U(l) H.A.

2. Eigh Flus: S D(2), and g(6,9) [ N,A, I, 2 l garmt .

3. RC Eigh Temperature 5 R ..it' 3A (9) I, 2

4. Flum - aflus - Flow 5(4) M(3) and Q(6.7,9) Jt' M,4, 1, 2 l g

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3. Sc law Fressure S E # 5A[T) I, 2 l

6. RC Nigh Pressure 5 E # 64[9) I, 2 l.

7. RC Fressure-Temperature 5 B X_$A(4) .1, 2 .

8. Eigh Flus /Ilumber of Reacter Coelaat fuepe Sa' 5 / Q(b,N ' g Ne d e I, 2

~l:

9. Conaaimment.BIsh Fressere 5 R g$4[9) 1 ,. 2-

" 30. Intermediate Bange, IIeutrem Fles'and Bate 5 5(6) S/"'5);"<)- N,A. 1, 2 anda E-(l-II. Se.ree n se, me tr rl.= g.A,(

-and Bete-5 t$)

R(6)~ .40-end-5 2,.3, 4 and S 4 :I-.

12. Control Bed Ibelve Trip Breakers M.A. -N.A. N(6,'l) ands /U(I)(3)-I,2anda

k. . . i- ' ,.

l:

I). Reacter. Trip Iledule f.egic M.A. M.A. N(9) . I, 2 an.la l

{ 14. Shnsdown sypass sigli Pressuse S~ R gd4(T) 2aa,saa.4.....l -

15. SCR Relays. N.A.- N.A. R I, 2 ' an.t

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- ~t Dockst Numbzr 50-346-Licznsa Numbar NPF-3'

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• Serici Numbar 2140

• Attachment Page'2 Tall.I 4. 3-1 (Continued)  !

NOTAT**N (1) - If not performee in previous 7 days.

(2) - Heat balance only, soove 15I of RATED TIERMAL FOTEt'. '

)

i (3) - Vhen TIERNAL 70VER (TF) is above 50% of 3ATED TIERIAL 70VII (RTFJ, and at steady state compara out-of-core sensured AIIAL 70 VIE  !

IMEALANCE ( AFI,] to incore sensured AIIAL 70 VIE IveALAmer (AyI I as iallows:

RTy-Y ( AFI* - AFI.] = Offset Error Recalibrate if the absolute value of the Offset Error is > 2.3%

AIIAL F0 VEE IMRALANCE and loop flov indications only. .r-(4) -

CHANNEL fdacT't09ALTUT is qwf- appffcable,,

(5) - 4 Verify days.

at least one decade overlap if not verified in previous 7 L rior +o each y& sfarfuf p

(6) - Neutron detectors any be awhuled from CEAIEERL cananavn.

(7) - Flow rate sensarement sensors may be essladed fres CIANIEL etunnATION. However, each flow messarement sensor shall be ,

calibrated at least once per 18 aesths.

(8) - The CIAllNEL FURCTIONAL TEST shall independently verify the '

OPERARILITT of both the undervoltage and.shant trip devices of the Reactor Trip 3reakers. ,

f E- Vith any control rod drive trip breaker closed.

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• • - When Shutdown typeas is actuated.

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L q -- le.cforme.d on & W OO DATIS-dESIE. UNIT 1 3/4 3-4 A=======t me. 43 ACE.AAS. @ ,

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