ML17320A569
| ML17320A569 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/08/1983 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17320A566 | List: |
| References | |
| NUDOCS 8307120401 | |
| Download: ML17320A569 (7) | |
Text
Attachment No.
2 to AHP:NRC:0591A Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Proposed Revisions to Unit Nos.
1 and 2
Technical Specifications 8307120401 830708 r
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EAGLE 4.3-7 REACTOR TRIP SYSTEH iHSTRUHEHTATIOH SURVEILLANCE AE UIAftlfHH n
~ 4D l
F UNCTIOHhL UtiIT NanuaI Aeagtor Trip 2.
Power ltange, Heutron FIux Clthttt~~EL QIECli C!ihtltlEL ClfhHttEl FUNCTICHAL ChLIDRhTIOM TEST N.A..
S/U{))
0(2), M(3) and g(6j BODES FV. krHICli SUAViILf.h iCE PE UIAEO 3.
Power Range, fleutron Flux, lll glr Positive Rate Power ttange, Hr.<<t.ron F)ux, llt gt, ttega tive Ba te 5.
Intermediate
- Range, tteutron Flux R(.6}
R(6)
SfU('I)
~ ~
1, 2 and@'.
Source
- Range, Heutron FIux 7.
Overter~peratore hT 0.
Overpower aT 9.
. Pressurizer Pressure-Lou IO, Presstrri zer Pressure--lligh ll; Pressurizer Water Leve)-llfgh
)2.
Loss of Flo~< <<Single Loop S
R(6j
'- and S/U() ) '.
2(7),3(Z),O and S
2 3 Q 2
TABLE 4.3-1 (Continued NOTATION With the reactor trip system breakers closed and the'ontrol rod drive system capable of rod withdrawal.
If not performed in previous 7 days.
(2)
He t balance only, above 15~ of RATED THERMAL POWER.
(3)
(~)-
\\
Compare incore to excore axial offset above 15", of RATED THERt/AL'OWER.
Recalibrate if absolute difference 3 percent.
Hanual ESF functional input check every 18 months.
Each train tested every other month.
.(6)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7)
- '. 'elow'.P-6'(Block of SourceRange Reac'tor:Trip) Setpoint, I
D. C, COOK UNIT.1 3/4 3<<14 Amendment No.
REACTOR TRIP SYSTFH iNSTAUl~iENTATIQMSUAVEIf LANCE AECiUIABIEHTS FUNCTlGHhL UHIT Cllht,i<EL CIIECK CllhNHEL CALI DRAT ION QlhHttEL FUHCT IOHAL TESr t'.MES Bt f,"ltiC',f SU"" 'LLf'.HCE
~II."I"J I IIFII l,
Hanual Aeagtor Trfp 2.
Power Bange, Heutron Flux Power Range, tleutron Flux, lllgli l'osftfve Rate Power Range, Neutron F'lux),
llf gl, Hega t f ve Aa te H.A.
. H.A.
SN{l) 0{2), H(3) and 9{6)
A(6)
A(6)
H.A.
5.
Iritermediate
- Range, Heutron Flux 6.
Source
- Range, Neutron Flux 7.
Overtemperature hT Q.
Overpower hT 9.
. Pressur fzer Pressure Low 10.
Pressurfzer Pressure flfgh Pressurfzer Mater Level-flfgh 12.
Loss of Floe - Sfng1e Loop S
R(6)
R(6)
SIU(>)
t') and S(U())
,rc:
TABLE 4.3-1 (Continued NOTATION
- 'ith the reactor trip system breakers
.closed and the control rod drive system capable of rod withdrawal.
(1)
If not performed in previous 7
days.'2)
(3)
(6)
~ P)-
He t balance only, above 15~ of RATED THERMAL POWER, Adjust channel if absolute difference
> 2 percent.
Compare incore to excore axial offset above 15'5 of RATED THERllAL POWER.
Recalibrate if absolute difference
> 3 percent.
Manual ESF functional input check every 18 months.
Each train tested every other month.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
Below P-6 (Block of Source Range Reactor Trip) setpoint.
D. C.
COOX - UNIT 2 3/4 3-13 Amendment No.
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