ML20073K723
| ML20073K723 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/30/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073K726 | List: |
| References | |
| NUDOCS 9105100308 | |
| Download: ML20073K723 (1) | |
Text
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I SAFETY LIMITS LIMITING SAFETY SYSTEM SETTINGS 1.1 DEL CIAD[11.tiG _INTEGRl.U 2.1 E l l C.lA D DI N O A R U f Rl U 6pylie ab11i t:y 6pplink111D The Safety Lirnit s established t The 1.imiting Safety System Settings preserve the fuel cladding integrity apply to trip settingn of the apply to those variables which instruments and devices which are monitor the fuel therrnal behavior, provided tn prevent the fuel cladding integrity Safety Limits Eld 1E from being exceede'd.
The objective of the Safety Limits is to estnblish limitn below which
@les.Lin the integrity of the fuel cladding is preserved.
The objective of the Limiting Safety System Settings is to detine the Milan level of the process variables at E'
li a Safety Limit is exceeded, the initiated to prevent the fuel reactor shall be in at least hot cladding integrity Safety Limits shutdown within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Irom being exceeded, faccifications Fyecifications A.
Eractor Pressure >$E0 niin ancL. gore Flow >10% of P.ated A.
IIip_Se t t ittu The existence of a rnini mum critical power ratio (MCPR)
The limiting safety system l
1ess than 1.06 for two trip settings shall be as recirculation loop operation specified below:
1 (1.07 for single-loop operation) shall constitute 1.
Etytron Flux Trip Setting violation of the fuel cladding integrity safety, n.
APRM Flux Scram Trip S e t. Ling B.
Core Thermal Power Limil (Reactor Press.ure <800 nsia When the Mode Switch is in the and/or Cfre Flow (10%)
RUN position, the APRM flux When the reactor pressure is scram trip setting shall be:
(800 psia or core flow is less than 10% of rated, the S50.66 W 4 54% -.66 AW core thermal power shall not whero-exceed 25% of rated thermal i
S - Setting in percent of power
- ^1 P"*"
he C.
Power Trantic_nt
[
ord ca To ensure that the Safety W - Two lon recirculation pc.
o5 Limit established in figy
,g of Q
Specification 1.1.A and 1,1.B rated (rated loop is not
- excteded, ench g,.
bu required scram shall be is the mit MMim f1w y
init int ed by its expected me sM rovides 100%
oc scram signal.
The Safety coreflow at 100% power) 1.imit shall be ar.sumed to be nom exceeded when scram is AW - Difference between
$$o.
accomplishett by a means other two loop and single-loop effective drive ilow at.
than the expected scrnm signal.
the same core flow.
Amendment No. 48,52,88,94,133 6