ML20245J503
| ML20245J503 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/14/1989 |
| From: | LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20245J501 | List: |
| References | |
| NUDOCS 8908180052 | |
| Download: ML20245J503 (2) | |
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REACTIVITY CONTROL SYSTEMS au mit-ngth c tas Am Cuy w.u arn -
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- CEA DROP TIME LIMITING CONDITION FOR OPERATICN l
3.1.3.4 The ividual full length (shutdown and regulating) CEA rop time, from a fully withdrawn position, shall be less than or equal to
.0 seconds from when the e tricalpowerisinterruptedtotheCEAdriv(emecanismuntil the CEA reaches 90% insertion position with:
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'D EL E.T E, A DD the Ann g1 T,yg greater than or equal to 520*F, and a.
b.
All reactor coolant pumps operating.
APPLICABILITY: MODES 1 and 2.
U me-cr ey WetvMu*ni G A g u.aar. c hec t he ave rage C.ER drcp ACTION:
o e.- re a ordTa Withk drop time (of any full 1ength CMdetermined to exceed the a.
a trc-abo im restore the CEA drop time to within the above limi s e bac2%or _ _ pro,ceeding to MODE 1 or 2.
oca ra, natn 4:m: Es b.
With the CEA drop times within limits but determined at less than full reactor coolant flow, opera. tion may proceed provided THERMAL POWER is restricted to less than or equal to the maximum THERHAL POWER level allowable for the reactor coolant pump combination e
operating at the time of CEA drop time determination.
SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full-length CEAs shall be demonstrated through measurement prior to reactor criticality:
a.
For all CEAs following each removal and reinstallation of the reactor vessel head, b.
For specifically affected individuals CEAs following any maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c.
At each refueling outage.
8908180002 890814 PDR ADOCK 05000362 P
PDC WATERFORD - UNIT 3 3/4 1-23 AMENDMENT NO. 7
_____________________J
Reissued mster. The %um cst; ** ? 4/3/87 REACTIVITY JONTROL SYSTEMS-f L cestr :ct;.a 1 w. h ne c at= ctr< p t; - e.
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i MOVABLE CONTROL ASSEMBLIES (Continued) continued operations when the positions of CEAs with inoperable position indicators can be verified by the " Full In" or " Full Out" limits.
3 CEA positions and OPERABILITY of the CEA position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent veri-fications required if an automatic monitoring channei is inoperable.
These verification frequencies are adequate for assuring t % t the applicable LCO's are satisjf gd o"% em aca.hmeb c avec TheGoaximum, CEA drop time restriction is $e.
consistant with the assumed CEA drop time used in the safety analyses.g easurement wjith T M
greater than or avg equal to 520 F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.
The establishment of LSSS and LCOs requires that the expected long and short-term behavior of the radial peaking factors be determined.
The long term behavior relates to the variation of the steady state radial peaking factors with core burnup and is affected by the amount of CEA insertion assumed, the por. tion of a burnup cycle over which such insertion is assumed, and the expected power level variation throughout the cycle.
The short term behavi,or relates to
. transient perturbations to the steady state radial peaks due to radial xenon y
redistribution.
The magnitudes of such perturbations depend upon the expected
,~
use of the CEAs during anticipated power reductions and load maneuvering.
Analyses are performed based on the expected mode of operation of the NSSS
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(base loaded, or load maneuvering) and from these analyses CEA insertions are I
determined and a consistent set of radial peaking factors defined.
The Long Term Steady State and Short Term Insertion Limits are determined based upon the assumed mode of operation used in the analyses and provide a means of preserving the assumptions on CEA insertions used. The limits specified serve to limit the j
behavior of the radial peaking factors within the bounds determined from analy-
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sis.
The actions specified serve to limit the extent of radial xenon redistri-bution effects to those accommodated in the analyses.
The Long and Short Term Insertion Limits of Specification 3.1.3.6 are specified for the plant which has been designed for primarily base loaded operation but which has the ability to accommodate a limited amount of load maneuvering.
The Transient Insertion Limits of Specification 3.1.3.6 and the Shutdown CEA Insertion Limits of Specification 3.1.3.5 ensure that (1) the minimum SHUT-DOWN MARGIN is maintained, and (2) the potential effects of a CEA ejection acci-
'j dent are limited to acceptable levels.
Long-term operation at the Transient Insertion Limits is not permitted since such operation could have effects on the core power distribution which could invalidate assumptions used to determine the behavior of the radial peaking factors.
Insertion of Reg. Groups 5 and 6 is permitted to be essentially tip-to-tip within the limits imposed by the Tran-sient Insertion Limit Line.
This method of insertion is protected from sequence errors by the Core Protection Calculators.
The Part' Length CEA Insertion Limits of Specification 3.1.3.7 ensure that adverse power shapes and rapid local power changes which affect radial peaking i
factors and DNB considerations do not occur as a result of a part-length CEA t
group covering the same axial segment of the fuel assemblies for an extended period of time during operation.
WATERFORD - UNIT 3 B 3/4 1-5 AMENDMENT NO. 12
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