ML18051A623
| ML18051A623 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/29/1983 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18051A621 | List: |
| References | |
| NUDOCS 8310050469 | |
| Download: ML18051A623 (5) | |
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CONSUMERS POWER COMPANY PALISADES PLAN~ - DOCKET 50-255 - LICENSE DPR-20 PROPOSED TECHNICAL SPECIFICATIONS.CHANGE REQUEST
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8310050469 830929 :
PDR ADOCK 05000255' 1, ___ P '
. PDR L MI0983-0016A-NL02
. PROPOSED PAGES 4 Pages
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~ - - - LiMff1NG -SAFETY-SYSTEM SETTINGS*- - -REACTOR--PROT.ECTIVE.SYSTEM __ (~Qnt '_d)
Basis (Cont'd)
(TM/LP) trip will occur before these limits are reached.
Refer-ence 13 forms the basis for Figure 2-3 for 4-pump operation.
For 2-and 3-pump operation the flow instability criterion is more limiting tha11 the MDNBR criterion.
Reference 7 forms the basis for Figures 2-1 and 2-2.
The trip is initiated whenever the pressurizer pressure drops below the minimum value given on Table 2.3.1, :or a value computed as described below, whichever is higher.
The computed value is a function of reactor inlet temperature and reactor outlet temperature, and takes the form PTrip = ATH.- BTC.... C where A, B and C are consta.nts and TH and TC are the ho_t and cold leg coolant temperatures, respec-tively. *The minimum value of reactor coolant flow and the maximum expected values of axial and radial peaking factors are assumed in generating this trip function.
The TM/LP trip set points are derived from 'the 4-pump operation core
- thermal limits (Figure 2-3) through application of appropriate allowances for measurement uncertainties and processing errors.
A maximum error of 165 psi is assumed to account for expected instru-ment drift and repeatability errors, process measurement uncertain-ties, flow stratification effects, and calibration errors.
As such, a maximum error in the calculated set point of -165 psi has been (12) assumed in the acciden.t analysis.
An analysis ha.s been performed 0 4
~ w~*ich verifies that the TM/LP trip for 4-pump operation provides.adequate thermal margin when RTD time delays and conservative assumptions regarding part.power radial peaking factors are compensa.ted for by an improved pressurizer model, a primary coolant flow update and the XNB DNB correlation for control rod withdrawal transients.
The XNB DNB correlation has been shown to be applicable to the Palisades Plant in Reference 15.
For two-and three-pump coolant pump operation, power is limited to 21% and 39% of rated power, respectively, for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
During either of these modes of operation, the high power level trip in conjunction with the TM/LP trip (minimum set point = *1750 psia) and the secondary system safety valves (set at 1000 psia) assure that the limits shown on Figures 2-1 and 2-2 will not be violated.
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Low Steam Generator Water Level - The low steam generator water level reactor trip protects against the loss of feed-water flow accidents and.assures that the design pressure of the primary coolant system will not be exceeded.
The specified' set point assures that there will be sufficient water inventory in the steam generator at the time of trip to provide a 15-minute margin before the auxiliary feedwater is rer:it.*ired. <9)
TS0883-0001A-NL02 2-8 PROPOSED
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- 2. 3 LIMITING SAFETY SYSTEM--SETYfNGS-.:.: REA:CTOR PROTECTIVE---SYST-EM- --(Cont '_d) _
References (Cont'd)
(8)
XN-NF-77-18, Section 3.8.
(9)
XN-NF-77-18, Section 3.7.
(10)
FSAR, Amendment No 17, Item 4.0.
(11)
XN-NF-77-18, Section 3.6.
(12)
XN-NF-77-18, Section 3.1.
(13)
XN-NF-77-22, Section 3.4.
(14)
XN-NF-83-57.
(15)
XN-NF-709.
TS0883-0002A-NL02 2-10 PROPOSED
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I POWER DISTRIBUTION LIMITS 3~23.1 LINEAR HEAT RATE (LHR)
LIMITING CONDITION FOR OPERATION ACTION 3:
- If the incore alarm system is inoperable and the excore monitoring system is not being used, operation at less than or equal to 85% of rated power may continue provided that incore readings are recorded manually.
Readings shall be taken on a minimum of 10 individual detectors per quadrant* (to in~lude 50% of the total number of detectors in a 10-hour
. period) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and.at least every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thereafter. If readings indicate a local power level equal to or* greater than the alarm setpoints, the action specified in ACTION 1 above shall be taken.
Basis The limitation on LHR *ensures that, in the event of a LOCA, the peak
. temperature. of the cladding will not exceed 2200°F. (1)
In addition, the limitation on LHR for the highest power fuel rod, narrow water gap fuel rod and interior fuel rod ensures that the minimum DNBR will be maintained above 1.30 for th~ W-3 correlation or above 1.17 for the}CNB correlation during anticipated t'ranpients; and, that fuel damage during Condition IV events such as locked* rotor will not exce.ed acceptable limits. (2) <3) <5)
The inclusion of the axial 'power distribution term ensures that the operating power distribution is enveloped by the design power distri-butions.
Either of the two core power.distribution monitoring systems (the incore alarm system or the excore monitoring system) provides adequate monitoring of the core power distribution and is capable of verifying that the LHR does not exceed its limits.
The incore alarm system performs this TS0883-0003A-NL02 3-104 PROPOSED
POWER DISTRIBUTION LYMIT~f- - -
3.23.1 LINEAR HEAT RATES (LHR LIMITING CONDITIONS OF OPERATION Basis (Cont'd) uncertainty factor of 1.03, a thermal power measurement uncertainty factor of 1. 02 and allowance for quadrant tilt.
References (1)' XN-NF-77-24 (2)
XN-NF-77-18 (3)
XN-NF-78-16 (4)
XN-NF-80-47 (5)
XN-NF-83-57 TS0883-0004.A-NL02 3-106 PROPOSED I