ML20212F299
| ML20212F299 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/22/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212F303 | List: |
| References | |
| NUDOCS 9711040253 | |
| Download: ML20212F299 (8) | |
Text
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k UNITED STATES y+
,j-NUCLEAR REGULATORY COMMIS810N g
waswiwarow. o.c. sonesanos NORTHEAST NUCLEAR ENERGY COMPT.NY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.152 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Comptay, et al. (the licensee) dated June 19, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There.s reasonable assurance (1) that the activities authorized by this amendtrent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satir.fied.
9711040253 971022 PDR ADOCK 05000423 F
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e 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.152
, and the Environmental Pro +ection Plan contained in Appendix B, both of which are attached horn;o are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION w
Phillip F. McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 22, 1997 e
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P ATTACHMENT TO LICENSE AMENDMENT NO, 152 FACILITY OPERATING LICENSE NO. NPF-49 I
QQCKET NO. Sn-423 Replace the following sages of the Appendix A, Technical Specifications, with the attached pages.
Tae revised pages are identified b contain vertical lines indicating the areas of change. y amenoment number and Remove Inigri 2-9 2-9 2-10 2-10 2-11 2-11 2-12 2-12 B 2-5 B 2-5 F
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- m TABLE 2.2-1 (Continued)
TABLE NOTATIONS
$z NOTE 1:
OVERTEMPERATURE AT o;:
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-4 E
f ar' (1+T 8)
(1+T 8) g _ g yj g
4 s
(1+t 8), z _g (1+T 8)
,aTy 2
s E
4 Where-AT is measured Reactor Coolant System AT, *F; AT. is loop specific indicated AT 'at RATED DIERMAL POWER, *F; (14e,s)
(1+t[s) is the function generated by the lead-lag compensator on measured AT; r, and r, are the time constants utilized in the lead-lag compensator for AT, r,18 sec, r, S 3 sec; K,1-1.20 (Four i. cops Operating); 51.20 (Three Loops Operating);
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K 10.02456/*F; 2
(1+t.s)
(1+t s) is the function generated by the lead-lag compensrtor for T,,,;
3 r4 a*xf r, are the time constants utilized in the lead-lag compensator for T f 120 sec, f. 5 4 sec; T 1s measured Reactor Coolant System average temperature, *F; 3a.
5 T' is loop specific indicated Tavg at RATED THERMAL POWER, 5 587.1*F; s
K 1 0.001311/ psi 3
.E P is measured pressurizer pressure, psia; D
P' is nominal pressurizer pressure,12250 psia; 4
s is the Laplace transform operator, sec ;
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3x TABLE 2.2-1 (Continued)
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h TABLE NOTATIONS (Continued) j E
m NOTE 1:
(Continued)
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g and f,(AI) is a function of the indicated difference between top and bottom detectors of the power q
range neutron ion chambers; with nominal gains to be selected based op measured instrument response during plant startup tests calibrations such that:
(1) For g - g between -26% and +3%, f,,(AI) 2 0, where g and g are percent RATED THEIMM. POWER in the upper and lower halves of the core, respectively, and g + g is the total THEIMM.
POWER in r.ercent RATED THERMAL POWER; (2) For each percent that the magnitude of g - g exceeds z6%, the AT Trip Setpoint shall be automatically reduced by 13.55% of its value at RATED THERMAL POWER.
j (3) For each percent that the magnitude of g - g exceeds +3%, the AT Trip Setpoint shall be automatically reduced by 21.98% of its value at RATED THERMAL POWER.
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NOTE 2:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 1.4%
AT span (Four loop Operation); 2.7% AT span (Three Loop Operation).
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TABLE 2.2-1 (Continued)
TABLE NOTATIONS (Continued) 3.5 NOTE 3:
OVERPOWER AT-a-7 f ar' (1+t s)
(t s) i y
g
, AT., (1+t s)-
(1+t,s) a l
.w Where:
AT is measured Reactor Coolant Systes AT, *F; I
AT, is loop specific iredicated AT at RATED THERMAL POWER, *F; (1+t s) i (1+t 8) is the function generated by the lead-lag compensator on measured AT; 2
r, and r, are the time constants utilized in the lead-lag compensator for AT, r,18 sec, 7 1 3 sec; K. I 1.09;
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K,2 0.02/*F for increasing Tavg and K. 5 0 for decreasing T,;
(t s) y (1+t,s) is the function generated by the rate-lag compensator for Tavg; k
ry is the time constant utilized in the rate-lag compensator for Tavg, ry 110 sec; s
{
T is seasured average Reactor Coolant System temperature, *F;
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T" is loop specific indicated Tavg at RATED THERMAL POWER, i 587.1*Fr
,F K,10.00180/*F when T > T" and K, s 0/*F when T i T";
g s is the Laplace transfom operator, sec".
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TABLE 2.2-1 (Continued)
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TABLE NOTATIONS (Continued) m e
E 4
w NOTE 4:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.77,AT span. (Four Loop Operation)
NOTE 5:
Setpoint is for increasing power.
NOTE 6:
Setpoint is for decreasing power.
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LIMITIM 1AFETY SYSTEN SETTIMS BASES Intermediate and Source Ranoe. Neutron Flur The Intermediate and Source Range, Neutron Flux trips - provide core protection during reactor startup to mitigate the consequences of an uncon-trolled. rod cluster control assembly bank withdrawal from a subcritical condition. These trips provide redundant protection to the Low Setpoint trip of the Power Range, Neutron Flux ghannels.
The Source Range channels will initiate a Reactor trip at about 10 coents per second unless manually blocked when P-6 becomes active. The Intermediate Range ciiannels will initiate a Reactor tric at a current level equivalent to ap>roximately 25% of RATED THERMAL POW 2R unless manually blocked when P 10.>ecomes active. No credit was taken for operation of the trips cssociated with either the Intermediate or Source Range Channels in the accident analyses; however, their functional capability at the specified trip settings is required by this specification ta ensance the overall reliability of the Reactor Trip System.
Overtemnerature AT 1
The overtemperature AT trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided that the transient is slow with respect to piping transit delays from the core to the temperature detectors, and pressure is within the range between the Pressurizer High and Low Pressure trips.
The Setpoint is automatically varied with:
(1) coolant temperature to correct for temperature induced changes in density and heat capacity of water and includes dynamic compensation for piping delays from the core to the loop temperature detectors (2) pressurizer pressure, and (3) axial power distribution.
With-normal axial power distribution, this Reactor trip 19mit is always below the core Safety Limit as shown in Figure 2.1-1. If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the Reactor trip-is automatically reduced according to the notations in Table 2.2-1. Although a direction of conservatism is identified for the Overtemperature AT reactor trip function K2 and K3 gains, the gains should be set as close as possible to the values contained in Note 1 to ensure that the Overtemperature AT setpoint is consistent with the assumptions of the safety analyses.
Operation with a reactor coolant loop out of service requires Reactor Trip System modification. Three loop operation is permissible after resetting
. the K1 input to the Overtemperature AT channels, reducing the Power Range Neutron Flux High setpoint to a value just=above the three loop maximum permissible power level, and resetting.the P-8 setpoint to its three loop value. These modifications have been chosen so-that, in three loop operation, each component of the Reactor Trip System perfcres its normal four loop function, prevents operation outside the safety limit curves, and prevents the-DNBR from going below the design limit during normal operational and antici-pated transients.
Overnower AT The Overpower AT trip provides assurance of fuel integrity (e.g., no fuel pellet melting and less than 1% cladding strain) under all possible overpower conditions,' limits the required range for Overtemperature AT NILLSTONE - UNIT 3 B t-5 Amendment No. JK, PP,152 osso
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