ML20065P260
| ML20065P260 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/06/1990 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065P264 | List: |
| References | |
| NUDOCS 9012130189 | |
| Download: ML20065P260 (8) | |
Text
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UNITED STATES o
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,n NUCLEAR REGULATORY COMMISSION j
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ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT UNIT 2 AMENDMENT TO FACILITY OP_ERATING LICENSE Amendment No. 79 License No. NPF-8 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee),datedJuly 31, 1990, complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act),
anc the Comission'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 Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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-8 is hereby amended to read as follows:
9012130189 901206 DR ADOCK 0500 4
2 (2) - Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, are hereby incorporated in the license.. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
Elinor G. _ Adensam. Director j
Project Directorate 11-1 Division of Reactor Projects. I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 6, 1990 l
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i A1TACHMENT TO LICENSE AMENDMENT NO, 79 i
j FACILITY OPERATING LICENSE N0, NPF-8 DOCKET NO, 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Insert Pages 2-2 2-2 2-5 2-5 2-8 2-8 2-9 2-9 3/4 2-15 3/4 2-15 i
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Unacceptable Operation 2400 psia 2250 psia s4e<
2000 psia 187g,9,
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Figure 2.1-1 Reacter Core safety Limit Three Le:ps in Operation FARLEY UNIT 2 heeneent No. 27, 65, 79 11
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.- i TABLE 2.2-1 I
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g REACTOR TRIP SYSTCM INSTRUMENTATION TRIP SEITOINTS i
g FUNCTIONAL UNIT-TRIP SETPOINT ALLOVABLE VALUES
[
1.
Manual Reactor Trip Not Applicable Not Applicable
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{
i 2.
Power Range, Neutron Flux Lov Setpoint - f 25% of RATED Low Setpoint - < 26% of RATED i
THERMAL POWER THERMAL POWER
{
}
High Setpoint - f 109% of RATED High Setpoint - f 110% of RATED i
THERMAL POWER THERMAL POWER i
)
3.
Power Range, Neutron Flux, f 5% of RATED THERMAL POWER with f 5.5% of RATED THERMAL POWER f
High Positive Rate-a time constant > 2 second with a time constant > 2 second i
.i 4.
Pover Range, Neutron Flux,
< 5% of RATED THERMAL POWER iith
< 5.5% of RATED THERMAL POWER 1
~
a time constant 2 2 second with a time constant 2 2 second
[
High Negative Rate
,i 5.
Intermediate Range, Neutroa f 25% of RATED THERMAL POWER f 30% of RATED THERMAL POVER Y
Flux i
v' i
l 6.
Source Range, Neutron ? lux
$ 10' counts per second f 1.3 X 10' counts per second 7.
Overtemperature aT See Note 1 See Note 3 i
8.
Overpower AT See Note 2 See Note 3 l
I 9.
Pressurizer Pressure-Lov 2 1865 psig 2 1855 psig i
10.
Pressurizer Pressure-High
$ 2385 psig
$ 2395 psig l
11.
Pressurizer Vater f 92% of instrument span
.$ 93% of instrument span
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Level-High
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l 12.
Loss of Flov 2 90% of design flow per loop
- 2 89% of design flow per loop
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- Design flow is 87,200 gpa per loop.
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g TABLE i.2-1 (Continued)
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E REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
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NOTATION Note 1: Overtemoerature Er f 5r, [K -K,1 +T S (T - T') + K (P - P') - f, (aI)]
3 1
3 1 + T, S w
i vhere:
AT, = Indicated ar at RATED THERMAL POtR T = Average temperature, 'F T' f 577.2*F (Maximum Reference T,,, at RATED THERMAL POVER) 1
~
P = Pressurizer pressure, psig a
P' = 2235 psig (Nominal RCS operating pressure) t L
- T
= The function generated by the lead-lag controller for T,,, dynamic campensation 1
y 1 + T,S
& T,
= Time constants utilized in the lead-lag controller for T,,,
T,
= 30 secs, T, = 4 secs.
l T1 S = Laplace transform operator, sec *.
~
i Operation with 3 loops Operation with 2 loops r
(values blank pending l
1.18 K
K
=
=
1 3
K, = 0.0154 K, = NRC approval of 0.000635 K
K 2 loop operation)
=
=
3 3
and f (aI) is a function of the indicated difference between top and bottom detectors of the pover-range nuclear ion g
chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
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7 13BLE 2.2-1 (Continued)
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REACTOR TRIP STS13 INSTRUMENTATION TRIP SETPOINTS NOTATION continued (i) for q
-q between -35 percent and +9 percent, f (AI) = 0 (where q and q are percent RATED 5
THERM 1L PO b in the top and bottom halves of the core respectively,,and q,,+ q, is total THERMAL 1
POVER in percent of RATED THERMAL F0VER).
y z
(ii) for each percent that the magnitude of (q, - q,) exceeds -35 percent, the aT trip setpoint shall be automatically reduced by 1.37 percent of its value at RATED THERMAL POVER.
(iii) for each percent that the magnitude of (q, - q,) exceeds +9 percent, the aT trip setpoint shall be automatically reduced by 1.75 percent of its value at RATED THERMAL F0VER.
l TS 3
Note 2:
Overpower E $ AT,[K, - K 1+T 5 T - K, (T-T*)-f ( al)]
3 3
3 where:
E,- Indicated aT at RATED THERMAL POWER T = Average temperature, 'F T* = Reference T,,,
at RATED THERMAL POVER (Calibration temperature for aT instrumentation, f 577.2'F)
K, = 1.08 K - 0.02/'F for increasing average temperature and 0 for decreasing average temperature 3
K, = 0.00109/'F for T > T*; K, m 0 for T f T*
T
- The function generated by the rate lag controller for T,,, dynamic compensation 3
1+T S 3
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TAB M 3.2-1 p
DNB PARAMETERS t
c:
LIMITS k
PARAMETER 3 Loops in Operation 2 Loops in Operation Reactor Coolant System T,,,
f 581.2'F Pressurizer Pressure 2 2220 psia
- Reactor Coolant System 2 261,600 gpa l
Total Flov Rate T
a Y
t:
Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POUCR step in excess of 10% of RATED THERMAL POVER.
Values blank pending NRC approval of 2 loop operation.
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