ML20214U788
| ML20214U788 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/02/1986 |
| From: | Oconnor P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214U791 | List: |
| References | |
| TAC-57896, NUDOCS 8612090398 | |
| Download: ML20214U788 (10) | |
Text
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UNITE] STATES NUCLEAR REEULATORY COMMISSION o
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,y WASHINGTON, D. C. 20555
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KAhSAS GAS & ELECTRIC COMPANY KANSAS CITY POWER AND LIGHT COMPANY KANSAS ELECTRIC POWER COOPERATIVE, It.C.
WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
7 License No. NPF-42 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by Kansas Gas and Electric Company acting for itself and Kansas City Power and Light Company and Kansas Electric Power Cooperative, Inc., (licensees) dated itay 31, 1985, as revised September 15, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance: (i)thattheactivitiesauthorizedby 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 set forth in 10 CFR Chapter I; 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; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all aoolicable requirements have been satisfied.
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l 8612090398 861202 DR ADOCK 0500 2
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- -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-42 is hereby wended to read as follows:
2.
Technical Specification The Technical Specifications contained in Appendix A, as revised through Amendment No. 7, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporeted into the license.
KG8E shall operate the facility in accordance with the Technical Specifications and the Envirerrental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE fiUCLEAP REGULATORY COMMISSION
\\'A Paul W. O'Connor, Project f!anager PWR Project Directorate No. 4 Division of PWR Licensing-A Attacht'ent:
Changes to the Technical Specifications Date of Issuance: December 2, 1986 gh;F(,
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ATTACHMENT TO LICENSE AMENDMENT NO. 7 OPERATING LICENSE FO. NPF-42 DOCKET NO. 50-482 Revise Appendix A Technica1' Specifications by rer.,cving the paces identified below and inserting the enciesed pages. The revised pages are identified by amendment nunber and contain marginal lines frdicating the area of change.
The corresponding overleaf page is also provided to maintain docunent cocpleteness.
AMENDED PAGE OVERLEAF PAGE 2-4 P-3 2-5 2-6 2-8 2-10 2-7
.v SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS n
- 2. 2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The Reactor Trip System Instrumentation and Interlocks Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.
APPLICABILITY:
As shown for each channel in Table 3.3-1.
ACTION:
a.
With a Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 2.2-1, adjust the Setpoint consistent with the Trip Setpoint value.
b.
With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Values column of Table 2.2-1, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 2.2-1 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2 was satisfied for the affected channel, or 2.
Declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
Equation 2.2-1 Z + R + S f,TA Where:
Z=
The value from Column Z of Table 2.2-1 for the affected channel, R=
The "as measured" value (in percent span) of rack error for the affected channel, S=
Either the "as measured" value (in percent span) of the sensor error, or the value from Column S (Sensor Error) of Table 2.2-1 for the affected channel, and TA = The value from Column TA (Total Allowances) of Table 2.2-1 for the affected channel.
)
WOLF CREEK - UNIT 1 2-3
TA8LE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS g
SENSOR p
TOTAL ERROR x
FUNCTIONAL UNIT ALLOWANCE (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE E
1.
Manual Reactor Trip M.A.
N.A.
N.A.
M.A.
N.A.
m 2.
Power Range, Neutron Flux a.
High Setpoint 7.5 4.56 0
1109% of RTP*
1112.3% of RTP*
b.
Low Setpoint P.3 4.56 0
12S% of RTP*
128.3% of RTP*
3.
Power Range, Neutron Flux, 2.4 0.5 0
14% of RTP* with 16.3% of RTP* with High Positive Rate a time constant a time constant 12 seconds
>2 seconds 4.
Power Range, Neutron Flux, 2.4 0.5 0
14% of RTP* with 16.3% of RTP* with High Negative Rate a time constant a time constant 12 seconds 12 seconds 5.
Intermediate Range, 17.0 8.41 0
12S% of RTP*
135.3% of RTP*
Neutron Flux 6.
Source Range, Neutron Flux 17.0 10.01 0
1105 cps 11.6 x 105 cps 7.
Overtemperature AT 7.2 3.76 1.55 See Note 1 See Note 2
+ 0.9 8.
Overpower AT 5.5 1.43 0.15 See Note 3 See Note 4 9.
Pressurizer Pressure-Low 3.7 0.71 2.49 11875 psig
>1866 psig g
10.
Pressurizer Pressure-High 7.5 0.71 2.49 12385 psig 12400 psig 5
- 11. Pressurizer Water Level-High 8.0 2.18
- 1. %
192% of instrument 193.9% of instrument g
span span "RTP = RATED THERMAL POWER
- Loop design flow = 95,700 gpm
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS g
SENSOR TOTAL ERROR x
FUNCTIONAL bMIT ALLOWANCE (TA)
Z (S)
TRIP SETPOINT ALLOWA8LE VALUE
- 12. Reactor Coolant Flow-Low 3.1 2.19 0.8 190% of loop 189.1% of loop l
c5 design flow"*
design flow"*
-4
- 13. Steam Generator Water 23.5 21.18 2.51
>23.5% of narrow
>22.3% of narrow Level Low-Low range instrument range instrument span span 14.
Undervoltage - Reactor 7.5 1.3 0
110578 Volts A.C.
110355 Volts A.C.
Coolant Pumps
- 15. Underfrequency - Reactor 3.3 0
0 157.2 Hz 157.1 Hz Coolant Pumps "4
- 16. Turbine Trip a.
Low Fluid Oil Pressure N.A.
N.A.
N.A.
1590.00 psig 1534.20 psig b.
Turbine Stop Valwe N.A.
N.A.
N. A.
11% open 11% open Closure
- 17. Safety Injection Input N.A.
N.A.
N.A.
N.A.
M.A.
from ESF l
5a 2a E
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TABLE 2.2-1 (Continued) 5q REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS n=
SENSOR E
TOTAL ERROR 7
FUNCTIONAL UNIT ALLOWANCE (TA)
Z_
(S)
TRIP SETPOINT ALLOWABLE VALUE g
18.
Reactor Trip System a
Interlocks a.
Intermediate Range N.A.
N. A.
N.A.
21 x 10 20 amps 16 x 10 12 amps Neutron Flux, P-6 b.
Low Power Reactor Trips Block, P-7
- 1) P-10 input N.A.
N.A.
N.A.
10% of RTP*
16.7% to < 13.3%
of RTP*
y
- 2) P-13 input N.A.
N.A.
N.A.
<10% of RTP*
<12.4% of RTP*
e s
Turbine Impulse Turbine Impulse Pressure Pressure Equivalent Equivalent c.
Power Range Neutron M.A.
N.A.
N.A.
-<48% of RTP*
<51.3% of RTP*
Flux, P-8 d.
Power Range Neutron N.A.
N.A.
N.A.
-<50% of RTP*
<53.3% of RTP*
Flux, P-9 e.
Power Range Neutron N.A.
N.A.
N.A 10% of RTP*
>6.7% to < 13.3%
Flux, P-10 of RTP* -
f.
Turbine Impulse Chamber N.A.
N.A.
N.A
$10% of RTP*
112.4% of RTP*
Pressure, P-13 Turbine Impulse Turbine Impulse Pressure Equivalent Pressure' Equivalent 19.
Reactor Trip Breakers N.A.
N.A.
N.A N.A.
N.A.
20.
Automatic Trip and Interlock N.A.
N.A.
N.A.
N.A.
N.A.
Logic
- RIP = RATE 0 THERMAL POWER 4
l
+.
- s TABLE 2.2-1 (Continued)
TABLE NOTATIONS (Continued) g NOTE 1:
(Continued) m T'
588.5'F (Nominal T,,,at RATED THERMAL POWER);
g K
=
3 0.000671; Z
P
=
Pressurizer pressure, psig; g
P' 2235 psig (Nominal RCS operating pressure);
=
5
=
Laplace transform operator, s a; and fg(AI) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant STARTUP tests such that:
y (i) for q
~9 between -2N aM + M, f (AI) = 0, h q aM q are Percent t
b t
b RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt*9b is total THERMAL POWER in percent of RATED THERMAL POWER; (ii) for each percent that the magnitude of q 9b exceeds -27%, the AT Trip Setpoint t
shall be automatically reduced by 1.5 N of its value at RATED THERMAL POWER; and (iii) for each percent that the magnitude of q A exceeds + N, the AT Trip Setpoint t
b shall be automatically reduced by 1.05% of its value at RATED THERMAL POWER.
[
NOTE 2:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than g
2.9% of AT span.
l a
.F
..=.
TABLE 2.2-1 (Continued) c5q TABLE NOTATIONS (Continued) l E
NOTE 3: OVERPOWER AT fy f 3 $ AT, N - Ks l T5 I
) (
1f S
AT T
- (
y, ts 7
Ts 1
TsS Em w
Where:
AT
=
Measured AT by RTD manifold instrumentation;
=
i 1
y'3 lead-lag compensator on measured AT;
=
3 i
Time constants utilized in lead-lag compensator for AT. Is = 8 s,12 = 3 s; 13, I2
=
1 Lag Compensator on measured AT;
=
y, g
,7 Time constant utilized in the lag compensator for AT. Ta = 0 s; T3
=
AT, Indicated AT at RATED THERMAL POWER;
=
K
=
4 1.08; Ks 0.02/*F for increasing average temperature and 0 for decreasing average
=
temperature; I
5 y73 T'e function genera.ted by the rate-lag compensator for T,yg h
=
dynamic compensatio't; Time constant utilized in the rate-lag compensator for T,yg, 17 = 10 s; 17
=
1 j
Lag compensator on measured T,yg;
=
y.
3 4
Time constant utilized in the measured T,yg lag compensator, T = 0 s; Ts
=
l t
e e
e q
TABLE 2.2-1 (Continued) l!
TABLE NOTATIDMS (Continued)
}
g; NOTE 3:
(Continued)
N Ks 0.00128/*F for T > T" and Ks = 0 for T 5 T";
=
gg T
Average temperature, *F;
=
a T"
Indicated T,yg at RATED THERMAL POWER (Calibration temperature for AT
=
instrumentation, 5 588.5'F);
l 5
=
Laplace transform operator, s.1; and f (AI) 0 for all AI.
=
2 NOTE 4:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 4
q) 4.0% of AT span.
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