ML20091E066
| ML20091E066 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 04/06/1992 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20091E068 | List: |
| References | |
| NUDOCS 9204130318 | |
| Download: ML20091E066 (10) | |
Text
'o UNITED STATES P
g NUCLEAR REGULATORY COMMISSION
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i W ASHING TON, D. C. 20555
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M QNWEALTH FDISON COMPANY QQ3ET NO. STN 50-454 BYRON STATION. UNIT NO. 1 M[1(DMENT TO FACILITY OPERATING LICENSE Amendment No. 45 License No. NPF-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated October 26, 1990, as supplemented April 23, 1991, NovemN r 18, 1991 and February 6, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and 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 (i) 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 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 applica'le requirements o
have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specif1-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:
I 920413031s 920406 gor ADOCK0500Q4
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- 1. -
i i
2-(2)'
Technical ' Soecifications -
The Technical Specifications contained-in Appendix A.as revised through Amendment-No. 45 L and the Environmental Protection Plan contained in Appendix B, both of which.are attached hereto, are hereby incorporated into this-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.
FOR-T NUCLEAR REGULATORY COMMISSION
- Por Richard J. Barrett, Director Project Directorate III-2 Division of Reactor Projects - !!!/IV/V Office of Nuclear Reactor Regulation-
Attachment:
Changes to the-Technical-
' Specifications-Date of Issuance:
March 25, 1992 1
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ATTACHMENT TO LICENSE AMEND. MENT NO. As IACILUX OPERATJfjG LICENSE NO. NPF-37 DOCKET NO. STN 50-451 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Bemove Paoes insert Pace.1 2-5 2-5 3/4 3-26 3/4 3-26
.s.
x..
1 en L
55 TABLE 2.2-1 (Continued)-
E REACTOR TRIP 5YSTEM INSTRUMENTATION TRIP SETPOINTS E
-SENSOR d
TOTAL ERROR' g
FUNCTIONAL UNIT.
ALLOWANCE (TA)..Z (SE)
TRIP SETPOINT
-ALLOWA8LE VALUE.
r
[
12.
Reactor Coolant Flow-Low.
2.5 1.77
- 0. 6 :
->90% 'of : loop mini-
>89.2% of loop mini-4 mum measured flow
- mum measured flow
- i r
13.
Steam Generator Water Level Low-Low i
a.
Unit 1 N.A.
N.A.
'N.A.
>33.0% of narrow
>31.0% of na'rrow l
f range instrument range instrumentL
^
span span b.
Unit 2 N.A N.A N.A.
>36.3% of narrow
>35.4% of narrow range instrument range instrument-7
. m span span i,
14.
Undervoltage - Reactor 12.0
- 0. 7 0
>5268 volts -
>4728 volts 1
Coolant Pumps each bus each bus 15.
Underfrequency. Reactor 14.4 13.3 0
>57.0 Hz
>56.5 Hz Coolant Pumps F
16.
t a.
Emergency Trip Header N.A.
N. A.
N.A.
>540 psig
>520 psig
. Pressure 2
b.
Turbine Throttle Valve' N. A.
N.A.
H.A.
>1% open 4
->1% open F
Closure
- 17. Safety Injection. Input N.A.
N. A.
N. A.
N.A.
N.A.
from ESF-s 18.
Reactor Coolant Pump N.A.
M.A.
.N.A.
N.A.
N.A.
Breaker Position Trip
- Ninimum measured flow = 97,600 gpm
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS c
. TOTAL SENSOR TRIP ALLOWABLE 3
FUNCTIONAL UNIT ALLOWANCE (TA)
Z_
ERROR (SE) SETPOIhT VALUE d
S.
Turbine Trip ano y
Feedwater Isolation (continued)
N c.
Safety Injection See Item 1. above for all Safet3 'ajection Trip Setpoints znd Allowable Values.
6.
Manual Initiation M.A.
N.A.
N.A.
N. A.
N.A.
b.
Automatic Actuation Logic and Actuation Relays N.A.
N.A.
N.A.
N.A.
N.A.
D c.
Steam Generator Wai.er y
Level-Low-Low-Start g
Motor-Driven Pump and Diesel-Driven Pump
- 1) Unit 1 N. A.
N.A.
N.A.
>33.0% of 131.0% of narrow range narrow range instrument instrument span span g
- 2) Unit 2 N.A.
N. A.
N.A.
136.3% of 135.4% of g
narrow range narrow range g
instrument instrument g
span span d.
Undervoltage-RCP Bus-N.A.
N.A.
N.A.
15268 volts
>4728 volts
?
Start Motor Driven Pump and Diesel-Driven Pump e.
Safety Injection-Start Motor-Driven Pump and See Item 1. above for all Safety Injection Trip Setpoints and Diesel-Driven Pump Allowable Values.
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'g UNITED STATES NUCLEAR REGULATORY COMMISSION
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M 4tNGTON, D. C. 20665
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34-License No. NPF-72 1.
The Nuclear Regulatory Com.nission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) da'ed October 26, 1990, as supplemented April 23, 1991, November 18, 1991 and February 6,1992, codiplies 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 Comission; C.
There is reasonable assurance (i) 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 ecmpliance 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 requiremants have been satisfied.
2.
Accordingly,.the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:
. ~ - -
'- n (2)
Technical Specifications The Technical Specificatters contained in Appendix A as revised
- through Amendment No. 34 - and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate' the facility in accordance with the Technir. Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAtt REGULATORY COMMISSION Ii for Richard J. Barrett, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 25, 1992 r;
l
ATTACHMENT TO LICENSE AMENDMENT NO. 34 FACILITY OPERATING LICENSE NO. F;1-22 DOCKET NO. STN 50-456 Replace _the following pages of the Appendix 'A' Technical Specifications with the attached:pages.
The revised pages are identified by amendment number and contain-vertical lines indicating the area of change.
Remove Paoes Insert Paaes 2-5 2-5 3/4 3-26 3/4 3-26 3/4 3-26a
(
4
+
1
~_
TABLE 2.2-1 (Continued)
$g REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS E5g
. SENSOR TOTAL ERROR EFUNCTIONALUNIT ALLOWANCE (TA)
Z (SE)
TRIP SETPOINT ALLOWABLE VALUE
$ 12.
Reactor Coolant Flow-Low 2.5' 1.77 0.6 190% of loop mini-189.2% of loop..
mum m=asured flow
- cinin:um measured.
i)ow*
[13.
Steam Generator Water i
Level Low-Low a.
Unit 1 N.A.
N.A.
N.A.
>33.0% of narrow
>31.0%'of narrow l
range instrument range instrument span span b.
Unit 2.
17.0 14.78
-1.5
>17% (Cycle 3);
>15L3% (Cycle 3);
(Cycle 3)
(Cycle 3)
(Cycle 3)
[36.3%(Cycle 4
[35.4%(Cycle 4and N.A. (Cycle 4 N.A. (Cycle 4 N.A. (Cycle and after) of after) of narrow 4
and after) and after) 4 and after) narrow range range instrument instrument span span 14.
Undervoltage - Reactor.
12.0 0.7 0
15268 volts -
>4728 volts -
Coolant Pumps.
each bus each bus 15.
Underfrcquency - Reactor 14.4 13.3 0
>57.0 Hz
>56.5 Hz Coolant Pumps F16.
E, h
E a.
Emergency Trip' Header N. A.-
N.A.
N.A.
g Pressure
. >540 psig 1520 psig
-1 C
b.
Turbine Throttle Valve N.A.
N.A.
N.A.
>l% open
>1% open
?
Closure M17.
Safety Injection Input N.A.
N.A.
N.A.
N.A.
N.A.
from ESF 18.
Reactor Coolant Pump N.A.
N. A.
N. A.
N.A.
N.A.
Breaker Position, Trip Minimum measured flow = 97,600 gpm
[
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SE1 POINTS
.sg TOTAL SENSOR TRIP ALLOWABLE g
FUNCTIONAL UNIT ALLOWANCE (Tri)
Z ERROR (SE) SETPOINT VALUE o
75.
Turbine Trip and Feedwater Isolation (continued) c h
c.
Safety Injection See Item 1. above fcr all Safety Injection Trip Setpoints and i
e Allowabie Values.
[
6.
Aur411ary Feedwater a.
Manual Initiation N.A.
N.A.
h.A.
N.A.
N.A.
b.
Automatic Actuation Logic and Actuation Relays H.A.
N.A.
N. A.
N.A.
N.A.
c.
Steam Generator Water Level-Low-Low-Start
{
Motor-Driven Pump and Diesel-Driven Pump
- 1) Unit 1 N.A N.A.
^;. A.
133.0% of
>31.0% of narrow range narrow range instrument instrument span span
- 2) Unit 2 17.0 14.78 1.5
- 17% (Cycle
>15.3% (Cycle 3);
y (Cycle 3)
(Cycle 3) (Cycle 3) 3); >35.3%
[35.<%(Cycle 4 m
N.A.
N.A.
N.A.
(CycTe 4 and and after) of y
(Cycle 4 (Cycle (Cycle 4 after) of narrow range and after) 4 and and after) narrow range instrument e
A after) instrument span g
span g
d.
Undervoltage-RCP Bus-N.A.
N. A.
N.A 15258 volts >4728 volts Start Motor Driven Pump and Diesel-Driven Pump e.
Safety Injection-Start Motor-Driven Pump and See Item 1. above for all Safety Injection Trip Setooints and Diesel-Driven Pump Allowable Values.
._