ML20094M700
| ML20094M700 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 03/25/1992 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20094M705 | List: |
| References | |
| NUDOCS 9204010269 | |
| Download: ML20094M700 (10) | |
Text
- - _ - _ - _ _ _ _ - _ - _ _ _ - _ -
/
'o UNITED STATES
~g
! " 3.,,
NUCLEAR REGULATORY COMMISSION o
W ASHINGTON, D. C. 20555 O
s I
%,..... /
COMMONWEAllH EDISON COMPANY DOCKET N0. STN 50-454 BYRON STATION. UNIT NO. 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 34 License No NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated October 26, 1990, as supplemented April 23, 1991, November 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 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 is reasonaole 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 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 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-37 is hereby amended to read as follows:
9204010269 920325 PDR ADOCK 05000454 P
4
. (2)
Technical Specifications The Technical Specifications 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 Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR TIE NUCLEAR REGULATORY COMMISSION f.
b~
Fer Richard J. Barrett, Director Project Directorate 111-2 Division of Reactor Projects - !!!/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 25, 1992
A11ACMMENT TO LICENSE AMEN 0 MENT NO. 34 FAClllTY OPERATING LICENSE NO. NPF-37 00CKET 70. STN 50-454 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, Remove Paaes insert Paaes 2-5 2-5 3/4 3-26 3/4 3-26 9
1 l
y L
1
4_. _.
i tos TABLE 2.2-1 (Continuad) e o
i 2
PEACTOR T!fio $r-TIM INSTEMENTATION TRIP SEliOINTS c
S SENSOR f
y1 TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA)
Z (SE)
TRIP SETPOINT ALLOWA3LE VALUE l
I?.
Reactor Coolant Fl::w-Low 2.5 1.77' O.5
>90% of icon mini-
>89.2% of loop mini-sum stee'_,ured flew
- sum measured flow
- 13.
Steau Generator Water
}
Level Low-Low i
l a.
Unit 1 N.A.
N.A.
N. A.
>33.0% of narrow
>31.0% of narrow i
i range instrument range instrument
(
span span b.
Unit 2 N.A H.A N.A.
>36.3% of narrow
>35.4% of narrow Fange instrument range instrument i
i
'7 span 5 pan l
u, f
- 14..Undervoltage - Reactor 12.0 0.7 0
>5268 volts -
>4728 volts -
[
j Coolant Pumps each bus each bus 4
j
- 15. Ur:derfrequency - Reactor 14.4 13.3 0
>57.0 Hz
>56.5 Hz l
Coolant Pumps
}
]
F 16.
m "3
I i
a.
Energency Trip Header N.A.
N.A.
N.A.
-540 psig
>520 psig
}
Pressure n
=
b.
Turbine Throttle Valve N. A.
N.A.
N.A.
>1% open
>1% open Closure r
17.
Safety Injection Ir.put 23 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 1
I r
i
- Minimtra measured flow = 97,6N gpm
{
i,
+
L
1 i
TABLE 3.3-4 (Continued) j
-ENGINEERED SAFETY FEATUr<ES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS l-TOTAL SENSOR TRIP ALLOWABLE e
5 FUNCTIONAL UNIT ALLOWANCE.fTA)
Z ERROR (SE) SETPOINT VALUE L
-vs j
5.
Turbine Trip and y
Feedwater Isolation (continued)
N c.
Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.
{
5.
Manual Initiation N.A.
N.A.
N.A.
N.A.
N.A.
i b.
Automatic Actuation Logic and Actuation Relays N.A.
N.A.
N.A.
N.A.
N.A.
m s
e c.
Steam Generator Water L
Level-Low-Low-Start t
w j
h Motor-Driven Pump and Diesel-Driven Pump
- 1) Unit 1 N.A.
N.A.
N.A.
>33.0% of
>31.0% of narrow range narrow range i
instrument instrument
(
I span span l
l p
- 2) Unit 2 N.A.
N.A.
N.A.
>36.3% of
>35.4% of
[
j-g narrow range narrow range
{
g instrument instrument g
span span d.
Undervoltage-RCP Bus-N.A.
N. 7..
N.A.
->5268 volts
>4728 volts i
'd Starc Motor Driven Pump k
~
1 and Diesel-Driven Pump l
e.
Safety Injection-F e
Start Motor-L Driven Pump ano See Item 1. above for all Safety Injection Trip Setpoints and l
j Diesel-Driven Pump Allowable Values.
i i,--
+
-v t-
-p g
.ew-1 9
m g
--w-es
.#'g >*
- s e g
'4 UNIT L D sT ATIS c
. [' 3 6< ' i NUCLE AR REGULATORY COMMISSION g
8 W ALHING TON, D, C,20Mb
'44...../
LQMtiQWEAL1ft_[QHON COMPAt(1 QQCKE1 NO. S1H_lD-4H EPAIM000 STAT 10.tlJ111 NO. I 6ML!iDHUfL10 I AC1.L11LDHfBlltiLLK[liH Amendment No. 34 License No. NPF-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated October 26, 1990, as supplemented April 23, 1991, November 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 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 is reasonable assurance (i) that the activities authorized by this amendmeni 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 nut 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 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 t.icense No. NPF-72 is hereby amended to read as follows:
t i
2-(2)
Technical Specifications The Tecunical Specifications 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 Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hb.
jL for Richard J. Barrett, Director Project Directorate 111-2 Division of Peactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation
- i
Attachment:
Changes to the Technical Specifications Date of issuance:
March 25, 1992 P
w y.
~-w-v--.-,,,-3
e-,,-,
,w,---
-,---ww,-
y--
,,w-w w-v w - w w,ww ww ww-ww we we=www
-n-e
-. - -era
=
"ww*
'w" - -- - - = *'"**-
e-
r AuAtsiwi 10 LICENSE AMENDMENT NO. 34
[ACJLLTY OPERATING tICENSE NO. NPF-7?,
5 QQCKET NO. SitL50-456 i
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, flemove Paud IDiert Pagu 2-5 2-5 3/4 3-26 3/4 3-26 3/4 3-26a t
i a
-,-.<-w-
.,m,,
...~..~.,,r,i,.,,
,.,w,,,...,,
,,,,.......,,_.m.,,w.v.,,m,w,.,mmy-,m,__e.,%-.m,.,,,-..,,
..,.,y.-,,w.
w,,,_.,,.,.m-.,,,.,ie.
I 4
TABLE 2.2-1 (Continued)
^
5
- g REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS i
15 i
g SENSOR f
i TOTAL ERROR
{
j --
FUNCTIONAL UNIT ALLOWANCE (TA)
Z_
(SE)
TRIP SETPOINT ALLOWASLE VALUE c
z t
i a 12.
Reactor Coolant Flow-Law 2.5 1.77 0.6
>90% of loop mini- >89.2% of loop m
mum measured flow
- minimum measured flow
- 1 j
e 13.
Steam Generator Water y
Level Low-Low a.
Unit 1 N.A.
N.A.
N.A.
>33.0% of narrow
>31.0% of narrow range instrument range instronent span span j
i b.
Unit 2 17.0 14.78
- 1. 5
>17% (Cycle 3);
>15.3% (Cycle 3);
t (Cycle 3)
(Cycle 3)
(Cycle 3) 736.3% (Cycle 4 535.4% (Cycle 4 and N.A. (Cycle 4 N.A. (Cycle 4 N.A. (Cycle and after) of ifter) of narrow f
y and after) and after) 4 and after) narrow range range instrument
[
instrument span span j
14.
Undervoltage - Reactor 12.0
- 0. 7 0
>52ES volts -
>4728 volts -
Coolant Pumps each bus each bus l
t j
15.
Underfrequency - Reactor 14.4 13.3 0
>57.0 Hz
>56.5 Hz Coolant Purgs 4
}
316.
L g-a.
Emergency Trip Header N.A.
N.A.
N.A.
>540 psig 1 20 psig 5
g Pressure t
c.
b.
Turbine Throttle Valve N.A.
N.A.
N.A.
>1% open
>I% open j
2o Closure i
i
%17. Safety Injection Input N.A.
N.A.
N.A.
N.A.
N.A.
from ESF l
- 18. Reactor Coolant Pump N.A.
N. A.
N.A.
N.A.
N.A.
j Breaker Position Trip l
- Minimum ceasured flow = 97,600 gpm
(
L
i 1l
{
{l
)I l'
ll I
l Iij
)
34 eef e
ll oe g
cc g
s nt yy) nt t
E f an CCran l
L ore
(( ere o
B d
m t
m v
d A
n
%wu
%%f eu n
WE a
or OU
- 0. r t 3 4. a er 8
a n
rt n 2
S LL s
A.
A.
1rsa 55dc sa 7
s T
LA t
3 anp 13nanp 4
t N
AV n
N N
1nis
>> anis n
I i
i O
o o
P p
s p
T t
e d
e t
t E
e g
e n
g l
e S
S nt c%a nt o
S l
f an P
T p
ore y3.4 o r e f an v
p I
N i
m C6
=
8 i
R I
r
- . wu (3e) wu 5
r T
O T
PF
- 0. o r
>T r o r 2
T rt n certn 5
N IT n
A.
A.
3rsa 7 ;yt rsa 2
n O
RE o
3 anp 1)Cf anp o
I TS i
N N
> ni s
>3( a ni s i
T t
t A
c T
)
e c
)
e N
E j
)
r j
E S
n 3
4 e n
M
(
I t
I U
R e
ef
)
R OR y
A.
y l
l a d
T SO t
c.c t
e S
NR e
A.
A.
A.
5 y A. C nyd N
e u
N ER f
.C f
n I
SE a
N N
N 1(N( a a
i S
t M
S
)
n E
l 3
l o
T l
C S
a e
e
)
a l
(
YS r
8l l dr
- 7. c.cne r
4 o
A.
A.
A.
y A. Cyat A
o N
f 4C f
f 3
O Z
N N
N 1(N(4 a N
I e
e.
3 T
vs vs A
oe E
U
)
b u oe bu L
T A
al B
C T
a al A
A
(
.V a
.V T
1
)
1 S
E e
)
r e
E C
ml 3
4 e R
N eb A.
ml t
eb U
A t a e
ef N
t a T
LW I w l
l a I w A
AO o
- 0. c
.c o
E TL el A.
A.
A.
y A. C nyd el F
)
el 7C el TA d SA N
N N
1(N( a SA Y
e T
u E
n p
mp F
.i r
d
- um A
t e
n sP u S
n nn tta u
P o
oo ar p
Bn p
D c
n ii Wapm en m
E
(
n o tt tmu P ve n
u R
o i aa rSuP Ci v o
dP E
n i r
t uu oP Rri i
n E
o t e
a tt t w n
- Dr t
an N
i c t
i cc aone e
D c-e
.I dt e a
t AA rLev gr-erpv G
na j w
i e-vi aol jomi N
al n d
n cd nwir 1
2 tt e nt ur E
o I
e I
i n eorD l os I oPD ps e
t a' GLD-t t
oMe M
iI y
F l
a s
i i
v i
y nl m c y' a e ol T
r t
a ml re n
n rtD tt ee I
Tr e y
u oia s
U U
er ervs N
e f r
n t gl evte dad f aie U
et a a
a uoe t eoi
)
)
nt n at ri na S i
M ALR SLMD 1
2 usa SSDD L
i w
l A
bd i
N re x
O ue u
I TF c A
a b c
d e
TCNU F
5 6
$g8, c$e [ "
{
- jg' G g g e
2 I
l;l
- l; i i j)i' j
i!lj ;'
l j::
l';!',