ML20059B447
| ML20059B447 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/17/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power & Light Co |
| Shared Package | |
| ML20059B451 | List: |
| References | |
| DPR-66-A-155 NUDOCS 9008290086 | |
| Download: ML20059B447 (12) | |
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'g UNITED STATES NUCLEAR REGULATORY COMMISSION W AsHINGT oN, D. C. 20bb6
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DDQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT WO.' 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 155 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated March 2, 1989, as supplemented June 12, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission' 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 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.
9008290086 900817
)
PDR ADOCK 05000334 l
P PDC t
.g.
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. DPR-66 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.155, 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 the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COM41SSION John F. S olz, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 17, 1990 u,
- =
I i
ATTACHMENT TO LICENSE AMENDMENT NO. 155
)
i FACILITY OPERATING LICENSE No. DPR-66 DOCKET NO. 50 334 Replace the following pages of Appendix A, Technical Specifications, with the J
enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
1 Remove Insert 2-6 2-6 2-7 2-7 2-7a 2-la 2-10 2-10 3/4 3-22 3/4 3-22 3/4 3-22a 3/4 3-22a 3/4 3-23 3/4 3-23 3/4 3-24 3/3 3-24 3/4 3-24a 3/4 3-24a t
1-l
TABLE 2.2-1 to g
HEACTOR TMIP SYSTEM INSTRUMENTATION TRIP SETPOINTS MN FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VAIMES
- 1. Manual Reactor Trip Not Applicable Not Applicable M
i 2.
Power Range, Neutron Flux Low Setpoint - S 25% of RATED Low Setpoint - S 27.3%
l t
THERMAL POWER c
RATED THERNAL POWER i
5 d
High Setpoint - 5 109% of RATED High Setpoint - 5 111.3%
l THERNAL POWER of RATED THERNAL POWER w
3.
Power Range, Neutron Flux, S 5% of RATED THERMAL POWER with 5 6.3% of RATED THERNAL l
High Positive Rate a time constant 2 2 seconds POWER with a time constant 2 2 seconds
- 4. Power Range, Neutron Flux, 5 5% of RATED THERNAL POWER with 5 6.3% of RATED THERMAL l
High Negative Rate a tima constant 1 2 seconds POWER with a time constant y
1 2 seconds
- 5. Intermediate Range, S 25% of RATED THERNAL POWCR S 31.1% of RATED THERNAL l
Neutron Flux POWER y
- 6. Source Range, Neutron Flux 5 10 counts per second 5 1.4 x 105 5
counts per l
second
- 7. Overtemperature AT See Note 1 See Note 3 y
- 8. Overpower aT See Note 2 See Note ai M
- 9. Pressurizer Pressure-Low 1 1945 }>sig 2 1934 psig l
}
- 10. Pressurizer Pressure--High 5 2385 psig i 2394 psig l
l
- 11. Pressurizer Mater S 92% of' instrument span S 93.9% of instrument span l
~0 Level--High G
- 12. Loss of Flow 2 90% of design flow
- 2 89.2% of design flow
- l per loop per loop
- Design flow in 88,500 gpn per loop.
~
=
d tu
- TAHLE 2.2-1 (Cont i nual)
M
..~
j REACTOR TRI P SYSTEM INSTRUMENTATION THIP SETPOINTS
~
- o FUNCTIONAL UNIT TRIP SETPOINT b
ALIDWABLE VAIMES Q,
- 13. Steam Generator Water 2 12% of narrow range instrument 2 10.7% of narrow range l
Level-Low-Inw span-each steam generator instrument span-each steam generator zy
- 14. Steam /Feedwater Flow 5-40% of full steam flow at S 43.4 of full steam flow l
Mismatch and Low Steam RATED THERMAL POWER coincident at RATED THERNAL POWER 3
Generator Water Imvel with steam generator water level coincident with steam generator water level 2 25% of narrow range instru-
> 23.$ of narrow range l
ment span--each steam generator instrument span-each steam i
generator
[
l
- 15. Undervoltage-Reactor 1 2750 volts-each bus 2 2687' volts-each bus l
y Coolant Pumps a
- 16. Underfrequency-Reactor 2 57.5 Hz - each bus 1 57.4 Hz - each bus Coolant Pumps
- 17. Turbine Trip A.
Auto stop oil pressure 45 psig N
i 5 psig g
B-Turbine Stop Valve 2 1% open 2 1% open S
j
- 18. Safety Injection Input Not Applicable Not Applicable
[
from ESF r*
O e
- 19. Reactor Coolant Pump Not Applicable Not Applicable 3
Breaker Position Trip g
- 20. Reactor Trip System Interlocks A.
Intermediate Range 2 1 x 10-10 Amps 2 6 x 10 -11 Amps Neutron Flux, P-6 i
1
TAl3LE 2. 2-I (Continued) to M
g REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS,
M l
M t
y
- 20. (Continued) ta t-M'<
FUNCTIONAL UNIT TRIP SETPOINT ALIANABIE VANDES a
e B.
P0wer Range 5 30% RATED THERMAL POWER S 32.3% RATED THERMAL l
l Neutron Flux, P-8
.-3 POWER r
C.
Power Range 5.49% RAT =,D THERMAL POWER
$ 51.3% RATED THERMAL l
Neutron Flux, P-9 POWER t
D.
Power Range 10% RATED THERMAL POWER
> 7.7% and S 12.3% RATED 3
i Neutron Flux, P-10 THERMAL POWER I
(Input to P-7)
E.
Turbine Impulse 5 10% of RTP Turbine Impulse 1 12.3% of RTP Turbine y
e Channucc m rsure, P-13 Pressure Equivalent Impulse Pressure i
j (Input to P-7) i Equivalent i
,i i
i b
k a
i a"
t o
N w
M
-F#
m e
. - mL" -
-A ae m
h s-t.
m-a
- s<s.--.
.a m
r:
~
=>.
TA13LE 2.2-l' (CONTINUEPj.
REACTOR TRIP' SYSTEM INSTRUMENTATION TRIP SETPOINTS c
- o NOTATION M
g NOTE 2:
Overpower AT [ 1
$ AT K -K S [1+ tST- / 1 i.T-K 1
o 4
6 T/ 1' 3 -T*
-f(aI 3
1+t S t
(
3y (1+15 4
. (+'5 j J
8 S
where:
AT H
O Indicated AT at RATED THERMAL POWER
=
e T
=
Average temperature,
- F T"
Indicated T at RATED THERMAL POWER S 576.3*F
=
avg l
K i
4 1.07
=
K S
0.02/*F for increasing average temperature
=
u' K6 0.00128 for T > T"; K6= (0) for T 5.T"
=
o i
Thefunction\\eneratedbytheratelagcontrollerforT,9 S
13
=
compensation.
dynamic
[
1+t S 3
Tiw constant utilized in the rate.'bng controller for T,9,
-t 1
=
3 i
= 10 secs..
[
1 f
Lag t. v nsator on measured AT
=
1+1 S 4
E.
g
?,
Time constant utilized in the lag compensator for aT,'s 2 secs.
i
=
4 1
Lag compensator on measured T,9
=
2
,o 1+ '58 g
t Time, constant utilized in the lag compensator for Tavg 5 2 secs.
=
5 2
S Laplace transform operator.
=
. f (a I)
.=
0 for all aI v.
NOTE 3: The channel's maximum trip. point shall not exceed its' computed trip point. by more than 3.3 percent.
NOTE 4:
The channel's maximum trip point shall.not exceed its. computed trip point by more than 2 ercent.
l
~.
~
l{,V]
.s-
_.g:
~ $
TABIE 1. 3-4 m*
~
ENGINEERED SAFETY FEATURE ACTUATION' SYSTEM INSTRUMi!.riTATION TRIP SETPOINTS t*
t<
M i
t FUNCTIONAL UNIT TRIP SETPOINT-ALLONABIE VALUES C
2:
H
+3 1.
SAFETY INJECTION, TURBINE TRIP AND FEEDNATER ISOIATION a.
Manual-Initiation Not Applicable' Not Applicable b.
Automatic factuation Logic Not Applicable Not Arpiicable Containment Pressure--High 5 1.5 psig s 2.4 pa19 c.
-l, k
d.
Pressurizer Pressure-Low 1 1845 psig 2 ie,10 ps ig lg w
e.
Steamline Pressure-Low
> 500 psig steam
> 4td psig' steam
-l.
/,
line pressure line pre vure w
+
8 Bn 0
v.
o
,y
.s.-
+,,
e
.s~
,_p._.:..
.a.,._
.P TA111.E 3.3-4 (Continued) tn E
y ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUNENTATION TRIP SETPOINTS -- -
38 N*
FUNCTIONAL UNIT TRIP SETPOINT ALLO 4&BIE VAIAJES 1.1 SAFETY INJECTION-TRANSFER FROM 8
INJECTION TO-THE RECIRCUIATION
+
r NODE a.
Manual Initiation Not Applicable Not Applicable b.
Automatic Actuation Ingic Not Applicable Not Applicable coincident with Safety w
}
Injection Signal y
c.
Refueling Water Storage Tank 18'8-1/2" 1 18'2-1/2" and 5 19'2-1/2" l w
Level-Iow w>
E 9'0" and a 10'0" d.
Refueliseg Water Storage Tank 9'6" Level - Auto QS Flow Reduction i
a
,8, O
G, u
~
~
TAllLE 3.~1-4 (Continued) m>
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION ' TRIP SETPO
- o
- t*
t*
M k
FUNCTIONAL UNIT TRIP SETPOINT ALIDUABLE VAINES I
2.
CONTAINMENT SPRAY-
~
czy a.
Manual Initiation Not Applicable Not Appl-icable w
b.
Automatic Actuation Logic Not Applicable-Not Applicable i
Containment Pressure-High-High
$ 8.0'psig 5 8.9 psig.
~
l~-
c.
w 3.
CONTAINMENT ISOIATION D
a.
Phase "A" Isolation w"
1.
-Manual.
. Not Applicable Not Applicable s
1 2.
From Safety Injection Not Applicable Not. Applicable-
- Automatic Actuation. Logic i
b.
Phase "B"~ Isolation
't 1.
Manual.
Not Applicable Not Applicable f
s 2.
Automatic Actuation logic Mot Applicalzle
.. Not Applicable E
g 3.
Contairnment Pressure--
1 8.0 psig.
5 8.9.psig l
5 g
High-High
~
5 M
Y e
x U"
" m
-..m i.
a'~..
1 J
r h.-- J'#
. :^
y TAtsLE 3.3-4 fContinued)-
~
W S
j ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUNENTATION TRIP SETPOINTS '.
FUNCTIONAL UNIT TRIP SETPOINT ALIDWABLE VarinES N
4.
STEAM LINE ISOIATION
^
I s
a.
Manual Not App *licable Not Applicable zy b.
Automatic Actuation Ingic Not Applicable Not Applicable w
c.
Containment Pressure--
5 3.0 psig 1 3.9 psig-
. l Incernediate-High-High d.
Steamline Pressure-Low 2 500 psig steam 2 488 psig steam l
line pressure line pressure e.
High Negative Steam Pressure
$ 100 psi with a time 5 127 psi with a-time
-l Rate w
constant 2 50 seconds constant > 50 seconds 8
5.
TURBINE TRIP AND FEEDWATER ISOIATION 1
a.
Steam Generator Water Level 5 75% of narrow range
$ 76.9%of narrow range l
High-High instrument span each instrument span each j
steam generator steam generator
~
6.
IDSS OF POWER i
a.
1.
-4.16kv Emergency Bus 2 75% of nominal bus 2 73% of nominal' bus l=~
l Undervoltage (Ioss of voltage with a 1 1 0.1 voltage with a 1 1 0.1 Voltage) (Trip Feed).
second time delay second' time delay a"
2.
4.16kv Emergency Bus f
(Start Diesel) 2 83% - 12 cycles 2 81% of nominal bus-voltage-U b.
4.16kv Emergency Bus Undervoltage 2 90% of nominal bus
~2 b8% of nominal bus l
(Degraded voltage)
C voltage with a 90 1 5.
voltage with a 90 1 5 second time delay second'. time delay w
c.
480v Emergency Bus.Undervoltage.
2 90% of nominal bus ~
2 88%.of nomina 1-bus l
~
~
(Degraded Voltage) voltage'with a 90.1 5 voltage with:a 90.t 5 second time delay.
second tinne de1.sy'
-~
+
=
m i-,._.;._..
..~.A
l
' "';s TAllLE '3. 3-4 (Continued)
M>
-y ENGINEERED SAFETY FEATURE AC'IVATION SYSTEN INSTP.. MENTATION TRIP SETPOINTS '
t~
t~
M FUNCTIONAL UNIT TRIP SETPOINT ALIDNABIE VAINES I
C 5
7.
AUXILIARY FEEDNATER e
e a.
Steam Generator Water Level-low-low 2 12% of narrow range 2 10.7% of narrow range'll instrument span each instrument span each steam generator steam generator b.
Undervoltage - RCP 2 2750 volts RCP bus 2 2687 volts RCP bus l.
voltage voltage w
1 c.
S.I.
See'I above (all SI Setpoints) d.
Emergency Bus Undervoltage 5 3350 volts 5 3325 volts e.
Trip of Main Feedwater Not Applicable Not Applicable g
Pumps E
R E
!?
?
ww s
__