ML20106B244
| ML20106B244 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/25/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20106B249 | List: |
| References | |
| NUDOCS 8502110514 | |
| Download: ML20106B244 (11) | |
Text
.
o,,
UNITED STATES 4
g NUCLEAR REGULATORY COMMISSION 5
- E WASHINGTON, D. C. 20555
?,
DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY l
PENNSYLVdNIAPOWERCOMPANY DOCKET N0. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Comission) has fo;nd that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsyl.vania Power Company (the licensees) dated June 28, 1984, 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 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 Comission'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 tha public; and E.
The issuance.of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all appl.icable' requirements have been satisfied.
2.
Accordingly, the licen'se 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:
2Qho p
P 9
(2)- Technical Specifications 5
The Technicil Specifications contained in Appendices
. A and.8, as revised through Amendment No. 90, are hereby. incorporated in the license. The~ licensee shall operate the facility in acco..7ce with the Technical Specifications.
3.-
This license amendment is effective on issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h
)
arga f
Operating Reactors nch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 25, 1985 1
.e O
r
-e,t
~.-
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT N0.
9010 FACILITY OPERCING LICENSE NO. OPR-66
. DOCKET N0. 50-334 l
Revise Appendix A'as follows:
Remove P' ages Insert Pages 3/4 3-19a 3/4 3-19a 3/4 3-24 3/4 3-24 3/4 3-24a 3/4 3-24a 3/4 3-27a 3/4 3-27a 3/4 3-28 3/4 3-28 3/4 3-31a 3/4 3-31a 3/4 3-66 3/4 3-66 3/4 3-67 3/4 3-67 I
e S
e e
1 2
e-e
~
e
-Q-
+ - +,
t i
r TABLE 3.3-3 (Continued) i I
h ENGINEERED SAFETY IEATURE ACTUATION SYSTEM INSTRUMENTATION
,1
- =>
MINIMUM g
TOTAL NO.
1 CilANNELS CilANNELS APPLICABLE p
FUNCTIONAL UNIT OF CHANNELS 10 TRIP OPERARLE MODES ACTION e
7.
' AUXILIARY FEEDWATER c:
Steam Gen. Water Level-Low-Iow
~
a.
((.oop Stop Valves Open) 1.
Start Turbine
'l Driven Pump 3/sta. gen.
2/sta. gen. - 2/sta. gen.
I, 2.- 3 14 any sim. gen.
i
- 11. Start Motor Driven Pumps 3/sta. gen.
2/sta. gen.
2/sta. gen.
1, 2, 3 14 any 2 stm. gen,
,s
[
b.
Undervaltage-RCP (Start
.f.
Turbine Driven Pump)
(3)-1/ bus 2
2 1
14
.o
~
c.
S.I. (Start Motor-Driven Pumps)
See I above (all S.I. Initiating functions and requirements)
.d. - Turbine Dr'Iven Pump Discharge Pressure Low (2)-1/ Train i
1 1, 2, 3 18 With Steam. Valve Open -
(Start Motor-Driven Pump) k Eme*rgency Bus Undervoltage e.
a (Start Motor Driven 1/ bus 1
1 1, 2, 3
'18 s
g Pumps)
- s
'r+
f.
Trip of Main Feeduater Pumps - (Start Motor
=
P
.DrivenPumps) 1/ pump 1
1 1,2,3 18 i
- 8 4
e e
i e
TABLE 3.3-4 (Eontinued)
ENGINEERED SAFETY FEATURE ACTUAi!0N SYSTEM INSTRUMENTATION TRIP SETPOINTS u,
i
'3 ?
j el IUNCTIONAL UNIT TRIP SEIPOINT ALLOWABLE VALUES.
m i
.4.
STEAM LINE ISOLATION "J
a.
Ma'nual No't Appilcable Not AppItcable i
b.
Automatic Actuation Logic Not Appilcable Not,Applic.ule
e O"
c.
Containment Pressure--
~
Intermediate-High-High f 5.0 psig 4 5.5 psig d.
Steamilne Pressure-Low 2500 psig steam
> 480 psig steam IIne pressure-line pressure.
e.
liigh Negative Steam Pressure
$100 psi with a time
$_110 psi with a tisine Rate constant h 50 seconds constant h 50 seconds 5
5.
TURBINE TRIP AND FEE 0 WATER ISOLATION a '.
Steam Generator leater Level f 751 ef narrow range 4 76% of narrow range
~
Illsh-liigh Instrument span each steam instrument span each steam 9enera tor generator 6.
LOSS OF POWER 4.16'y Emergency Bus 175% of nominal bus
& 74% of nominal bus k
a.
1.
Undervolta e (Loss of Voltage) voltage with a 1 10.1 voltage with a 1 1 0.1 (Tripfeed second time delay second time delay 2.
4.16ky Emergency Bus t 831 - 12 cycles t
3
'(StartDiesel) 4 ca.
a
+ 31 b.
4.16'kv Emergency Bus 901 - 01 of nom'r..: bus 2 891 of nominal bus thodervol tage _ (Degraded. Vol tage) voltage wl*j. a 90 1 5 voltage with a 90 1 5 g
secoM stee delay second time delay E
+ 31 480v-Emerg'ency Dus Undervoltage 901 - 0% of nominal bus h 891 of nominal bus c.
(Oegraded voltage) voltage with a 90 1 5 volt ~ age with_a 90 1 5 second time delay second time delay
_ = -
c 7
2 Bi n
TNIIE 3.3-4 (Continued)
?
E DCINEEIED SAEErY MWitNE EnWrIG4 SYSTIM Ilet1tHWrATIGI 11tIP SIM1OINIS '
EINCTIG4hb LMIT 11tIP SEITOINF h!JIJWAINE VAI1JES y
7.
AtlXII.IARY FEEI5MtHL a.
Steam Generator 212% of narrow range klii c' narrow range Water Idvel-low-low instnuient spe.i cach instrtusent span each steam generatt)r,-
steam gescrator b.
thwiervoltage - ICP 22750 volta ICP bus voltage 2 2725 volts IEP bus voltage w
c.
S.I.
See 1 above (all SI Setpoints) w da d.
1brbine Driven Ptusp 2468 psig-2 452 psig Discharge Pressure Im e.
Energency Bus tht.iervoltage
$3350 volts
$ 3325 volts-f.
Trip of Main Feedwater Pumps Not Applicable Not 4plicable e
(D 3
'~
,+
2 m
O 1
6 e
a
DEI.E 3.3-5 (Q:ri dnued)
~
IRmmu SA3 TIT FIAIt3ElS ESKESE "lMES INITDC'ING SIGNAL *AND It2CICN RESPCNSE TIME IN SE:DCS r
- 11. Steam 'Ge:erater Water IAvel-ICW-1cW
~
a.
Luulven P-v'1 d = y 60.0 Feedwater Purps**'
b.
w4W.ven h v'"=7 60.0 Fembater W ***
- 12. Underveltaae RCP a.
Tc= hine-driven At. W 60.0 Feedwater Pumps
- 13. Bneroency Bus underveltace l
a.
Motor driven PO 4='y 60.0 Feschater Pumps i
t 14., Trip of Main Feedwate P=s i
t l
a.
L A ". riven W 14="f 60.0 Feechster Pu::ps t
- 15. Tctaine Driven PL.:o Discharte Ea'asure low l
a.
Mven W14=7 60.0 Feschater Pumps I
4 l
NOTE:
Beepcmse tirm for letor-driven 60.0 W 14= 7 Feedwater Punps en all S.I. signal starts
- cn 2/3' any Steam Generatcc
- cm 2/3 in 2/3 Steam Generators 1
EAV.U. SEI.IY - t2 TIT 1 3/4 3-27a Amenoment No. 90 e
1 0
9 7
e v
g y
.., ~
c m,
y y.,, _
y
_.-,n 9
.,_,g
TABLE 3.3-5 (Continued) -
TABLE NOTATION e
Diesel ' generator starting and sequence leading delays included.
Response time limit includes opening of valves to establish SI path and attainment of discharge' pressure for centrifugal charging.
pumps and Low Head Safety Injection pumps.
Diesel generator startin
!. Offsite power available.g and sequence loading delays g included.
Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
ff Diesel generator starting and sequence loading delays included.
Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
(1) Feedwater system overall response time shall inclu'de verification of valve stroke times applicable to the feedwater valves shown for penetrations 76, 77 and 78 on Table 3.6-1.
i l
a EEAVER VALLEY - Uti1T 1 3/4 3-28 Amendment No. 90
- l 6
l t
s i
Ng ps
[
TNME '4.3-2 (Continued) t*
2 Il I!NGINEEIWD SAFETY E7JttURE hCItihTIG4 SYSliiH INS 11EMNFATIO4 e
5 fi SUlWEIIJANLY. IWX1UIRINNIS
- OINGH, M mI!S IN HIIOl OIMHL ORARE..
FIMCTIONAL SUlWEIIJANCE FIMCTI(NRL IMIT OIEKX CALIEWATIGE TESP RIUlIIED 7.
AUKILIARY FEHE5fl1!R M
a.
. Stessa Generator hter
^
level-fae-Ima S
R H
1, 2, 3 Y
[
b.
Undervoltage - HCP S
R M
1, 2 c.
S.I.
See 1 above (all SI surveillance requirements) d.
1brbine-driven Ptsp Discharge IYmwe Int N/A R
R 1, 2, 3 e.
Baergency Dus-N/A R
R 1, 2, 3 Undervoltage.
>Bg f.
Trip of Ma'n g
Feedwater Fumps N/A N/A R
1, -2, }
co 3
1 2
O i
o t
i
+
t e
e
p 4
TABLE 4.3-13 (Continued)
RADICACTIVE CASE 005 EFFLUENT MNitTORilIG INSTRiNIENTATI0ll SURVEILL411CE REQUIREMENTS hs CllAIINEL
-Q CllAfeML SOURCE.
CilAllllEL FQNCT10NAL
~
IllSTRINNT CilECK CilECK CALIBRATION TEST
~
e.
Sampler Flow Rete -
D N/A R
'Q,
3.
lleactor Building / Supplementary Leak Collectfon and Release System (IIM-VS-107A & B) a.
Iloble Gas Activtty Montto:-
D M(5).P(5)***R(3)-
Q(2) l b.
Iodfue Sampler Cartridge' U(6)
N/A N/A N/A
[
c.
Particulate Activity Monttor U
N/A N/A N/A E
d.
System Effluent Flow Rate -
D N/A R
q leasuring Device (FR-VS-112) e, Sampler Flow Rate Measuring Device D
N/A R
,Q 4.
Waste Gas Decay Tanks Montter k
a.
Oxygde Monttor D
N/A g(4)
, M; (0 -AS-GH-110-1,2) g 2
N
- b. * (tedIat'fon Moniter (llM-CN-101)
D**
M(5)
R(3) g(2) l
~
.e i
c.
Sampier Flow Rate Measuring Device D**
N/A R
Q
. o e
~~
TABLE 4.3-13 (Continued)'
{,
TABLENOTATI$N During releases via this pathway 4
During Waste Gas Tank filling operations i
During purging of Reactor Containment via this pathway 1
1 (1). The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic 1
isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:
4 l
i a.
Instrument indicates measured levels above the alann/ trip i
setpoint.
i b.
Downscale failure.
I c.
Instrument controls not set in operata mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control 4
room alarm annunciation occurs if any of the following enditions exist:
~
a.
Instrument indicates measured levels above the alarm / trip j
setpoint.
b.
Downscale failure.
c.
Instrument controls not set in operate mode.
l t
(3) The initial CHANNEL CALIBRATION for radioactivity' measurement i
instrumentation shall be perfomed using one or more of the reference standards certified by the National Sureau of Standards i
or using standarcis that have been obtained ~ from suppliers that j
participate in measurement assurance activities with N85.- These standards should permit calibrating the system over-its intended r
range of energy and rate capabilities.
For subsequent CHANNEL i
CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per eighteen months.
This can normally be accomplished during 4
l refueling cutages.
1 b
~
i BEAVER VALLEY - UNIT 1 3/4 3-67 Amendment No. 90 i
4 I
1 s
3
--w--.---
w,..w-e
,y---%g---gw
--ma w-s.,
--g gc-3 w
e y
-w ity yww.-wvy 9
v-
,----iv-up---+-emur
-awe-W
1 TABLE 4.3-13 (Continued)
S:
g RADI0 ACTIVE GASEOUS EFFLUENT MNilTORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
- =.
h CllAINtEL p
CilANNEL SOURCE CilAllllEl FilNCTIONAL Ills 1RUMElli CilECK CilECK CALIBRATION TEST E
e.
Sampler Flow Rate -
D N/A R
'Q - -
3.
Reactor Building / Supplementary Leak Collection and Release Systen (lut-VS-107A & 8) a.
Hoble Gas Activity Honitor D
M(5) P(5)*** R(3)*
Q(2) l.
b.
Iodine Sampler Cartridge' W(6)
N/A N/A N/A m
c.
Particulate Activity Honitor W
N/A N/A N/A E
d.
Systen Effluent Flow Rate D
N/A R
q heasuring Device (FR-VS-112) e.
. Sampler Flow Rate Measuring Device D
N/A R
,q 4.
Maste Gas Decay Tanks Monitor k
a.
Oxygen Monitor D
N/A q(4)
, M;' '
g (0-AS-GW-110-1.2) 2 B
g
- b. ' liedIat'lon Monitor (RM-GW-101)
Da*
H(5)
R(3)
Q(2) l g
c.
Sampler Flow Rate Heasuring Device D**
I:/A R
q O
I as m
-