ML20195E457
| ML20195E457 | |
| Person / Time | |
|---|---|
| Site: | Cooper  (DPR-46-A-121) |
| Issue date: | 06/13/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20195E460 | List: |
| References | |
| NUDOCS 8806240054 | |
| Download: ML20195E457 (11) | |
Text
'
o UNITED STATES n
~
NUCLEAR REGULATORY COMMISSION h
- E WASHINGTON, D. C. 20555 t
%,... /e NEBRASKA PUBLIC POWER DISTRICT DOCKET N0. 50-298 COOPER NilCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 121 Licer.se No. OPR-46 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated February 2, 1988, complies with the standards and requirements of the Atomic Erergy 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 confortnity with the application, as anended, 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 license amendment will not be inimical to the l
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 applicable requirements have l
been satisfied.
i 8806240054 000613 PDR ADOCK 05000290 P
PDR i
2.
Accordingly, the license is anended 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. CPR-46 is hereby amended to read as follers:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.121, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of isseance.
FOR THE NUCLEAR REGULATORY COMMISSION
[e + c. '
6.
(N 6 ; s-Jcse A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reacter Regul6 tion
Attachment:
Changes to the Technical Specifications Date of Issuance: June 13,1988 l
l
ATTACHMENT TO LICENSE AftEf;CFEliT l'O.1?l FACILITY CPE, RATING LICENSE NO. DPR-46 DOCKET NO. 50-998 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Page:.
10 53 54 55 56 70 71 73 l
GEMAC 91675"
- 400*
i IN.
850".
84815"-
332' (N S TRtACiT TAP
- g~
RE ACTOR
- e5"E TA%
.d 750"-
722.25' VESSEL FLA E 70 6-ROSEMOUNT 69256 STEAM 34o" N0ZZLg RANGE 650"- 6400* gag LINE L I.9 2 ROSEMOUNT
,,~
YARwAY GEM C
)
I33 577.56./
8ARTON YARWAY
- +2 25
- 60=
- HPCI 8 :-. 60"-- -
+ 60* 576 #
+ 60
-575 25(8)
-559 25 ( 7) ylj T58 Sl8) 42.5 %HIALARM
- 9 2 (3)
REACTCR 4
g
)
- gh,--"y-- 3 "#-
2 *-- - ' ~ 0"- - 516.75" 0"
INSTRus,0ff D- 0" -
0 500 ZERO (9 43512.5 6 160" Lis lot tg.94
(-FEED WATM d,-.
473 p(2)
. 37"(27 (9 5)
.d.10 INITIATE RCIC, HPCI, 450".
TRIP RECIRC. PtJAPS 1
1 400"-
1 l
-371.25 (1) 44 5.5* (l)
.4 50" '--INI TIA TE RH R, C. S.,
.. 150" 366.75" TAF+ 152.56 <
O.
350" 352.56,,
STA R T OIESEL 8 CO M BUTE T AE S.
EhL$i (931'.6")
[
LI 35 31 5'-
39' J
(9
- 5I IN STRU MEN T 2/3 30 6-S RACK CCRE HEIGHT g"
( 25 5 4 25 6)
PERMIS$1W 250"-
h
- t WATER LEVEL NOMENCLATURE 202*6*
.gg-y 200.
208 56,,
LEVEL HEIGHT ABCNE INSTRUMENT HT ABOVE
" E LI8 1
(
NO.
WSSEL ZERO READING TAF 3
161.5* {yRC
{ jn,}
(jn)
N0ZZLE 150"-
N0ZZLE
,,r--
(3) 575.25 58.5 22269
( 7) 559.25 42.5 206.69 (4)
!44.25 27.5 191.69 100"-
(3) 529.25 12.5 176 69 (2) 479.75 37 127 19 (1) 371.25 34 5.5 18.69 O*
E LE V ATION 917 '.~D *
~
VESSEL BO T TO M FIGURE 2,l.1 8802110282 880202 REACTOR WATER LEVEL INDICATON CORRELATION PDR ADOCK 05000298
.jg.
P pon Amendment NO. 87. 200,121
COOPER NUCLEAR STATION TABLE 3.2.B (PACE 1)
CIRCUITRY REQUIREMENTS CORE SPRAY SYSTEM Minimum Number of Action Required %' hen Instrument Operable Components Component Operability Instrument I.D. No.
Setting Limit Per Trip System 1s Not Assured (1)
Reactor Low Water NBI-LIS-72 A, B, C,
>-145.5 of Indicated 2
A Level
&D Level Reactor Low Pressure NBI-PS-52 Al, A2, 1450 psig 2
A C1, & C2
'NBI-PIS-52 B & D 4
Drywell High Pressure PC-PS-101. A, B, 12 psig 2
A C&D Core Spray Pump CS-PS-44, A & B 2
A Disch. Pressure CS-PS-3 7, A & B 100 1 P 1 165 psig Core Spray Pump CS-TDR-K16 91T111 seconds 1
B a$
Time Delay A&B
- a p
Low Voltage Relay 27XI - IF & 1G Loss of Voltage 1
B Emerg. Bus 27X2 - IF & 1G Aux. Bus Low 27X3 - IA & IB Loss of Voltage 1
B Voltage Relay Pump Discharge Line CM-PS-73, A & B
>10 psig (3)
D Low Pressure S
R E
E.
1 i
-.e I
COCPER NUCLEAR STATION TABLE 3.2.8 (PAGE 2)
RESIDUAL HEAT REMOVAL SYSTEM (LPCI MODE) CIRCUITRY REQUIREMENTS Minimum Number of Action Required k' hen Instrument Operable Components Component Operability Instrument I.D. No.
Setting Limit Per Trip System (1)
Is Not Assured Drywell High Pressure PC-PS-101 A,B.C
& D
<2 psig 2
A Reactor Low Water NBI-LIS-72, A,B,C, 3-145.5" Indicated 2
A Level
& D #1 Level Reactor Vessel Shroud
'NBI-LITS-73, A & 3 3-39 Indicated 1
B Level Below Low "il Level Level Trip Reactor Low Pressure RR-PS-128, A & B
<75 psig i
B Reactor Low Pressure NBI-PS-52Al,A2,Cl&C2
<450 psig 1
A (Injection Valve NBI-PIS-52B & D Permissive) e Drywell Pressure PC-PS-119, A,B,C,
<2 dsig 2
&D RHR Pump Discharge RHR-PS-120, A,B,C,6D 100 < P < 165 psig 2
A RilR-PS-105, A,B,C,&D 100 < P < 165 psig 2
A Reactor Low Pressure NBI-PS-52A & C 185 < P < 235 psig 1
A (Recirc. Discharge NBI-PIS-52B & D Permissive) g 2~
C.
COOPER NUCLEAR STATION TABLE 3.2.B (PAGE 3)
RESIDUAL llEAT REMOVAL SYS~lEM (I.PCI MODE) CIRCUITRY REQUIREMENTS Minimum Number of Action Required When Instrument Operable Components Component Operab'111ty Instrumient I.D. No.
Setting I.f r, ' t l'er Trip System (1) 1s Not Assured Rilk Pump I.ow Flow RilR-dPIS-115 A & B
>2500 gpm 1
A Time Delays RHR-TDR-K45, IA&lB 4.251T15.75 min.
1 A
RilR Pump Start RHR-TDR-K75A & K708 4.51T35.5 Sec.
1 A
Time Delay RilR-TDR-K75B & K70A 1 5 sec.
I A
RiiR Heat Exchanger RHR-TDR-K93, A & B 1.83T<z.2 min.
I B
Bypass T.D.
RilR Crosstie Valve RHR-LMS-8 Valve Not closed (3)
E Position Bus IA Low Volt.
27 X 3/lA Loss of Voltage 1
B Aux. Relay Bus IB Low Volt.
27 X 3/IB Loss of Voltage 1
B 4
Aux. Relay Y
Bus IF Low Volt.
27 X 1/lF I.osg of Voltage I
B Aux. Relays 27 X 2/lF I.oss of Voltage i
B Bus IG Low Volt.
27 X 1/lG Loss of Voltage 1
B Aux. Relays 27 X 2/lG Loss of Voltage Pump Discharge Line CM-PS-266
>$ psig (3)
D CM-PS-270
>l5 psig (3)
D Emergency Buses 27/IF-2, 27/IFA-2 3600 15%
2 B
Undervoltage Relays 27/lG-2, 27/lGB-2 8 second 12 sec.
2 B
(degraded voltage) time delay 1
B g-Emergency Buses I.oss 27/lF-1, 27/lFA-1, 2900V 15%
g of Voltage Relays 27/ lG-1, 27/ ICB-1, 5 second il sec.
c+
27/ET-1, 27/ET-2 delay 1
B f
Emergency Buses Under-27X7/lF, 27X7/lG, Voltage Relays Timers 10 second 12 sec.
I B
y*
COOPER NUCLEAR STATION TABLE 3.2.B (PAGE 4)
HPCI SYSTEM CIRCUITRY REQUIREMENTS Minimum Number Action Required When Instrument ol Operable Components Component Operability Instrument I.D. No.
Setting Limit Per Trip System (1)
Is Not Assured Reactor Low Water NBI-LIS-72, A,B,C,
>37" Indicated Level 2
A Level
& D #3 j
Reactor High Water NBI-LIS-101, B & D
<+58.5" Indicated Level 2(2)
A Level
- 2 High Drywell Press.
PC-PS-101 A.B.C, & D
<2 psig 2(2)
A HPCI Turbine High HPCI-PS-97, A & B
<l50 psig 1(2)
A Exhaust Pressure HPCI Pump Low HPCI-PS-84-1
<l5" Hg Vacuum 1(2)
A Suction Press.
HPCI Pump Low HPCI-FS-78
>400 gpm 1(2)
A
,g Discharge Flow a
D HPCI Low Steam HPCI-PS-68, A,B,C
>100 psig 2(2)
A Supply Pressure
&D HPCI Steam Line HPCI-dPIS-76 130 <S<210" H 0 1
A
,130[S[-210"y High AP HPCI-dPIS-77 H0 HPCI Steam Line HPCI-TS-101, A,B,C &
<200*F 2(4)
A g
Space Hi Temp.
D -102, 103, 104, o
HPCI-TS-125.126,127,128 i
RHR-TS-150,151,152,153 154,155,156,157,158,159 3
160,161 f
Emerg. Cond. Storage HPCI-LS-74 A & B
>0" H,0 (10,000 gal.
1(2)
A e
Tank Low Level HPCI-LS-75 A & B usable remaining)
M
COOPER NUCLEAR STATION TABl.E 4.2.B I age 1)
CORE SPRAY SYSTEM TEST & CALIBRATION FREQUENCIES Instrument Item Item I.D. No.
Functionsi Test Freq.
Calibration Freq.
Check Instrument 1.
Reactor Low Water Level NBI-LIS-72, A.B.C, & D Once/ Month (1)
Once/3 Months Once/ Day 2.
Reactor Low Pressure NBI-PS-52, Al,A2 C1, & C2 Once/ Month (1)
~0nce/3 Months None NB1-PIS-52, B & D 3.
Drywell High Pressure PC-PS-101, A,B,C, 6 D Once/ Month (1)
Once/3 Months None 4
Core Spray Pump Disch.
CS-PS-44, A & S Once/ Month (I)
Once/3 honths None Press.
CS-PS-37, A & B Once/ Month (1)
Once/3 Months None 5.
I Core Spray Pump Time Delay CS-TDR - K16, A & B Once/ Month (1)
Once/Oper.
None Cycle (4) 6.
Emergency Bus Low Volt Relay 27XI - IF & IG Once/Oper. Cycle Once/5 Years None 27X2 - IF & IG Once/Oper. Cycle once/5 Years None 7.
Aux. Bus Low Voltage Relay 27X3 - IA & IB Once/Oper. Cycle Once/5 Years None 8.
Pump Disch. Line Low Press.
CM-PS-73, A & B once/3 Months once/3 Months None
"?
Logic (4) (6) 1.
Logic Power Monitor Once/6 Months N.A.
N.A.
2.
l Core Spray Initiation Once/6 Months N.A.
N.A.
3.
Pump & Valve (Signal override)
Once/6 Months N.A.
N;A.
Control N
8 8-emm8
___._.m 1
COOPER NUCLEAR STATION TABLE 4.2.B (Page 2)
RHR SYSTEM TEST & CALIBRATION FREQUENCIES Functional Instrument Item Item I.D. No.
Test Freq.
Calibration Freq.
Check Instrumentation 1.
Drywell High Pressure PC-PS-101, A, B, C & D Once/ Month (1) Once/3 Months None 2.
Reactor Vessel Shroud Level NBI-LITS-73, A & B f1 Once/ Month (1) Once/3 Months Once/ Day 3.
Reactor Low Pressure RR-PS-128 A & B Once/ Month (1) Once/3 Months None 4.I Reactor Low Pressure NBI-PS-52 Al.A2.Cl, & C2 Once/ Month (8) Once/3 Months None NBI-PIS-52 B & D 5.
Drywell Press.-Containment PC-PS-Il9, A,B,C & D Once/Monti-
) Once/3 Months None Spray 6.
RHR Pump Discharge Press.
RHR-PS-120, A.B.C & D Once/ Month (1) Once/3 Months None 7.
RHR Pump Discharge Press.
RHR-PS-105, A,B,C & D Once/ Month (1) Once/3 Months None 8.
RHR Pump Low Flow Switch RHR-dPIS-125 A & B Once/ Month (1) Once 3 Months None 9.
RHR Pump Start Time Delay RHR-TDR-K70, A & B Once/ Month (1) Once/Oper. Cycle None
,g 10.
RHR Injection Valve Close T.D.
RHR-TDR-K45 1A & IB Once/ Month (1) Once/Oper. Cycle None a
11.
RHR Pump Start Time Delay RHR-TDR-K75, A & B once/ Month (1) Once/Oper. Cycle None 12.
RHR Heat Exchanger Bypaar T.D.
RHR-TDR-K93, A & B Once/ Month (I) Once/Oper. Cycle None 13.
RHR Cross Tie Valve Position RHR-LMS-8 Once/ Month (1)
N.A.
l 14.[ Low Voltage Relays 27 X 3/lA (7)
None 15.
Low Voltage Relays 27 X 3/18 (7)
None 16.
Low Voltage Relays 27 x 2/IF, 27 X 2/IC
( 7)
None 17.
Low Voltage Relays 27 X 1/lF, 27 X 1/IC (7)
None 18.
Pump Disch. Line Press. Low CM-PS-266, CM-PS-270 Once/3 Months once/3 Months None 19.
Emergency buses Undervoltage 2 7/ l F-2, 2 7/ l FA-2, 2 7/ IC-2, Once/ Month once/18 Months once/12 hrs.
N Relays (Degraded Voltage) 27/ICB-2 20.
Emergency Buses Loss of 27/lF-1, 27/lFA-1, 27/IC-1, Once/ Month once/18 Months Once/12 hrs.
Voltage Relays 2 7/ ICB-1, 27/ET-1, 27/ET-2 21.
Emergency Buses Undervoltage 27X7/lF, 27X7/lG Once/ Month once/18 Months None Relays Timers
.o t!2 i
N I
1 1
l
COOPER NUCLEAR STATION TABLE 4.2.B (Page 4)
IIPCI TEST & CALIBRATION FREQUENCIES Functional Instrument Item item 1.D. No.
Test Freq.
Calibration Freq.
Check 1.
Reactor Low Water Level NBI-LIS-72 A,B,C, & D #3 Once/ Month (1) Once/3 Mont-Once/ Day 2.
Reactor liigh Water Level NBI-LIS-101. (B & D #2)
Once/ Month (1) Once/3 Montns Once/ Day 3.
liigh Drywell Pressure PC-PS-101 t., B, C & D (7)
(7) None 4.
IIPCI Turbine High Exhaust itPCI-PS-97 A & B Once/ Month (1) Once/3 Months None Press.
5.
IIPCI Pump Low Suction Press.
HPCI-PS-84-1 Once/ Month (1) Once/3 Months None 6.
HPCI Pump Low Discharge Flow HPCI-FS-78 Once/ Month (1) Once/3 Months None 7.
HPCI Low Steam Supply Preis.
HPCI-PS-68, A,B,C, & D Once/ Month (1) Once/3 Months None 8.I HPCI Steam Line liigh AP llPCI-dPIS-76 Once/ Month (1) Once/3 Months None
.;PCI-dPIS-77 Once/ Month (1) Once/3 Months None 9.
HPCI Steam Line Space High IIPCI-TS-101, A.B.C. & D Once/ Month (1) Once/Oper. Cycle None Temp.
102, 103, 104, llPCI-TS-125, 126, 127, 128 RilR-TS-150,151,152,153,154, 155,156,157,158,159,160,161 6
10.
Emergency Cond. Stg. Tk. Low HPCI-LS-74 A & B Once/ Month (1) Once/3 Months None i'
Level HPCI-LS-75 A & B Once/ Month (1) Once/3 Months None 11.
Suppression Chamber High HPCI-LS-91 A & B once/ Month (1) Once/3 Months None Water Level 12.
HPCI Cland Seal Cond. Hotwell HPCI-LS-356 B Once/Moath (1) Once/3 Months None Level HPCI-LS-356 A once/ Month (1) Once/3 Months None 13.
HPCI Control Oil Pressure Low HPCI-PS-2787-H Once/ Month (1) Once/3 Months None HPCI-PS-2787-L once/ Month (1) Once/3 Months None 14.
Turbine Condition Supr. Alarm HPCI-TDR-K14 Once/ Month (1) Once/Oper. Cycle None 3f Actuation Timer 15.
Pump Disch. Line Low Press.
CM-PS-268 Once/3 Months once/3 Months None
@f 16.
IIPCI Turbine Stop Valve Hon.
HPCI-LMS-4 Once/ Month N.A.
None 17.
Sup. Chamber HPCI Suction Viv.
HPCI-LMS-2 Once/ Month N.A.
None 18.
HPCI Steam Line High AP HPCI-TDR-K33, once/ Month Once/Oper. Cycle None Actuation Timer llPCI-TDR-K43 Once/ Month once/Oper. Cycle None
- g Logic (4)(6)
Logic Bus Power Monitor Once/6 Months N.A.
2.
IIPCI Initiation Once/6 Months N.A.
ta 3.
IIPCI Turbine Trip Once/6 Months N.A.
m
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _