ML17146A322
| ML17146A322 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/01/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17146A323 | List: |
| References | |
| NUDOCS 8604080531 | |
| Download: ML17146A322 (17) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 25 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power Light Company, dated December 19, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endanqering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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 Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No.
NPF-22 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 25 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.
PP&L shall operate the facility in accordance with the Technical Specifi-cations and the Environmental Protection Plan.
860408053i 860q0i PDR ADOCK 05000388 P
3.
This amendment is effective upon startup following the Unit 2 +irst refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
4%
9 l gy Elinor G. Adensam, Director BWR Proiect Directorate No.
3 Division of BWR Licensing
0
ATTACHMENT TO LICENSE AMFNDMENT NO. 25 FACILITY OPERATING LICFNSE NO.
NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE 3/4 3-11 3/4 3-12 3/4 3-17 3/4 3-18 3/4 3-21 3/4 3-22 3/4 3<<23 3/4 3-24 3/4 6-19 3/4 6-20 B3/4 3-7 83/4 3-8 INSERT 3/4 3-11 (overleaf) 3/4 3-12 3/4 3-17'/43-18 (over leaf) 3/4 3-21 3/4 3-22 (overleaf) 3/4 3-23 (overleaf}
3/4 3-24 3/4 6-19 3/4 6-20 (overleaf) 83/4 3-7 (overlea<)
83/4 3-8
TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION TRIP FUNCTION 1.
PRIVY CONTAINMENT ISOLATION ISOLATION SIGNAL S a
MINIMUM OPERABLE CHANNELS PER TRIP SYSTEM b
APPLICABLE OPERATIONAL CONDITION ACTION aO Reactor Vessel Mater Level 1)
Low, Level 3 1j2j3 20 2.
2)
Low Low, Level 2 3)
Low Low Low, Level 1 b;
Drywell Pressure - High c.
Manual Initiation d.
SGTS Exhaust Radiation-High e.
Main Steam Line Radiation-High SECONDARY CONTAINMENT ISOLATION X
Y,Z NA 1 j 2 j 3 1, 2, 3 1, 2, 3
1, 2, 3
20 20 20 24 1, 2, 3 20
]
2 3
4~~*
5*** 20 O
a.
b.
C.
d.
e.
Reactor Vessel Mater Level-Low Low, Level 2 Drywell Pressure - High Refuel Floor High Exhaust Duct Radiation - High Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Mall Exhaust Duct Radiation - High Manual Initiation 2
1 I, 2, 3and*
1.2 3
1, 2, 3 and
- 25 25 25 25 24
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION MINIMUM ISOLATION OPERABLE CHANNELS
~)Y
'R
'"I)
TRIP FUNCTION I
'I R
3-MAIN STEAM LINE ISOLATION a.
Reactor Vessel Water Level-Low Low Low, Level 1
b.
Main Steam Line Radiation-High c.
Main Steam Line Pressure
- Low d.
e.
g.
h.
Main Steam Line Flow - High 0
Condenser Vacuum - Low UA Reactor Building Main Steam E
Line Tunnel Temperature - High Reactor Building Main Steam E
Line Tunnel b, Temperature - High Manual Initiation NA 2/line i.
Turbine Building Main Steam Line E
Tunnel Temperature - High 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION APPLICABLE OPERATIONAL CONDITION 1, 2, 3
1 2.3 1, 2, 3
1, 2, 3
1, 2, 3
1.2 3
1 2.3 1,2,3 ACTION 21 21 22 20 21 21 21 24 21 O
a.
b.
C.
d.
e.
g.
RWCU h, Flow - High RWCU Area Temperature - High RWCU Area Ventilation 6 Temperature - High SLCS Initiation Reactor Vessel Water Level - Low Low, Level 2
RWCU Flow - High Manual Initiation J
NA
~ 2 2
1, 2, 3
1, 2, 3
1, 2, 3
1 2
3 1
2 3
1, 2, 3
1, 2, 3
23 23 23 23 23 23 24
TABLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION TRIP SETPOINT ALLOWABLE VALUE a 0 b.
C.
d.
e.
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1 Drywell Pressure - High Manual Initiation SGTS Exhaust Radiation - High Main Steam Line Radiation - High
>13.0 inches"
> -38.0 inches"
> -129 inches*
< 1.72 psig NA
< 23.0 mR/hr
< 3 X full power background
> ll 5 inches
> -45.0 inches
> -136 inches
< 1.88 psig NA
< 31.0 mR/hr
< 3.6 X full power background 2.
SECONDARY CONTAINMENT ISOLATION a.
b.
c ~
d.
e.
Reactor Vessel Water Level-Low Low, Level 2
Drywell Pressure - High Refuel Floor High Exhaust Duct Radiation High Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Wall Exhaust Duct Radiation - High Manual Initiation
> -38.0 inches"
< 1.72 psig
< 2.5 mR/hr*"
< 2.5 mR/hr*"
< 2.5 mR/hr**
NA
> -45.0 inches
< 1 88 psig
< 4.0 mR/hr""
< 4.0 mR/hr*"
< 4.0 mR/hr""
NA 3.
MAIN STEAM LINE ISOLATION ao b.
c d.
Low Low Low, Level 1
Main Steam Line Radiation - High Main Steam Line Pressure - Low Main Steam Line Flow - High
> -129 inches"'
3 X full power background
> 861 psig
< 107 psid
> -136 inches
< 3.6 X full power background
> 841 psig
< 110 psid
Vl t
AD TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS m
I M
TRIP FUNCTION MAIN STEAM LINE ISOLATION (Continued) e.
Condenser Vacuum - Low
. f.
Reactor Building Main Steam Line Tunnel Temperature - High g.
Reactor Building Main Steam Line Tunnel h Temperature - High h.
Manual Initiation TRIP SETPOINT
> 9.0 inches Hg vacuum 177oF
< 99'F NA ALLOWABLE VALUE
> 8.8 inches Hg vacuum
< 184 F
< 108 F
NA i.
Turbine Building Main Steam Line Tunnel Temperature - High
< 177 F
4.
REACTOR WATER CLEANUP SYSTEM ISOLATION
< 184 F
a.
b.
C.
d.
g.
RWCU h Flow - High RWCU Area Temperature - High RWCU/Area Ventilation h, Temperature - High SLCS Initiation Reactor Vessel Water Level-Low Low, Level 2
RWCU Flow - High Manual Initiation
< 60 gpm
< 147'F or 118.3 F¹ 69oF or 35 3oF¹ NA
> -38 inches" 426 gpm NA
< 80 gpm
< 154 F or 125.3 F¹ 78oF or 44 3oF¹ NA
> -45 inches 436 gpm NA I
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5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION O
b.
C.
< 10.0 psig RCIC Steam Line b, Pressure High
< 153" H>0""
RCIC Steam Supply Pressure
- Low
> 60 psig RCIC Turbine Exhaust Diaphragm Pressure
- High
< 165" HgO*"
> 53 psig
< 20.0 psig C
l!'
TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME
RESPONSE
TIME Seconds ¹
<iO(a)
<~.o /<io(')-
. <yO(a)
<io(')
NA
<yO(a)
<yO(a)
<yO(a)
<iO(a)
<yO(a)
<yO(a)
<iO(')
NA
<yO(a)
<i.o <<xo(')-
<i.o r<io(')-
<O.'5 r<iO(')
- NA MAIN STEAM LINE ISOLATION a.
Reactor Vessel Water Level-Low Low Low, Level 1 b.
Main Steam Line Radiation - High c.
Main Steam Line Pressure - Low d.
Main Steam Line Flow-High e.
Condenser Vacuum - Low f.
Reactor Building Main Steam Line Tunnel Temperature - High g.
Reactor Building Main Steam Line Tunnel 6 Temperature - High Manual Initiation Turbine Building Main Steam Line Tunnel Temperature - High 3.
NA NA NA h.l.
NA iO(a)¹¹ NA NA NA
<yO(a)
NA NA
( )¹¹¹
<yO(a)
NA NA NA NA NA NA NA
<yp(a)
REACTOR WATER CLEANUP SYSTEM ISOLATION 4.
a.
RWCU 6 Flow - High b.
RWCU Area Temperature - High c.
RWCU Area Ventilation Temperature bT - High d.
SLCS Initiation e.
Low Low, Level 2
f.
RWCU Flow " High g.
Manual Initiation REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.
RCIC Steam Line 6 Pressure - High b.
RCIC Steam Supply Pressure - Low c.
RCIC Turbine Exhaust Diaphragm Pressure
- High d.
RCIC Equipment Room Temperature - High e.
RCIC Equipment Room b, Temperature - High 5.
f.
RCIC Pipe Routing Area Temperature - High g.
RCIC Pipe Routing Area h, Temperature - High h.
RCIC Emergency Area Cooler Temperature High i.
Manual Initiation j.
Drywell Pressure - High TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
b.
Drywell Pressure
- High c.
Manual Initiation d.
SGTS Exhaust Radiation - High e.
Main Steam Line Radiation - High 2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level-Low Low, Level 2
b.
Drywell Pressure - High c.
Refuel Floor High Exhaust Duct Radiation - High( )
d.
Railroad Access Shaft Exhaust Duct Radiation - High e.
Refuel Floor Wall Exhaust Duct Radiation -High f.
Manual Initiation SUSQUEHANNA " UNIT 2 3/4 3-21 Amendment No. 25
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TRIP FUNCTION TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME
RESPONSE
TIME Seconds ¹ 6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION a 0 b.
C.
d.
e.f.
g h.
HPCI Steam Flow - High HPCI Steam Supply Pressure - Low HPCI Turbine Exhaust Diaphragm Pressure - High HPCI Equipment Room Temperature - High HPCI Equipment Room 6 Temperature " High HPCI Emergency Area Cooler Temperature - High HPCI Pipe Routing Area Temperature - High HPCI Pipe Routing Area 4 Temperature - High Manual Initiation Drywell Pressure - High
,XO(a)¹¹¹¹ 10( )
NA NA NA NA NA NA NA
<yO(a) 7.
RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION a ~
b.
C.
d.
e.f.
g.
Reactor Vessel Water Level - Low, Level 3
Reactor Vessel (RHR Cut-in Permissive)
Pressure " High RHR Equipment Area 5 Temperature - High RHR Equipment Area Temperature - High RHR Flow - High Manual Initiation Drywell Pressure - High (a)
NA NA NA NA NA<io(')
(a) The isolation system instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.
Isolation system instrumentation response time specified includes the delay for diesel generator starting assumed in the accident analysis.
(b) Radiation detectors are exempt from response time testing.
Response
time shall be measured from detector output or the input qf the first electronic component in the channel.
- Isolation system instrumentation response time for MSIVs only.
No diesel generator delays assumed for MSIV Valves.
- "Isolation system instrumentation response time for associated valves except MSIVs.
¹Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown in Table 3.6.3-1 and 3.6.5.2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.
¹¹kith time delay of 45 seconds.
¹¹¹With time delay of 3 seconds.
AASWith time delay of 3 seconds.
SUS(UEHANNA " UNIT 2 3/4 3-22
CA Cll AD I
M 44 l
CQ TRIP FUN T ON 1.
PRIMARY CONTAINMENT ISOLATION CHANNEL CHECK CHANNEL FUNCTIONAL CHANNEL TEST CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED 2.
a.
Reactor Vessel Mater Level-1)
Low, Level 3
2)
Low Low, Level 2 3)
Low Low Low, Level 1 b.
Drywell Pressure - High c.
Manual Initiation d.
SGTS Exhaust Radiation - High e.
Main Steam Line Radiation-High SECONDARY CONTAINMENT ISOLATION S
S S
NA NA S
M M
M M
R R
R R
R NA R
1 ~ 20 3 1, 2, 3 1, 2, 3 1, 2, 3 1, 2, 3, 4, 5
1, 2, 3 TABLE ~.~.2.1-1 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS b.
C.
e.
Reactor Vessel Water Level-Low Low, Level 2 Drywell Pressure - High Refuel Floor High Exhaust Duct Radiation " High Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Mall Exhaust Duct Radiation - High Manual Initiation S
NA M
M R.
R NA 1, 2, 3 and
- 1 2
3 1, 2, 3 and
- TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 3.
MAIN STEAM LINE ISOLATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE VIREO ae b.
C.
d.
e.f.
g-h.
1 ~
Reactor Vessel Water Level-Low Low Low, Level 1
S Main Steam Line Radiation-High S
Main Steam Line Pressure-Low Main Steam Line Flow -
High'ondenser Vacuum -
Low Reactor Building Main Steam Line Tunnel Temperature - High Reactor Building Main Steam Line Tunnel 6 Temperature-High Manual Initiation Turbine Building Main Steam Line Tunnel Temperature - High NA M
M M
M R
Q NA 1, 2, 3
1.2 3
1 1, 2, 3
2A'*
3*%',
2, 3
1, 2, 3
1, 2, 3
1, 2, 3
4.
REACTOR WATER CLEANUP SYSTEM ISOLATION a e b.
C.
d.
e.
f.
g.
RWCU 6 Flow - High RWCU Area Temperature - High RWCU Area Ventilation h Temperature - High SLCS Initiation Reactor Vessel Water Level-Low Low, Level 2
RWCU Flow - High Manual Initiation NA NA S
S NA M
M Q
NA R
R NA 1
2 3
1, 2, 3
1.2 3
1, 2, 3
1, 2, 3
1, 2, 3
P
TABLE 3. 6. 3-1 PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER a.
Automatic Isolation Val ves MSIV HV-241F022 A,B,C,D HV-241F028 A,B,C,D MSL Drain HV-241F016 HV-241F019 RCIC Steam Su 1
HV-249F007 HV-249F008 HV-249F088 HPCI Steam Su 1
HV-255F002 HV"255F003 HV-255F100 RHR - Shutdown Coolin Suction HV"251F008 HV"251F 009 RWCU Suction(
)
HV"244F001 HV-244F004 RHR - Reactor Vessel Head S ra HV"251F022 HV"251F023 MAXIMUM ISOLATION TIME Seconds 5
5 10 10 20 20 3
50 50'3 52 52 30 30 30 20 ISOLATION( )
SIGNAL S X,C,D,E,P,UA X,C,D,E,P,UA X,C,D,E,P,UA K,KB K,KB K,KB L,LB L,LB L,LB A,M,UB A,M,UB B,J,W I,B,J,W A,M,UB,Z A,M,UB,Z SUSQUEHANNA " UNIT 2 3/4 6-19 Amendment No. 25
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~
4 4
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4 ~
~
4t TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER MAXIMUM ISOLATION TIME Seconds ISOLATION( )
SIGNAL S Automatic Isolation Valves (Continued)
Containment Instrument Gas HV-22603 SV"22605 SV"22651 SV-22661 SV-22671 RBCCW HV-21313 HV"21314 HV"21345 HV-21346 Containment Pur e
HV-25703 HV"25704 HV-25705 HV-25711 HV-25713 HV-25714 HV-25721 HV-25722 HV"25723 HV-25724 HV-25725 RHR " Dr ell S ra HV"251F016 A,B RB Chilled Water HV-28781 Al,A2,Bl,B2 HV-28782 A1,A2,B1,B2 HV"28791 Al,A2,B1,B2 HV-28792 A1,A2,B1, B2 20 N/A N/A N/A N/A 30 30 30 30 15 15 15 15 15 15 15 15 15 15 15 90 40 6
15 4
X,Z X,Z X,Z Y,B Y,B X,Z X$Z X,Z X,Z B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R X,Z X,Z X,Z Y,B Y,B SUSQUEHANNA " UNIT 2 3/4 6-20
'I A
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INSTRUMENTATION BASES 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM This specification is provided to ensure that the turbine overspeed protection system instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.
3/4.3.9 FEEDWATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/main turbine trip system actuation instrumentation is provided to initiate action of the feedwater system/main turbine trip system in the event of failure of feedwater controller under maximum demand.
SUS(UEHANNA - UNIT 2 B 3/4 3"7
WATER l.EVELNOMENCLATURE HEIGHT ABOVE NO.
VESSEL 2ERO READING lin0 VESSEl>>
FLANGE IB) l7) f4) l3) l2) l1)
+54
+39
+30
+)3
<<38
~129 MAIN 588~STEAM LINE NARllOWRANGE~
BOTTOM OF STEAM DRYER SKIRT FEED 498 5 500 WATER 5818 IB) 568.5 17) 557$ I4) 540.5 I3) 527 5 INSTRUMENT ZERO 89.5 2)
CORE SPRAY IBI 54 &0 I7)
HPCI &
RCIC TRIPS
~38 l2) INITIATERCIC, HPCI TRIP RBCIRC PUMPS WO 39 Hl ALARM 30 LO ALARM I3) 13 0
REACTOR SCRAM CONTRIBUTE TO ADS 350 398.5 I1 I 3662 150 129 l1) INITIATERHR, CS.
START DIESEL CONTRIBUTE TO A.CLS.
CLOSE tBIV S AC FU TIVE EL RECIRC OUTLET 161.
NOZZLE 150 216 RECIRC IB'l.O~ INLET NO22LE NOTE: SCALE IN INCHES ABOVE VESSEI ZERO BASES FIGURE B 3/4 3-l REACTOR VESSEL lATER LEVEL SUS)UEHANNA - UNIT 2 B 3/4 3-8 Amendment No. 25