ML17156A267
| ML17156A267 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/15/1985 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17156A268 | List: |
| References | |
| NUDOCS 8505280515 | |
| Download: ML17156A267 (33) | |
Text
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UNITEDSTATES NUCLEAR REGULATORY COMMlSSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER
& LIGHT COMPANY
, ALLEG ENY LE RIG C
OP R TIVE, NC.
DOCKET NO. 50-387 SUS UEHANNA S E
M ELECTRIC STA ION UNIT 1 AMENDMENT 0 FACILITY OPER TING LICENSE Amendment No.
44 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A;. The application for an amendment fil'ed by the Pennsylvania Power
~
8 Light Company, dated January 31, 1985 as supplemented on May 3, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regu'.ations set forth in 10 CFR Chapter I; 8.
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 endangering 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.he 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 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-14 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.
44
, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.'P&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
85052805i5 8505l5 PDR ADOCf( 05000387 P
4
3.
This amendment is effective. upon start-up following the first refueling outage.'OR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
hgY g $ ~
Wal ter R. But er, Chief Licensing Branch No.
2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
F CIL P
R I
G ENSEN. NP-14 DOCKET N. 50-3 7
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.
REMOVE 3/4 3-27 3/4 3-28 3/4 3-29 3/4 3-30 3/4 3-31 3/4 3-32 3/4 3-33 3/4 3-34 3/4 3-35 3/4 3-36 INSERT 3/4 3-27 3/4 3-28 3/4 3-29 3/4 3-29a 3/4 3-30 3/4 3-31 3/4 3-32 3/4 3-33 3/4 3-34 3/4 3-35 3/4 3-36
"PO
~ 'f 1
3/4.3.3
'EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEM.RESPONSE TIME as shown in Table 3.3.3-3.
APPLICABILITY:
As shown in Table -3.3.3-1.
ACT!ON:
a.
b.
With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its.trip setpoint adjusted consistent with the Trip St,tpoint value.
With one or more ECCS actuation instrumentation chaAnels inoperable, take the ACTION required by Table 3.3.3-1.
SURVEILLANCE RE UIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3.1-1.
4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.3.3 The ECCS
RESPONSE
TIME of each ECCS trip function shown in Table 3.3.3-3 shall be demonstrated to be within the limit at least once per 18 months.
Fach test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ECCS trip system.
SUS(UEHANNA - UNIT 1 3/4 3-27
TRIP FUNCTION S
AY SYSTSA TABLE-3. 3. 3" 1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION MINIMUM OPERABLE APPLICABLE CHANNELS PER TRIP OPERATIONAL SYSTEM CONDITIONS ACTION
'a 0 b.
C.
Reactor Vessel Water Level - Low Low Low, Level 1
Drywell Pressure High Reactor Vessel Steam Dome Pressure
- Low (Permissive) a 0 b.
C.
Low Low Low, Level 1
Drywell Pressure
- High Reactor Vessel Steam Dome Pressure - Low (Permissive) 1)
System Initiation 2)
Recirculation Discharge Valve Closure d.
Manual Initiation 3.
HIGH PRESSURE COOLANT INJECTION SYSTEM a.
Reactor Vessel Water Level - Low Low, Level 2
b.
Drywell Pressure
- High c.
Condensate Storage Tank Level - Low d.
Suppression Pool Water Level - High e.
Reactor Vessel Water Level - High, Level 8 f.
Manual Initiation d.
Manual Initiation 2.
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM 2(')
,(a) 2(')
1/subsystem 2(')
2(')
2(')
2(')
1/subsystem 2(')
2(')
,(a)(b) 2(')
2(c) 1/system 1, 2, 3, 4*, 5*
1-, 2, 3
1.2 3
4*
5A 1,-2, 3, 4", 5*
3 4*
53II 1, 2, 3
1, 2, 3
4*
5*
1>>2 3
43l" 5A',
2, 3, 4", 5" 1
2 3
1,'2, 3
1,2,3 1,2,3
- l. 2.
3 1, 2, 3
30 30 31 32 33 30 30 31 32 31 32 33 30 34.
34 31 33 O
CP I
ED TABLE 3.3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION MINIMUM OPERABLE CHANNELS PER TRIP SYSTEM 2(f)
,(f) 1(f)-
2(d)(f)
,(d)(e)(f) 1(f) 2(f) 1 1/valve i.
Manual Initiation I
APPLICABLE OPERATIONAL CONDITIONS 1, 2, 3.
1, 2, 3
1, 2, 3
12 3',
2, 3
1, 2, 3
1 2.3 1
2 3
1, 2, 3
TOTAL NO.
'F CHANNELS CHANNELS TO TRIP MINIMUM APPLICABLE CHANNELS OPERATIONAL OPERABLE CONDITIONS TRIP FUNCTION 4.
AUTOMATIC DEPRESSURIZATION SYSTEM a.
Reactor Vessel Mater Level -
Low Low Low, Level 1
b.
Drywell Pressure
- High c.
ADS Timer d.
Core Spray Pump Discharge Pressure
- High (Permissive) e.
RHR LPCI Mode Pump Discharge Pressure - High (Permissive) f.
Reactor Vessel Mater Level - Low, Level 3 (Permissive) g.
ADS Drywell Pressure Bypass Timer h.
Manual Inhibit ACTION 30 30 31 31 31
-31 31 33 33 ACTION LOSS OF POMER a.
- 4. 16 kv ESS Bus Under-voltage (Loss of Voltage,
<20K) b.
4.16 kv ESS Bus Under-voltage (Degraded Voltage,
<65K) c.
- 4. 16 kv ESS Bus Under-voltage (Degraded Voltage
<84K) w O
1/bus 2/bus 2/bus 1/bus
. 2/bus 2/bus 1/bus 2/bus 2/bus 3
4'A*
5'A*
3 5 3
4**
5AIIC 36 3
4A*
5'Jtk 36
TABLE 3.3.3-1. (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION (a)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
(b)
One trip system.
Provides signal to HPCI pump suction valves only.
(c)
Two out of two logic.
(d)
Either 4d or 4e must be satisfied.
The ACTION is required to be taken only if neither is satisfied.
A channel is not OPERABLE unless its associated pump is OPERABLE per Specification 3.5. 1.
(e)
Within an ADS Trip System there are two logic subsystems, each of which contains an overall pump permissive.
At least one channel associated with each of these overall pump permissives shall be OPERABLE.
(f)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required
,surveillance testing provided that all channels in the other trip system are OPERABLE.
When the system is required to be OPERABLE per Specification 3.5.2.
Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 150 psig.
Required when ESF equipment is required to be OPERABLE.
Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 100 psig.
TABLE 3. 3. 3-1 (Continued) v ACTION 30 "
ACTION 31-ACTION 32 "
ACTION 33-ACTION 34-ACTION 35-ACTION 36-EMERGENCY CORE'-COOLING SYSTEM ACTUATION INSTRUMENTATION, ACTION STATEMENTS With the number of OPERABLE channels less than required by the, Minimum OPERABLE Channels per Trip System requirement:
a.
For one trip system, place the inoperable trip system in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />" or declare the associated ECCS inoperable.
b.
For both trip systems, declare the associated ECCS inoperable.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare the associated ECCS inoperable.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the associated ECCS.-inoperab1e.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within
~ hour" or declare the HPCI system inoperable.
With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8. l. 1 or 3.8.1.2, as appropriate.
With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;~ operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.
f The provisions of Specification 3.0.4 are not applicable.
SUS(UEHANNA - UNIT 1 3/4 3-30 Amendment No.to>
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TRIP FUNCTION 1.
CORE SPRAY SYSTEM 1'ABLE 3.3. 3-2 EMERGENCY CORE COOLING SYSTEH ACTUATION INSTRUMENTATION SETPOINTS TRIP SETPOINT ALLOMABLE VALUE a ~
C.
Low Low Low, Level 1
Drywell Pressure
- High Reactor Vessel Steam Dome Pressure Low Manual Initiation
>-129 inches*
- 1. 72 ps 1 g-
" > 436 psig, decreasing NA
>-136 inches
< 1.88 psig
> 416 psig, decreasing NA 2.
LOW PRESSURE COOLANT INJECTION I'LODE OF RHR SYSTEM a.
Reactor Vessel Mater Level -
Low Low Low, Level 1
b.
Drywell Pressure - High c.
Reactor Vessel Steam Dome Pressure - Low 1)
System Initiation 2)
Recirculation Discharge Valve Closure d.
Manual Initiation 3.
HIGH PRESSURE COOLANT INJECTION SYSTEH
>-129 inches*
< 1.72 psig
>436 psig, decreasing
>236 psig, decreasing
>-136 inches
< 1.88 psig
>416 psig, decreasing
>216 psig, decreasing NA a 0 b.
C.
Reactor Vessel Water Level - Low Low, Level 2
Drywell Pressure High Condensate Storage Tank Level - Low
>-38 inches*
1.72 pslg
> 36.0 inches above tank bottom
> -45 inches
< 1.88 psig
=> 36.0 inches above tank bottom d.
Reactor Vessel Mater Level - High, Level 8 e.
Suppression Pool Mater Level - High f.
Manual Initiation
< 54 inches
< 23 feet 9 inches NA
< 55.5 inches
< 24 feet NA
TABLE 3.3.3-2 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION 4.
AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SETPOINT ALLOWABLE VALUE a.
I b.
M C.
d.
e.
g.
h.
Reactor Water Level - Low Low Low, Level 1 Drywell Pressure High ADS Timer Core Spray Pump Discharge Pressure - High RHR LPCI Mode Pump Discharge Pressure - High Reactor Vessel Water Level-Low, Level 3
ADS Drywell Pressure Bypass Timer Manual Inhibit Manual Initiation
> -129 inches"
< 1..72 psig
< 102 seconds 145 i 10 psig 125 a 4 psig
> 13 inches
< 420 seconds NA NA
>-136 inches
< 1.88 psig
< 114 seconds 145 k 20 psig 125 + 10 psig
> 11.5 inches
< 450 seconds NA NA
~
LOSS OF POWER 4.16 kv ESS Bus Undervoltage (Loss of
- Voltage,
<20K) a.
- 4. 16 kv Basis - 840 + 16.8 volts b.
120 v Basis - 24 + 0.48 volts c.
0.5 + 0. 1 second time delay 840 f 59.6 volts 24'+ 1.7 volts 0.5 + 0.1 second time delay b.
- 4. 16 kv ESS Bus Undervoltage (Degraded
- Voltage,
<65K) a.
4.16 kv Basis - 2695
+ 53.9 volts b.
120 v Bas'is - 77 + 1.54 volts c.
3.0 + 0.3 second time delay 2695 t 191.3 volts 77 2 5.5 volts 3 2 0.3 second time delay O
C.
"See Bases Figure B 3/4 3-1.
- 4. 16 kv ESS Bus Undervoltage (Degraded
- Voltage,
<84K) a ~
b.
C.
- 4. 16 kv Basis 3483 2 69.7 volts 120 v Basis - 99.5 t 1.99 volts 5 minute + 30 second time delay without LOCA 10 + 1.0 second time delay with LOCA 3483 + 247.3, - 69.7 volts 99.5 + 7.1 volts, -1.99 volts 5 minutes
+ 30 second time delay without LOCA 10 + 1.0 second time delay with LOCA
TRIP FUNCTION TABLE 3.3.3-3 t
EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES
RESPONSE
TIME Seconds 1.
CORE SPRAY SYSTEM a.
Reactor Vessel Water Level-Low Low Low, Level 1 b.
Drywell Pressure-High c.
Reactor Vessel Steam Dome Pressure-Low d.
Manual Initation 2.
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.
Reactor Vessel Water Level-Low Low Low, Level 1
b.
Drywel 1 Pressure-High c.
Reactor Vessel Steam Dome Pressure-Low 1)
System Initiation 2)
Recirculation Discharge Valve Closure d.
Manual Initiation 3.
HIGH PRESSURE COOLANT INJECTION SYSTEM
<27
<27
<27 NA
<40
<40
<40
<40 NA
'a ~
b.
C.
d.
e.f.
Reactor Vessel Water Level - Low Low, Level Drywell Pressure
- High Condensate Storage Tank Level-Low Reactor Vessel Water Level-High, Level 8
Suppression Pool Water Level-High Manual Initiation
<30
<30 NA NA NA NA 4.
AUTOMATIC DEPRESSURIZATION SYSTEM a ~
b.
C.
d.
e.f.
g.
h.
1
~
Reactor Vessel Water Level-Low Low Low, Level 1
Drywell Pressure-High ADS Timer Core Spray Pump Discharge Pressure-High RHR LPCI Mode Pump Discharge Pressure-. High Reactor Vessel Water Level-Low, Level 3
ADS Drywell Pressure Bypass Timer Manual Inhibit Manual Initiat',on NA NA NA NA NA NA NA NA NA 5.
LOSS OF POWER a.
- 4. 16 kV ESS Bus Undervoltage (Loss of
,Voltage <20K) b.
- 4. 16 kV ESS Bus Undervoltage (Degraded Voltage <65K) c.
- 4. 16 kV ESS Bus Undervoltage (Degraded Voltage <84K)
NA NA NA SUSQUEHANNA - UNIT 1 3/4 3-33 Amendment No. 44
TABLE 4.3.3.1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 1.
CORE SPRAY SYSTEM CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED a.
b.
C.
d.
Reactor Vessel Water Level-Low Low Low, Level 1 Drywell Pressure High Reactor Vessel Steam Dome Pressure
- Low Manual Initiation S
NA NA HA NA 1, 2, 3, 4*, 5" 1, 2, 3
1, 2, 3, 4", 5*
2.
LOW PRESSURE COOLANT INJECTION MODE OF RllR SYSTEM a.
b.
C.
d.
Reactor Vessel Water Level-Low Low Low, Level 1
Drywell Pressure - High Reactor Vessel Steam Dome Pressure Low 1)
System Initiation 2)
Recirculation Discharge Valve Closure Manual Initiation S
NA NA NA 1, 2, 3, 4", 5" 1
2 3
1, 2, 3, 4", 5" 1, 2, 3, 4", 5" 1, 2, 3, 4", 5" a.
Reactor Vessel Water Level-Low Low, Level 2
S b.
Drywell Pressure - High NA Condensate Storage Tank Level-Low HA Suppression Pool Water Level-High HA Reactor Vessel Water Level High, Level 8 C.
e.
NA NA f.
Manual Initiation 3.
HIGH PRESSURE COOLANT INJECTION SYSTEM NA 1 j 2 $
3 1, 2, 3
1, 2, 3
1 2
3 1, 2,.3 1
2 3
TABLE 4.3.3.1-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSlRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 4.
AUTOMATIC DEPRESSURIZATION SYSTEM CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE VIREO a.
b.
C.
d.
e.
g.
h.
NA NA NA Reactor Vessel.Water Level-Low Low Low, Level 1
Drywell Pressure
- High ADS Timer Core Spray Pump Discharge Pressure
- High NA gHR LPCI Mode Pump Discharge Pressure-High NA Reactor Vessel Water Level-Low, Level 3
S ADS Drywell Pressure Bypass Timer Manual Inhibit Manual Initiation NA NA 1 2.3 1
2.'
1 2
3 1, 2, 3
1.
2 3
1 2
3 1
2 3
5.
LOSS OF POWER b.
C.
4.16 kv ESS Bus Undervoltage (Loss of Voltage)
- 4. 16 kv ESS Bus Undervoltage (Degraded Voltage)
- 4. 16 kv ESS Bus Undervoltage (Degraded Voltage) 3 4AA'A'*
3 4A'A 5'AA' 3
4%A'A'4 When the system is required to be OPERABLE, after being manually realigned, as applicable, per Spe'cification 3.5.2.
Required OPERABLE when ESF equipment is required to be OPERABLF.
¹ Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 150 psig.
¹¹ Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 100 psig.
I INSTRUMENTATION 3/4,3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.4.l The anticipated transient without scram recirculation pump trip (ATWS-RPT) system instrumentation channels shown in Table 3.3.4. 1-1 shall be OPERABLE with their trip setpoints set consistent with values shown in the Trip Setpoint column of Table 3.3.4. 1-2.
APPLICABILITY:
OPERATIONAL CONDITION 1.
ACTION:
a e b.
C.
d.
,With an ATWS recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in tbe Allowable Values column of Table 3.3.4. 1-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
With the number of OPERABLE channels one less than required by the Minimum OPERABLE channels per Trip System requirement for one or both trip systems, place the inoperable channel(s) in the tripped condition within one hour.
With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:
1.
If the inoperable channels consist of one reactor vessel water level channel and one reactor vessel pressure
- channel, place both inoperable channels in the tripped condition within one hour.
2.
If the inoperable channels include two reactor vessel water level channels or two reactor vessel pressure
- channels, declare the trip system inoperable.
With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
e.
With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4;3.4.1. 1 Each ATWS recirculation pump instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.4.1-1.
4.3.4.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at.least once per 18 months.
SUS(UEHANNA - UNIT 1 3/4 3-36
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n 4p**4 UNITED STATES NUCLEAR R EG ULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLE N
L C RIC CO PER IVE IN DOCKET N
. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
11 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Comission or the NRC) having found that:
A.
The application for an amendment filed by the Pennsylvania Power 8 Light Company, dated January 31, 1985 as supplemented on May 3, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),-.and the Comnission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applicat on, the provisions of the Act, and the regulati'ons 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 set forth in 10 CFR Chapter I; D.
The issuance of.his 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 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. 11, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
~
~
I~
~
2'.
This amendment is effective as of thirty (30) days from the date of issuance except for the amendment to the Technical Specifications listed below.
The amendment to the Technical Specificati'ons indicated below is effecti've upon completion of the modifications and associated performance
- testing, but no later than September 1, 1985.
~Pa e, 3/4 3-29 3/4 3-32
'/4 3-33 3/4 3-35, Item Trip Function 4.h Trip Function 4.h Trip Function 4.h Trip Function 4.h FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications
'ate of Issuance:
MAY 15 SM Walter R. Butler, Chief Licensing Branch No.
2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
11 F CILI Y
PER ING LICENS NO.
NPF-2 CK N
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.
REMOVE 3/4 3-27 3/4 3-28 3/4 3-29 3/4 3-29a 3/4 3-30 3/4 3-31 3/4 3-32 3/4 3-33 3/4 3-34 3/4 3-35 3/4 3-36 INSERT 3/4 3-27 3/4 3-28 3/4 3-29 3/4 3-29a 3/4 3-30 3/4 3-31 3/4 3-32 3/4 3-33 3/4 3-34 3/4 3-35 3/4 3-36
INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels show'n in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEM RESPONSE TIME as shown in Table 3. 3. 3-3.
APPLICABILITY:
As shown in Table 3.3.3-1.
.ACTION:
a.
b.
Mith an ECCS actuation instrumentation channel trip setpoint less conservative than the -value shown in the Allowable Values column of
, Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
Mith one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3-1.
SURVEILLANCE RE UIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBPATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3. 1-1.
4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all'hannels shall be performed at least once per 18 months.
4.3.3.3 The ECCS
RESPONSE
TIME of each ECCS trip function shown in Table 3.3.3-3 shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ECCS trip system.
SUSQUEHANNA - UNIT 2 3/4 3"27
.: TABLE 3.3..3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION d.
Manual Initiation 2.
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a 0 C.
Reactor Vessel Water Level - Low Low Low, Level 1
Drywell Pressure - High Reactor Vessel Steam Dome Pressure -
Low (Permissive) 1)
System Initiation 2)
Recirculation Discharge Valve Closure d.
Manual Initiation 3.
HIGH PRESSURE COOLANT INJECTION SYSTEM a.
Reactor Vessel Water Level - Low Low, Level 2
b.
Drywell Pressure
- High c.
Condensate Storage Tank Level - Low d.
Suppression Pool Water Level High e.
Reactor Vessel Water Level - High, Level'8 f.
Manual Initiation TRIP FUNCTION I
ICY IYITE~
a.
Low Low Low, Level 1
b.
Drywell Pressure
- High c.
Reactor Vessel Steam Dome Pressure
- Low (Permissive)
MINIMUM OPERABLE CHANNELS PER TRIP SYSTEM 2(')
2(')
2(')
1/subsystem 2(')
,(a) 2(')
2(a) 1/subsystem 2(')
2(')
2(a)(b)
,(a) 2(c) 1/system APPLICABLE OPERATIONAL CONDITIONS 1, 2, 3, 4", 5" 1
2 3
1, 2, 3
4A 5A 1, 2, 3, 4", 5" I
1, 2, 3, 4", 5" 1
2>>3 1, 2, 3
4*
5A 1, 2, 3, 4A'A 1, 2, 3, 4", 5" 1
2 3
1 2
3 1
2 3
1 2.3 1 2.3 1, 2, 3
ACTION 30 30 31 32 33 30 30 31 32 31 32 33 30 30 34 34 31 33 O
TABLE 3.3.3-1 (Continued)
EMERGENCY CORE COOLINCi SYSTEM ACTUATION INSTRUMENTATION MINIMUM OPERABLE APPLICABLE CHANNELS PER TRIP OPERATIONAL SYSTEM CONDITIONS TRIP FUNCTION 4.
AUTOMATIC DEPRESSURIZATION SYSTEM I
Qo b.
,(f) 2(f) 1(f) 2(d)(f)
. 2(d)(e)(f)
',()
2(f) 1 1/val ve 1
2 3
1, 2, 3
1, 2, 3
1 2
3 1,2,3 1
2 3
1 2
3 C.
e.
1 2
3 1, 2, 3
i.
Manual Initiation Reactor Vessel Mater Level Low Low Low, Level 1
Drywell Pressure
- High ADS Timer Core Spray Pump Discharge Pressure - High (Permissive)
RHR LPCI Mode Pump Discharge Pressure
- High (Permissive)
Reactor'essel Mater Level - Low, Level 3 (Permissive)
ADS Drywell Pressure Bypass Timer Manual Inhibit ACTION 30 30 31 31 31 31 31 33 33 5.
LOSS OF POMER TOTAL NO.
CHANNELS OF CHANNFLS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE OPERATIONAL CONDITIONS ACTION a.
b.
C.
4.16 kv voltage
<2')
4.16 kv vol tage
<65K}
4.16 kv vol tage
<84X)
ESS Bus Under-(Loss of Voltage, 1/bus ESS Bus Under-(Degraded Voltage 2/bus ESS Bus Under-(Degraded Voltage, 2/bus 1/bus 2/bus 2/bus 1/bus 2/bus 2/bus 1, 2, 3, 4"", 5""
35 3
4*III 5TII*
36 2
3 4A'*
5A'III 36 0:
See footnotes on next page.
O
TABLE 3:3-.3-1 (Continued)
EHERGENCY CORE COOLING SYSTEH ACTUATION INSTRUHENTATION (a)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
(b)
One trip system; Provides signal to HPCI pump suction valves only.
(c)
Two out of two logic.
(d)
Either 4d or 4e must be satisfied.
The ACTION is required to be taken only if neither is satisfied.
A channel is not OPERABLE unless its associated pump is OPERABLE per Specification 3.5.1.
(e)
Within an ADS Trip System there are two logic subsystems, each of which contains an overall pump permissive.
At least one channel associated with each of these overall pump permissives shall be OPERABLE.
(f)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance testing provided that.all channels in the other trip system are OPERABLE.
When the system. is required to be OPERABLE per Specification 3.5.2.
¹ Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 150 psig.
Required when ESF equipment is required to be OPERABLE.
¹¹ Not required to be OPERABLE-when reactor steam dome pressure is less than or equal to 100 psig.
ACTION 30-ACTION 31-ACTION 32-ACTION 33-ACTION 34-ACTION 35-ACTION 36 "
3g, TABLE 3. 3. 3-1 (Continued)
I.
~
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION'TATEMENTS With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:
a.
For one'rip system, place the inoperable trip system 'in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />."
or declare the associated ECCS inoperable.
b.
For both trip systems, Meclarz the associated ECCS inoperable.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, declare the associated ECCS inoperable.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
With the number of OPERABLE channels less than required by the Minimum OPERABI.E Channels per Trip System requirement, restore
(
the inoperable channel to.OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the associated ECCS inoperable.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />" or declare the HPCI system inoperable.
I With the rumber of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator inoperable and take the ACTION required by Specification
- 3. 8. 1. 1 or 3.8.1.2, as appropriate.
With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;~ operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.
"The provisions of Specification 3.0.4 are not applicable.
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TRIP FUNCTION 1.
CORE SPRAY SYSTEtl TABLE 3.3.3-2 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE b.
Reactor Vessel Water Level - Low Low Low, Level 1
Drywell Pressure
- High Reactor Vessel Steam Dome Pressure Low d.
Manual Initiation 2.
LOM PRESSURE COOLANT INJECTION MODE OF RHR SYSTBi
>-129 inches"
< 1.72 psig
>'36 psig, decreasing NA
>-136 inches
-< 1.88 psig
> 416 psig, decreasing NA a.
b.
C.
Reactor Vessel Mater Level -
Low Low Low, Level 1
Drywell Pressure
- High Reactor Vessel Steam Dome Pressure
- Low
'>-129 inches*
< 1.72 psig
>-136 inches
< 1.88 psig 1)
System Initiation 2)
Recirculation Discharge Valve Closure d.
Manual Initiation 3.
HIGH PRESSURE COOLANT INJECTION SYSTEM
> 436 psig, decreasing
> 236 psig, decreasing NA
> 416 psig, decreasing
> 216 psig, decreasing NA C.
Low Low, Level 2
Drywell Pressure
- High Condensate Storage Tank Level -
Low
> -38 inches"
< f.72 psig
> 36.0 inches above tank bottom 45 inches
< 1.88 psig
> 36.0 inches above-tank'ottom d.
Reactor Vessel Water Level - High, Level 8
e.
Suppression Pool Water Level - High f.
Manual Initiation
< 54 inches
< 23 feet 9 inches NA
< 55.5 inches
< 24 feet NA
TABLE 3.3.3-.2 (Continued) 1j a'MERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION 4.
AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SETPOINT ALLOWABLE VALUE a.
b.
C.
e.
g.
h.
Reactor Water Level - Low Low Low, Level 1
Drywell Pressure
- High ADS Timer Core Spray Pump Discharge Pressure High RHR LPCI Mode Pump Discharge Pressure
- High Reactor Vessel Water Level-Low, Level 3
ADS Drywell Pressure Bypass Timer Manual Inhibit Manual Initiation
> -129 inches~
< 1.72 psig
< 102 seconds 145 2 10 psig 125 + 4 psig
> 13 inches
< 420 seconds NA
>-136 inches
< 1.88 psig
< 114 seconds 145 + 20 psig 125 + 10 psig
> 11.5 inches
< 450 seconds NA NA 5.
LOSS OF POWER a ~
b.
4.16 kv ESS Bus Under voltage (Loss of
- Voltage,
<20X)
- 4. 16 kv ESS Bus Undervoltage (Degraded
- Voltage,
<65K) a.
- 4. 16 kv Basis - 840 + 16.8 volts b.
120 v Basis - 24 + 0.48 volts c.
0.5 + O.l second time delay a.
4.16 kv Basis - 2695 + 53.9 volts b.
120 v Basis 77 + 1.54 volts c.
- 3. 0 + 0. 3 second time delay 840 + 59.6 volts 24 + 1.7 volts 0.5 + 0. 1'second time del ay.
2695 t 191.3 volts 77 + 5.5 volts 3 + 0.3 second. time delay "See Bases 4.16 kv ESS Bus Undervoltage (Degraded
- Voltage,
<84K)
Figure B 3/4 3-1.
a.
b.
C.
- 4. 16 kv Basis - 3483 + 69.7 volts 120 v Basis - 99.5 + 1.99 volts 5 minute + 30 second time delay without LOCA 10 + 1.0 second time delay with LOCA 3483 + 247.3, - 69.7 volts 99.'5
+ 7.1 volts, -1.99 volts 5 minutes
+ 30 second time delay without LOCA 10 + 1.0 second time delay with LOCA
1 TRIP FUNCTION TABLE 3. 3. 3-3 EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES
RESPONSE
TIME (Seconds 1.
CORE SPRAY SYSTEM.
a ~'.
C.
d.
Reactor Vessel Water Level-Low Low Low, Level 1
Drywell Pressure-High Reactor Vessel Steam Dome Pressure-Low Manual Initation
<27
<27
<27 NA 2.
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a ~
b.
C.
d.
Reactor Vessel Water Level-Low Low Low, Level 1
Drywell Pressure-High Reactor Vessel Steam Dome Pressure-Low 1)
System Initiation 2)
Recirculation Discharge Valve Closure Manual Initiation
<40
<40
<40
<40 NA 3.
HIGH PRESSURE COOLANT INJECTION SYSTEM ao b.
C.
d.
e.
T.
Reactor Vessel Water Level - Low Low, Level Drywell Pressure
- High Condensate Storage Tank Level-Low Reactor Vessel Water Level-High, Level 8
Suppression Pool Water Level-High Manual Initiation
<30
<30 NA NA NA NA 4.
AUTOMATIC DEPRESSURIZATION SYSTEM a 0 b.
C.
d.
e.f.
g.
h.l.
Reactor Vessel Water Level-Low Low Low, Level 1
Drywell Pressure-High ADS Timer Core Spray Pump Discharge Pressure-High RHR LPCI Mode Pump Discharge Pressure-High Reactor Vessel Water Level-Low, Level 3
ADS Drywell Pressure Bypass Timer Manual Inhibit Manual Initiation F
NA NA NA NA NA NA NA NA NA 5 ~
LOSS OF POWER a.
- 4. 16 kV ESS Bus Undervoltage (Loss of Voltage <20K) b.
- 4. 16 kV ESS Bus Undervoltage (Degraded Voltage <65K) c.
4.16 kV ESS Bus Undervoltage (Degraded Voltage <84M)
NA NA SUS(UEHANNA - UNIT 2 3/4 3-33 Amendment No. ll
TABLE 4. 3. 3. 1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 1.
CORE SPRAY SYSTEM CHANNEL CHECK CHANNEL OPERATIONAL FUNCTIONAL CHANNEL CONDITIONS. FOR WHICH TEST CALIBRATION SURVEILLANCE RE UIRED a.
b.
C.
Reactor Vessel Water Level-
- Low Low Low, Level 1
Drywell Pressure
- High Reactor Vessel Steam Dome Pressure Low Manual Initiation S
NA NA NA R
1, 2, 3, 4", 5*
1 2
3 1, 2, 3, 4", 5" 2.
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.
b.
C.
Reactor Vessel Water Level-Low Low Low, Level 1
Drywell Pressure
- High Reactor Vessel Steam Dome Pressure Low S
NA R.
Q 1, 2, 3, 4", 5" 1, 2, 3
1)
System Initiation NA 2)
Recirculation Discharge Valve Closure NA d.-
Manual Initiation NA 3.
HIGH PRESSURE COOLANT INJECTION SYSTEM 1, 2, 3, 4", 5" 1, 2, 3, 4", 5" 1, 2, 3, 4", 5" a.
C.
d.
e.
Reactor Vessel Water Level-Low Low, Level 2
Drywell'Pressure
- High Condensate Storage Tank Level-Low
'uppression Pool Water Level-High Reactor Vessel Water Level-High, Level 8
Manual Initiation S
NA NA NA NA Q
NA 1,'2,3 1
2 3
1 2
3 1
2 3
1 2
3 12 3.
TABLE 4. 3. 3. l-l (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REgUIREHENTS TRIP FUNCTION 4.
AUTOMATIC DEPRESSURIZATION SYSTEM CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED a.
b.
C.
d.
e.
g.
h.
S NA NA NA NA NA Reactor Vessel Water Level-Low Low Lowl Level 1
Drywell Pressure
- High ADS Timer Core Spray Pump Discharge Pressure
- High NA RHR LPCI Mode Pump Discharge Pressure-High NA Reactor Vessel Water Level-Low, Level 3
S ADS Drywell Pressure Bypass Timer Manual Inhibit Manual Initiation M
M R
Q NA NA 1 l 2 l 3
1 2
3 1, 2, 3
1 2
3 1
2 3
1,2,3 1, 2, 3
1, 2, 3
1 2
3 5.
LOSS OF POWER a.
b.
C.
- 4. 16 kv ESS Bus Undervoltage (Loss of Voltage)
- 4. 16 kv ESS Bus Undervoltage (Degraded Voltage)
- 4. 16 kv ESS Bus Undervoltage (Degraded Voltage) 3 4**
5%A 3
4*lA',
5IR"8 3
4%A 5*IRi When the system is required to be OPERABLE, after being tI>anually realigned, as applicable, per Specification 3.5.2.
Required OPERABLE when ESF equipment is required to be OPERABLE.
¹ Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 150 psig.
- ¹¹ Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 100 psig.
O
INSTRUMENTATION 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION APPLICABILITY:
OPERATIONAL CONDITION l.
ACTION:
a.
With an ATWS recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.4. 1-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With the number of OPERABLE channels one less than required by the Minimum'PERABL'E channels per Trip System requirement for one or both trip systems, place the inoperable channel(s) in the tripped condition within one hour.
c.
With the number of OPERABLE ch'annels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:
l.
If the inoperable channels consist of one reactor vessel water level channel and one reactor vessel pressure
- channel, place both inoperable channels in the tripped condition within one hour.
2.
If the inoperable channels include two reactor vessel
'water level channels or two reactor vessel pressure
- channels, declare the trip system inoperable.
d.
With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
e.
With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
EILLANCE RE UIREMENTS SURV 3.3.4.
1 The anticipated transient without scram recirculation pump trip (ATWS-RPT) system instrumentation channels shown in Table 3. 3.4. 1-1 shall be OPERABLE with their trip setpoints set consistent with values shown in the Trip Setpoint column of Table 3.3.4. 1-2.
4.3.4. l. 1 Each ATWS i ecirculation pump instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown i n Tab 1 e 4. 3. 4. 1-1.
'.3.4.
1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
SUSQUEHANNA - UNIT 2 3/4 3-36