ML17156B535
| ML17156B535 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/06/1989 |
| From: | Boger B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17156B536 | List: |
| References | |
| NUDOCS 8912180162 | |
| Download: ML17156B535 (30) | |
Text
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++**+
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No.
NPF-14 1.
The Nuclear ReguIatory,Commission (the Commission or the NRC) having found that.:
A.
The application for the amendment filed by the Pennsylvania Power Light Company, dated October 19, 1989 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 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'i'll 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 Speci<ica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the 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.
94 and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.
PP&L shall operate the facility in accor dance with the Technical Specifications and the Environmental Protection Plan.
80i62 89i206 OCK 05000337 PDR ADO
.3.
This license amendment was effective on October 20, 1989.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 6,
1989 Bruce A. Boger, Assistant Director for Region.'eactors Division of Reactor Projects I/I'.
ATTACHMENT TO LICENSE AMENDMENT NO.
94 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 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 overleaf pages are provided to maintain document completeness.*
REMOVE 3/4 3-11 3/4 3-12 3/4 3-13 3/4 3-14 3/4 3-17 3/4 3-18 3/4 3-19 3/4 3-20 3/4 3-23 3/4 3-24 3/4 3-25 3/4 3-26 INSERT 3/4 3-11*
3/4 3-12 3/4 3-13 3/4 3-14 3/4 3-17*
3/4 3-18 3/4 3-19 3/4 3-20 3/4 3-23*
3/4 3-24 3/4 3-25 3/4 3-26
AD m
TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
MINIMUM APPLICABLE ISOLATION( )
OPERABLE CHANNELS OPERATIONAL 1, 2, 3
1, 2, 3
1 2
3 ACTION 20 20 20 b.
Drywell Pressure
- High c.
Manual Initiation Y,Z,X NA 1
2 3
1, 2, 3
20 24 d.
SGTS Exhaust Radiation-High R
e.
Main Steam Line Radiation-Hi h
C g
2.
SECONDARY CONTAINMENT ISOLATION 1, 2, 3
20 3
4IIIIkIII 5IIIIN*
20 B
~
TD ITI C
~ O CO CQ 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 NA 1,2,3and" 1, 2, 3
1, 2, 3 and "
25 25 25 25 25 24
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION TRIP FUNCTION 3.
MAIN STEAM LINE ISOLATION MINIMUM APPLICABLE ISOLATION OPERABLE CHANNELS OPERATIONAL SIGNAL(s)
PER TRIP SYSTEM (b)
CONDITION ACTION C.
Reactor Vessel Mater Level-Low, Low, Low, Level 1
Main Steam Line Radiation-High Main Steam Line Pressure Low Main Steam Line Flow - High D
Condenser Vacuum - Low UA NA E
f.
Reactor Building Main Steam Line E
Tunnel Temperature High g.
Reactor Building Main Steam Line E
Tunnel d Temperature High h.
Manual Initiation i.
. Turbine Building Main Steam Line Tunnel Temperature-High REACTOR MATER CLEANUP SYSTEM ISOLATION 2
2/line 2
2 2-1, 2, 3
1, 2, 3
1 2
3 1, 2, 3
1, 2, 3
1 2
3 1
2 3
1 2
3 21 22 20 21 21 21" 24 21 gO Pl ec+W
>oe
<a oc+
e ~
wo
~ we Z y Q
0 y
'c) e g)
~ ~
a.
b.
C.
RWCU b, Flow High RWCU Area Temperature
- High RMCU Area Ventilation 6 Temp.
High SLCS Initiation Reactor Vessel Mater Level Low Low, Level 2
RMCU Flow - High
'anual Initiation J
NA 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
- These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
Vl AD m
D'RIP FUNCTION 5.
REACTOR CORE ISOLATION TABLE 3. 3. 2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION MINIMUM ISOLATION( )
OPERABLE CHANNELS SIGNAL(s)
PER TRIP SYSTEM (b)
COOLING SYSTEM ISOLATION APPLICABLE OPERATIONAL CONDITION ACTION v om I
O Q ro 8 c+
S vo 0
v O
gp W c+
MO
(~ os a.
RCIC Steam Line 6 Pressure
- High K
b.
RCIC Steam Supply Pressure Low KB c.
RCIC Turbine Exhaust Diaphragm K
Pressure
- High d.
RCIC Equipment Room Temperature
- High
- e. 'CIC Equipment Room d,
Temperature High f.
RCIC Emergency Area Cooler Temperature High g.
RCIC Pipe Routing Area 6 Temperature High h.
RCIC Pipe Routine Area Temperatur e High Manual Initiati on j.
Drywell Pressure
- High 1, 2, 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 1, 2, 3
23 23 23 23 23K'3 23*
23 23
~These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION DO 2 0 A) g+
~ O ag et ~
CI
~~v O
C) tQ CO Pl lD O
- MINIMUM, ISOLATION OPERABLE CHANNELS SIGNAL(s)
PER TRIP SYSTEM (b)
TRIP FUNCTION 6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION a.
HPCI Steam Line b, Pressure-L High b.
HPCI Steam Supply Pressure-Low LB c.
HPCI Turbine Exhaust Diaphragm L
Pressure
- High d.
HPCI Equipment Room Temperature
- High e.
HPCI Equipment Room 6 Temperature
- High f.
HPCI Emergency Area Cooler Temperature
- High g.
HPCI Pipe Routing Area Temperature High h.
HPCI Pipe Routine Area 6 Temperature High i.
Manual Initiation j.
Drywell Pressure
- High 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
.1 2
3 1
2 3
"This trip function need not be OPERABLE from October 19, 1989 to January 19, 1990.
ACTION 23 23 23 23 23 23 23 23~
24 23
tn A3 m
TABLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION TRIP SETPOINT ALLOWABLE VALUE 2.
a.
b.
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
Drywell Pressure - High c.
Manual Initiation d.
SGTS Exhaust Radiation - High e.
Main Steam Line Radiation High SECONDARY CONTAINMENT ISOLATION
> 13.0 inches"
> -38.0 inches*
> -129 inches"
< 1.72 psig NA
<23.0 mR/hr
< 7.0 x full power background
> 11.5 inches
> -45.0 inches
> -136 inches
< 1.88 psig NA
<31.0 mR/Hr
<8.4 x full power background 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 o.B Cl C)
C+
O EXt a.
C.
Reactor Vessel Water Level - Low Low Low, Level 1
Main Steam Line Radiation - High Main Steam Line Pressure Low Main Steam Line Flow - High
> -129 inches"
< 7.0 X full power background
> 861 psig
< 107 psid
> -136 inches
< 8.4 X full power background
> 841 psig
< 110 psid
V)
AO m
D D
TRIP FUNCTION TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE MAIN STEAM LINE ISOLATION (Continued) e.
Condenser Vacuum -
Low Reactor Building Main Steam Line Tunnel Temperature - High Reactor Building Main Steam Line Tunnel b, Temperature - High
> 9.0 inches Hg vacuum
<177 F
< 99'F
> 8.8 inches Hg vacuum
< 184 F
< 108'F*
+O0 fD~o B
CL ~
lD
~O 0
~ 0D LO I
O g+
Ao C
lD O
Qlr+
lD
~ ~
C.
RWCU 6 Flow - High RWCU Area Temperature
- High RWCU/Area Ventilation 6 Temperature
- High SLCS Initiation Reactor Vessel Mater Level-Low Low, Level 2
RWCU Flow High Manual Initiation
< 60 gpm
< 147'F or 118.3'F¹ 690F or 35 30F¹ NA
> -38 inches*
< 426 gpm NA 5.
REACTOR. CORE ISOLATION COOLING SYSTEM ISOLATION h.
Manual Initiation NA i.
Turbine Building Main Steam Line
<177'F Tunnel Temperature-High 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION NA
<184 F
< 80 gpm 1540F or 125 3'I
< 78 F or 44.3 F¹A NA
> -45 inches
< 436 gpm NA a.
b.
RCIC Steam Line b, Pressure
- High RCIC Steam Supply Pressure Low RCIC Turbine Exhaust Diaphragm Pressure High
< 177" H20 60 psig
< 10.0 psig
< 189" H,O
> 53 psig
< 20.0 psig
- These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
C/l AD m
TRIP FUNCTION TABLE 3. 3. 2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE REACTOR e.
h.
<89F CORE ISOLATION COOLING SYSTEM ISOLATION Continued)
RCIC Equipment Room Temperature - High 167'F*'CIC Equipment Room 6 Temperature
- High
< 89 F
RCIC Pipe Routing Area Temperature High
<167 F
RCIC Pipe Routing Area b, Temperature High RCIC Emergency Area Cooler Temperature
- High
< 147 F
Manual Initiation NA Drywell Pressure
- High
<1.72 psig
( j74<
FA'A'98 F*
174PF¹¹ 98PF¹¹
<154 F
NA
<1.88 psig 6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION
~om
+o m O
tD B~a o
~ tD a@a NS Z>>
Q 0 M c+
~M lD
~Q)
~ ~
LO a.
b.
C.
HPCI Steam Line 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
< 350 inches HzO
> 104 psig
< 10 psig
< 167 F
< 89 F
< 147 F
167oF¹¹
< 367 inches H>0 90 psig
< 20 psig
< 174 F
<98F
<154 F
< 174'F
~These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
Cjl AO foal TRIP FUNCTION TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE h.
HPCI Pipe Routing Area 6 Temperature
- High i.
Manual Initiation j.
Drywell Pressure
- High 8 9P F¹¹ NA
<1.72 psig 98P F¹¹*4 NA
<1.88 psig I
CD 1 CDm
+ o CP caW
~O CP O-O'
>lDH S g Aa C MQ CD 0 W c+
CO 0 CO~)
s ~
CO 7.
RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION a.
b.
C.
d.
Reactor Vessel Water Level-Low, Level 3
Reactor Vessel (RHR Cut-in Permissive)
Pressure
- High RHR Equipment Area 6 Temperature High RHR Equipment Area Temperature-High RHR Flow - High Manual Initiation g.
Drywell Pressure
- High
> l3.0 inches*
< 98 psig
< 89 F
< 167 F
< 25,000 gpm NA
<1.72 prig
> 11.5 inches
< 108 psig
< 90.5'F
< 170.5 F
< 26,000 gpm NA
<1.88 psig See Bases Figure B 3/4 3-1.
¹Lower setpoints for TSH-G33-1N600 E,
F and TOSH-G33-1N602 E,
F.
¹¹15 minute time delay.
~"This trip function need not be OPERABLE from October 19, 1989 to January 19, 1990.
TABLE 4. 3. 2. 1-1 m
TRIP FUNCTION l.
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level-CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION CHANNEL CHECK ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED 1)
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
b.
Drywell Pressure
- High NA 1, 2, 3
1 2
3 1, 2, 3
1, 2, 3
c.
Manual Initiation NA d.
SGTS Exhaust Radiation High S
e.
Main Steam Line Radiation - High S
NA R
R 1,2,3 3
4*A%
5'AA'A 1
2 3
2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Vesse Water Level-Low Low, Level 2
b.
Drywell Pressure
- High Refuel Floor High Exhaust Duct Radiation - High NA 1,2,3and" 1, 2, 3
B PD
~
~
(+
d.
e.
Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Wall Exhaust Duct Radiation - High 0
tg) 0 f.
Manual Initiation 1,2,3and"
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 3.
MAIN STEAM LINE ISOLATION Reactor Vessel Water Level
- Low, Low Low, Level 1
Main Steam Line Radiation - High Main Steam Line Pressure Low CHANNEL CHECK CHANNEL OPERATIONAL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TEST CALIBRATION SURVEILLANCE RE VIREO l
2 3
1,2,3 S
NA d.
Main Steam Line Flow High e.
Condenser Vacuum - Low f.
Reactor Building Main Steam Line Tunnel Temperature
- High NA g.
Reactor Building Main Steam Line Tunnel 6 Temperature High NA h.
Manual Initiation NA i.
Turbine Building Main Steam Line NA Tunnel Temperature
- High REACTOR WATER CLEANUP SYSTEM ISOLATION 1,2,3 2**
3A'*
1,2,3 1, 2, 3" 1, 2, 3
1 2
3 porn c+m
> O tb
~cr o
> lD r+
8 g ao
~me CI Wv 0
gu W c+
LQ Q lO Q) ~ ~
b.
C.
e.
g.
RWCU 6 Flow - High RWCU Area Temperature
- High RWCU Area Ventilation b,
Temperature - High SLCS Initiation Reactor Vessel Water Level -
Low Low, Level 2
RWCU Flow High Manual Initiation S
NA NA NA S
S NA NA R
R NA 1
2 3
1,2,3 i, z, s*
1;2,3 1,2,3 1
2 3
1,2,3
~These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR MHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE RE UIRED 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
>om
>OW (D g+~
D O fD M Cf O Q I c+
5 ~>>
C et MI Cl
~v Q
DI W tD IQQ
~ ~
~ LD a."
b.
HPCI Steam Line 6 Pressure
- High HPCI Steam Supply Pressure Low HPCI Turbine Exhaust Diaphragm Pressure
- High NA NA a.
RCIC Steam Line 6 Pressure High NA b.
RCIC Steam Supply Pressure-Low NA c.
RCIC Turbine Exhaust Diaphragm Pressure
- High NA d.
RCIC Equipment Room Temperature - High NA e.
RCIC Equipment Room 6 Temperature
- High NA f.
RCIC Pipe Routing Area Temperature - High NA g.
RCIC Pipe Routing Area 6 Temperature
- High NA h.
RCIC Emergency Area Cooler Temperature - High NA i.
Manual Initiation NA j.
Drywell Pressure
- High NA HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION NA R
1 2
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
1 2
3 1
2 3
j 2
3 1, 2, 3
~These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
WtD Pl B A CD t+W DOlb O-O' c+
(Q +
Mo C
~ M tD C) 0
~ + g+
M lD
~ (Q
~ ~
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE RE UIRED HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION (Continued) d.
HPC'I Equipment Room Temperature - High NA M
e 1,
2 3
e.
HPCI Equipment Room 6 Temperature High NA M
f.
HPCI Emergency Area Cooler Temperature
- High NA M
1 2
3 g.
HPCI Pipe Routing Area h.
3)p)ep))r(out(ghAvea NA M
h Temper ature - High NA M
i.
Manual Initiat ion NA R
NA j.
Drywell Pressure
- High NA M
R 7.
RHR SYSTEM SHUTDOMN COOLING/HEAD SPRAY MODE ISOLATION 1
2 3
1 2
3
]
2 3**%'I' 2
3 1, 2, 3
b.
e.,
f.
g.
Reactor Vessel Mater Level-Low, Level 3
S Reactor Vessel (RHR Cut-in Permissive)
Pressure
- High NA RHR Equipment Area 6 Temperature - High NA RHR Equipment Area Temperature-High NA RHR Flow - High S
Manual Initiation NA Drywell Pressure High NA R
NA R
l, 2, 3
1,2,3 1
2 3
1 2
3 1, 2, 3
1, 2, 3
1 2
3 Mhen hand sng irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
"* @hen reactor steam dome pressure
> 1043 psig and/or any turbine stop valve is open.
- "When VENTING or PURGING the dryweT1 per Specification
- 3. 11.2.8.
"~~~ This trip function need not be OPERABLE from October 19, 1989 to January 19, 1990.
j
gAg REGS po Cy nO O
~ Yg
~O
+>>*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 PENNSYLVANIA POWER Pi LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
61 License No.
NPF-22 I.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 8
Light Company, dated October 19, 1989 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 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 de~ense 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.
61 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
- PPEL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This 1icense amendment was effective on October 20, 1989.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technica1 Specifications Date of Issuance:
December 6,
1989 Sruce A. Boger, Assistant Director
. or Region I Reactors Division of Reactor Projects I/II
ATTACHMENT TO LICENSE AMENDMENT NO. 61 FACILITY OPERATING LICENSE 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 overleaf pages are provided to maintain document completeness.*
REMOVE 3/4 3-11 3/4 3-12 3/4 3-13 3/4 3-14 3/4 3-17 3/4 3-18 3/4 3-19 3/4 3-20 3/4 3-23 3/4 3-24 3/4 3-25 3/4 3-26 INSERT 3/4 3-11*
3/4 3-12 3/4 3-13 3/4 3-14 3/4 3-17*
3/4 3-18 3/4 3-19 3/4 3-20*
3/4 3-23*
3/4 3-24 3/4 3-25 3/4 3-26
TRIP FUNCTION 1.
PRIHARY CONTAINMENT ISOLATION.
a.
Reactor Vessel Water Level TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION HINIHUM ISOLATION OPERABLE CHANNELS SIGNAL(S)(a)
PER TRIP SYSTEM (b)
APPLICABLE OPERATIONAL CONOITION ACTION C.
1)
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
Orywell. Pressure
- High Hanual Initiation Y,Z NA 1,2,3 1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
20 20 20 20 24 2.
d.
SGTS Exhaust Radiation-High e.
Hain Steam Line Radiation-High SECONOARY CONTAINMENT ISOLATION 1, 2, 3
20 3
4A'**
5'ATTAIN 20 a.
Reactor Vessel Water Level-Low Low, Level 2
b.
Orywel 1 Pressure High c.
Refuel Floor High Exhaust Ouct Radiation - High 1, 2, 3 and "
1, 2, 3
25 25 25 2
CD CL ID CC)
CO O
d.
e.
Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Wall Exhaust Ouct Radiation - High Hanual Initiation 1, 2, 3 and "
25 25 24
TRIP FUNCTION TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION MINIMUM APPLICABLE ISOLATION OPERABLE CHANNELS OPERATIONAL SIGNAL(S)(a)
PER TRIP SYSTEM (b)
CONDITION ACTION 3.
MAIN STEAM LINE ISOLATION a.
Reactor Vessel Mater 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 P
0 UA E
4 f.
Reactor Building Main Steam Line Tunnel Temperature
- High g.
Reactor Building Main Steam E
Line Tunnel 6 Temperature High h.
Manual Initiation NA i.
Turbine Building Main Steam Line E
Tunnel Temperature High REACTOR MATER CLEANUP SYSTEM ISOLATION 2
2/line 2
1 2
3 1, 2, 3
'1 2
3 1'2 3
1 2
3 1
2 3
1 2
3 1, 2, 3
21 21 22 20 21 21 21*
24 21
~on ION c+ W
~o I D O I Gl c+
5 Me
~Me(
C) D 0
~MA
~ Q)
~ ~
a.
C.
d.
e.
g.
RMCU 6 F 1 ow - High RMCU Area Temperature
- High RMCU Area Ventilation 6 Temperature High SLCS Initiation Reactor Vessel Mater Level -
Low Low, Level 2
RMCU Flow - High Manual Initiation NA 3 '
1, 2, 3
1 2
3 1
2 3
1 2
3 1
2 3
1 2
3 1, 2, 3
23 23 22*
23 23 23 24 "These trip functions need not be OPERABLE from October 19, 1989 to January 1, 1990.
(A AD m
TABLE 3. 3. 2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION MINIMUM ISOLATION OPERABLE CHANNELS SIGNAL(S)(a)
PER TRIP SYSTEM (b) a.
RCIC Steam Line b, Pressure
-High K
b.
RCIC Steam Supply Pressure Low c.
RCIC Turbine Exhaust Diaphragm Pressure
- High d.
RCIC Equipment Room Temperature
- High e.
RCIC Equipment Room d Temperature High f.
RCIC Pipe Routing Area Temperature
- High g.
RCIC Pipe Routing Area 6 Temperature - High KB TRIP FUNCTION 5.
REACTOR CORE ISOLATION COOLING 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
ACTION 23 23 23 23 23 XO got+
~ O CL~
R fD G) ~reID Zv 0
Ch CO h.
RCIC Emergency Area Cooler Temperature
- High 1,
2 3
j.
Drywell Pressure
- High i.
Manual Initiat ion NA
~e Z
2 1, 2, 3
"These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
23 24 23
O I
N CU Cd CV CV CV N
5l OJ CU UJ <<L M
~DO Co O M
<<LMI LJ IM M <<L O DCP K CP UJ O CP- 0
<<L O Cgl A
CU hl
~\\
Cl I
QP UJ C
'g I
C LP) 0 Z
O I
<<L I
Cl I
<<C O
<Jl Lg) JD M UJ W <<C I-
~ W Lgl ZV 0V)
M UJ M U CL Q CCI M
<<L Q CP I 0
CL O UJ 6
O ch MM
<<C <<L O U Lgl M M V)
U Cl Cl Cj)
Cl I
LLI I
Cl Cl Ql
~ g CU CU 3
E 0
Ul gd I
S-QP S-QP VP Vl Cl QP S-CL Vl dl 0.
XJ 0.
LU 0)
~ g C/7 QP ~
E QP S-QPI V)
M M Vl Ql 0-CL S
X XCL E0 J O Ol
~ p I
dP Ql g!.
S
~ g 0
IQ UJ S-QP M 0, E
0 0)
~ g I
dl Ql
- 0. S-T g 0'S UJ S-QP M Q, E
<<C'p IJ I
C Ql QP Ol S-S-
QP M E
QP UJ S
QP E
CL QP Ml Id Ql S-
<<C
- 0) U)
C
~ g
~ g I
0 Ql S-QPO.M
~ g QS S
Ol Ch C gr
~ g I
0 QP S-QP CLM
'g Id CP S-Ql M Q.
CL QP Ml C0
~ g Id I
~ gC g
0 S-0 O
E0 4
IX) gd:
LIJ OCl dP J5 0
0
~ g Cl.
~ g S-Vl
~ g I
SUSQUEHANNA - UNIT 2 3/4 3-14 Effective Date:
October 20, 1989 Amendment No.
61
TABLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS AD m
TRIP FUNCTION 1.
PRIMARY CONTAINHENT ISOLATION TRIP SETPOINT ALLOMABLE VALUE a.
b.
C.
d.
e.
Reactor Vessel Mater Level 1)
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
< 7.0 X full power background
> 11.5 inches
> -45.0 inches
> -136 inches
< 1.88 psig NA
< 31.0 mR/hr
< 8.4 X full power background 2.
SECONDARY CONTAINMENT ISOLATION 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 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.
HAIN STEAN LINE ISOLATION Po C
a0 o
CO O
CA CJl C>
a.
b.
C.
d.
Low Low Low, Level 1
Hain Steam Line Radiation - High Hain Steam Line Pressure Low Hain Steam Line Flow - High
> -129 inches"
< 7.0 X full power background
> 861 psig
< 107 psid
> -136 inches
< 8.4 X full power background
> 841 psig
< 110 psid
TRIP FUNCTION TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE M
MAIN STEAM LINE ISOLATION (Continued) e.
Condenser Vacuum -
Low f.
Reactor Building Main Steam Line Tunnel Temperature High g'.
'eactor Building Main Steam Line Tunnel 6 Temperature - High h.
Manual Initiation i.
Turbine Building Main Steam Line Tunnel Temperature
- High 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION
> 9.0 inches Hg vacuum
<177F
< 99'F NA
<177 F
> 8.8 inches Hg vacuum
< 184-'F
< 108 F" NA
< 184F C.
d.
RWCU 6 Flow - High RWCU Area Temperature
- High RWCU/Area Ventilation 6 Temperature
- High SLCS Initiation
< 60 gpm
< 147'F or 118.3'F¹
< 69'F or 35.3'F¹ NA
< 80 gpm
< 154'F or 125.3'F¹
< 78 F or 44.3 F¹*
NA O Pl 0)
O (D
0 0 c+
Q 5 Ao C
NQ C) v Q
0
~
A r+
40 lD Q)
~ ~
lg e.
g.
Reactor Vessel Water Level-Low Low, Level 2
RWCU Flow - High Manual Initiation
> -38 inches~
426 gpm NA a.
b.
C.
RCIC Steam Line b, Pressure High
< 153" HqO RCIC Steam Supply Pressure Low
> 60 psig RCIC Turbine Exhaust Diaphragm Pressure
- High
< 10.0 psig 5.
REACTOR CORE ISOLATION. COOLING SYSTEM ISOLATION
> -45 inches 436 gpm NA
< 165" HqO
> 53 psig
< 20.0 psig "These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION REACTOR CORE ISOLATION COOLING SYSTEM TRIP SETPOINT ISOLATION (Continued)
ALLOWABLE VALUE e.
g.
h.
RCIC Equipment Room Temperature High RCIC Equipment Room 6 Temperature High RCIC Pipe Routing Area Temperature
- High RCIC Pipe Routing Area 6 Temperature
- High RCIC Emergency Area Cooler Temperature
- High Manual Initiation Drywell Pressure
- High
< 167 F
< 89 F
< 267'F¹¹
< 89'F¹¹
< 147'F NA
< 1.72 psig
< 174 F
< 98 F"
< 174'F¹¹
< 98'F¹¹'
154 F
NA
< 1.88 psig
+ om O 0
~ a'o tD c+
Me ru e(
C) 0 0
g)
~ c+
~ ~
a.
b.
C.
e.
g.
HPCI Steam Line 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 8, Temperature - High Manual Initiation Drywell Pressure
- High 6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION
< 275 inches HqO
> 104 psig
< 10 psig
< 167'F
<89F
< 147 F
< 167 F¹¹
< 89 F¹¹ NA
< 172 psig
< 292 inches HqO 90 psig
< 20 psig
< 174'F
< 98 F
<154F
< 174'F¹¹
< 98'F¹¹*
NA
< 1.88 psig
- These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
l/I C:
C/1 AD ITl TRIP FUNCTION TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUHENTATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE 7.
RHR SYSTEH SHUTIXNN COOLING/HEAO SPRAY NODE ISOLATION 4JI CD a.
b.
C.
d.
g.
Drywell Pressure
- High Reactor Vessel Mater Level-Low, Level 3
Reactor Vessel (RHR Cut-in Permissive)
Pressure - High RHR Equipment Area h Temperature - High RHR Equipaent Area Temperature - High RHR Flow - High Hanual Initiation
> 13.0 inches"
< 98 psig
<89F
< 167F
< 25,000 gpm NA
< 1.72 psig
> 11.5 inches
< 108 psig
< 90.5 F
< 170.5 F
< 26,000 gpm NA
< 1.88 psig
- See Bases Figure B 3/4 3-1.
¹Lower setpoints for TSH-G33-2N600 E,
F and TOSH-G33-2K602 E,
F.
¹¹15 minute time delay.
o g
O
TABLE 4. 3. 2. 1-1 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS J
TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED a.
Reactor Vessel Water Level-b.
C.
1)
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
Drywell Pressure - High Manual Initiation d.
SGTS Exhaust Radiation - High e.
Main Steam Line Radiation-High SECONDARY CONTAINMENT ISOLATION S
S S
NA NA R
R R
R NA R
1, 2, 3
t 1,2,3 1, 2, 3
1 2
3 1,2,3 3
Q*** 5***
f 1,2,3 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 S
NA S
NA R
NA 1,2,3and*
1, 2, 3
1, 2, 3 and
- TABLE 4.3.2.1-1 (Continued)
OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED CHANNEL CALIBRATION 1
2, 3
1, 2, 3
1 1
2, 3 3k*
1, 2, 3
1, 2, 3*
1 2
3 NA NA 1
2 3
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL CHANNEL FUNCTIONAL TRIP FUNCTION CHECK TEST 3.
MAIN STEAM LINE ISOLATION a.
Reactor Vessel Water Level-Low Low Low, Level 1
S M
R b.
Main Steam Line Radiation-High S
M R
c.
Main Steam Line Pressure-Low NA M
d.
Main Steam Line Flow - High S
M R
e.
Condenser Vacuum Low NA M
Q f.
Reactor Building Main Steam Line Tunnel Temperature - High NA M
GJ g.
Reactor Building Main Steam Line Tunnel 6 Temperature-High M
Q h.
Manual Initiation R
NA i.
Turbine Building Main Steam Line Tunnel Temperature High NA M
4.
REACTOR WATER CLEANUP SYSTEM ISOLATION
+ om 0
CD o e
~ a'o fD c+
CD
+ ~a
~ we Cl D O
pp
& g+
LD 6)
CJl Q)
~ ~
a.
b.
C.
e.
f.
g.
RWCU 6 Flow High RWCU Area Temperature
- High RWCU Area Ventilation d Temperature High SLCS Initiation Reactor Vessel Water Level-Low Low, Level 2
RWCU Flow - High Manual Initiation S
NA NA NA S
S NA NA R
R NA
~These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
1, 2, 3
1, 2, 3
1, 2, 3" 1
2 3
1 2
3 1
2 3
1, 2, 3
TABLE 4.3.2.1-1 (Continued)
O Pl 2 0 (D
O tD CL CP O tD W 8
5 C P4 lD C)
Z v O
0
~
W c+
C) tD CO
~ ~
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS OPERATIONAL CONDITIONS FOR MHICH SURVEILLANCE RE UIRED CHANNEL CHANNEL FUNCTIONAL TRIP FUNCTION CHECK TEST 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION CHANNEL CALIBRATION RCIC Steam Line d Pressure High RCIC Steam Supply Pressure-Low 1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
i, z, s*
1, 2, 3
1, 2, 3*
NA b.
RCIC Turbine Exhaust Diaphragm Pressure High RCIC Equipment Room Temperature
- High RCIC Equipment Room h Temperature
- High RCIC Pipe Routing Area Temperature
- High RCIC Pipe Routing Area 6 Temperature High RCIC Emergency Area Cooler Temperature
- High Manual Initiation C.
e.
NA 1
2 3
1, 2, 3
1, 2, 3
e R
j.
Drywel 1 Pressur e High NA 6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION HPCI Steam Line 5 Pressure
- High HPCI Steam Supply Pressure Low a.
b.
1, 2, 3
1, 2
3 HPCI Turbine Exhaust Diaphragm Pressure
- High 1
2 3
~These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
TABLE 4.3.2. 1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE VIREO HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION (Continued) d.
HPCI Equipment Room Temperature
- High NA M
e.
HPCI Equipment Room 6 Temperature - High NA M
f.
HPCI Emergency Area Cooler Temperature
- High NA M
g.'PCI Pipe Routing Area Temperature
- High NA M
h.
HPCI Pipe Routing Area 6 Temperature
- High NA M
i.
Manual Initiation NA R
j.
Drywell Pressure
- High NA M
7.
RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION Q
NA R
1 2
3 1, 2, 3
1 2
3 1
2 3
34'A'**
1 2
3 1
2 3
~ om I 0c+
h O Q
~ urn (g
Al c+
5 Mo Me C)
+v lg 0
M <<+
c)I Q)
~ ~
<<O a.
b.
d.
e.f.
g.
hen with
"*When
"""When
"*""Th)s Reactor Vessel Water Level-Low, Level 3
Reactor Vessel (RHR Cut-in Permissive)
Pressure
- High RHR Equipment Area 6 Temperature High RHR Equipment Area Temperature - High RHR Flow - High Manual Initiation Drywell Pressure
- High 1
2 3
1 2
3 1
2 3
NA S
NA NA
,R NA R
M 1
2 3
M 1 2.3 R
1 2
3 M
1, 2, 3
hand sng irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations a potential for draining the reactor vessel.
reactor steam dome pressure
> 1043 psig and/or any turbine stop valve is open.
VENTING or PURGING the drywell per Specification
- 3. 11.2.8.
trip function need not be OPERABLE from October 19, 1989 to January 19, 1990.