ML17156B413
| ML17156B413 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/20/1989 |
| From: | Boger B Office of Nuclear Reactor Regulation |
| To: | Keiser H PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| NUDOCS 8910310297 | |
| Download: ML17156B413 (23) | |
Text
October 20, 9
Docket Nos. 50-387 and 50-388 Hr. Harold M. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Al1entown, Pennsylvania 18101
Dear h1r. Keiser:
SUBJECT:
CONFIRMATION OF CHANGE TO TECHNICAL RE:
SUSQUEHANNA STEAM ELECTRIC STATION, DISTRIBUTION: w/enclosures EJ d
NRC PDR BGrimes Local PDR THeek (4)
PDI-2 Rdg.
Ilanda Jones SVarga JCalvo BBoger RGoel WButler ACRS (10)
MThadani/JStone GPA/PA HO'Brien Rita Jaques,ARh1/LFMB OGC DHagan SPECIFICATIONS JLinvi 1 1 e JDyer UNITS 1
AND 2 CSchulten, OTSB This confirms our telephone authorization given on October 20, 1989, for the change to the Technical Specifications for Susquehanna Steam Electr ic Station, Units 1 and 2, as requested in your letter dated October 19, 1989.
Facility Operating License NPF-14 and Facility Operating License NPF-22 are amended as requested in your letter dated October 19, 1989.
The Technical Specification change permits relief from the provisions of Technical Specification Section 3.2.2 for a period of 3 months starting on October 20, 1989.
The corrected Technical Specification pages are enclosed.
I The formal license amendment and our completed safety evaluation of this change to the Technical Specifications for Susquehanna Steam Electric Station, Units 1
and 2, are being processed'and copies of these documents will be sent to you in the near future.
Sincerely,
Enclosures:
Technical Specification Pages cc w/enclosures:
See next page
/s/
Bruce A. Boger, Assistant Director for "Region I Reactors Division of Reactor Projects I/II Office of Nuclear Reactor Regulation I KEISER]
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UNITED STATES NUCLEAR R EGULATORY COMMISSION WASHINGTON, O. C. 20555 October 20, 1989 Docket Nos.
50-387 and 50-388 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Mr. Keiser:
SUBJECT:
CONFIRMATION OF CHANGE TO TECHNICAL SPECIFICATIONS RE:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS I AND 2 This confirms our telephone authorization given on'October 20, 1989, for the change to the Technical Specifications for Susquehanna Steam Electric Station, Units 1 and 2, as requested in your letter dated October 19, 1989.
Facility Operating License NPF-14 and Facility Operating License NPF-22 are amended as requested in your letter dated October 19, 1989.
The Technical Specification change permits relief from the provisions of Technical Specification Section 3.2.2 for a period of 3 months starting on October 20, 1989.
The corrected Technical Specification pages are enclosed.
The formal license amendment and our completed safety evaluation of this change to the Technical Specifications for Susquehanna Steam Electric Station, Units 1
and 2, are being processed and copies of these documents will be sent to you in the near future.
Sincerely,
Enclosures:
Technical Specification Pages cc w/enclosures:
See next page Bruce A.
B ger, Assistant Director for Region I Reactors Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Mr. Harold W. Keiser Pennsylvania Power 5 Light Company Susquehanna Steam Electric Station Units I 5 2
CC:
Jay Silberg, Esq.
Shaw, Pittman, Potts 8 Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.
M. Kenny Licensing Group Supervisor Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsylvania P. 0.
Box 2063 Harrisburg, Pennsylvania 17120 Mr. Jesse C. Tilton, III AI leg heny E 1 ec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harrisburg, Pennsylvania 17108-1266 Mr. S.
B. Ungerer Joint Generation Projects Department Atlantic Electric P.O.
Box 1500 1199 Black Horse Pike Pleasantville, New Jersey 08232 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Al'lendale Road King of Prussia, Pennsylvania 19406 Mr. R.
G. Byram Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company 2 North Ninth Street A 1 lentown, Pennsylvania 18101 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company 1009 Fowles Avenue Berwick, Pennsylvania 18603
AO m
D TRIP FUNCTION TABLE 3. 3. 2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION MINIMUM APPLICABLE ISOLATION( )
OPERABLE CHANNELS OPERATIONAL SIGNAL(s)
PER TRIP SYSTEM (b)
CONDITION ACTION 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.
Main Steam Line Flow - High D
Condenser Vacuum - Low UA Reactor Building Main Steam Line E
Tunnel Temperature
- High Reactor Building Main Steam Line E
Tunnel 6 Temperature
- High Manual Initiation NA E
h.
i.
Turbine Building Main Steam Line Tunnel Temperature-High 4.
REACTOR WATER CLEANUP SYSTEM ISOLAT'ION 2/l inc 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 24 21 O Pl 0
O tD cr o lD c+
5 Ae PO lD C) v O
I r+
Qj ~ ~
a.
b.
C.
d.
e.
f.
g.
RWCU 6 Flow - High RWCU Area Temperature
- High RWCU Area Ventilation 6 Temp.
High SLCS Initiation Reactor Vessel Water Level - Low Low, Level 2
RWCU Flow - High Manual Initiation 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.
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION O Pl 0 W C+ W O 0 D 0 lD c+
Wo C
po 6 CO v
Q I
rl M TTI Q)
~ ~
LD MINIMUM ISOLATION OPERABLE CHANNELS TRIP FUNCTION SIGNAL(s)
PER TRIP SYSTEM (b) 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.
RCIC Steam Line 6 Pressure
- High K
1 b.
RCIC Steam Supply Pressure
- Low KB c.
RCIC Turbine Exhaust Diaphragm K
Pressure
- High d.
RCIC Equipment Room Temperature
- High e.
RCIC Equipment Room IAI Temperature
- High f.
RCIC Emergency Area Cooler Temperature
- High g.
RCIC Pipe Routing Area 6 Temperature
- High h.
RCIC Pipe Routine Area Temperature
- High 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
ACTION 23 23 23*
23 23*
23 24 23 "These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
(A AD m
TABLE 3. 3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION MINIMUM APPLICABLE ISOLATION( )
OPERABLE CHANNELS OPERATIONAL SIGNAL(s)
PER TRIP SYSTEM (b)
CONDITION TRIP FUNCTION I
6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION ACTION a.
HPCI Steam Line 6 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 d
Temperature
- High f.
HPCI Emergency Area Cooler Temperature
- High g.
HPCI Pipe Routing Area Temperature
- High 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 O Pl 0c+ W O 0 cr n fD ~o C
MI O
v Q
Ql I
c+
lD lD (g
~ ~
h.
HPCI Pipe Routine Area 6 Temperature
- High i.
Manual Initiation j.
Drywell Pressure
- High NA 1,2,3 1
2 3.
1, 2
3 23K 24 23
~This trip function need not be OPERABLE from October 19, 1989 to January 19, 1990.
CA AD m
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 6 Temperature
- High
> 9.0 inches Hg vacuum
< 177 F
< 99'F
> 8.8 inches. Hg vacuum
< 184'F
< 108 F" CrJ I
CO O Pl O
c+o I a o I
c+
5
~I C
O Ql c+I Q)
~ ~
RWCU 6 Flow - High RWCU Area Temperature
- High RWCU/Area Ventilation 6 Temperature
- High SLCS Initiation e.
Reactor Vessel Water Level-Low Low, Level 2
f.
RWCU Flow - High g.
Manual Initiation
< 60 gpm
< 147 F or 118.3 F¹
< 69'F or 35 3'F¹ 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
< 154 F or 125.3 F¹
< 78'F or 44.3 F¹~
NA
> -45 inches
< 436 gpm NA a.
RCIC Steam Line 6 Pressure
- High b.
RCIC Steam Supply Pressure Low c.
RCIC Turbine Exhaust Diaphragm Pressure
- High
< 177" HHO
> 60 psig
< 10.0 psig
< 189" HgO
> 53 psig
< 20.0 psig "Ilrese trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
TABLE 3. 3. 2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 167.F"
< 147'F NA 1'RIP FUNCTION TRIP SETPOINT REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION Continued) d.
RCIC Equipment Room Temperature
- High
] 67 e.
RCIC Equipment Room 6 Temperature
- High
< 89 F
f.
RCIC Pipe Routing Area Temperature
- High g.
RCIC Pipe Routing Area 6 Temperature
- High
< 89 F
h.
RCIC Emergency Area Cooler Temperature
- High i.
Manual Initiation ALLOMABLE VALUE
< 174 F".'98 F*
98()FN' 154 F
NA Orywell Pressure High
<1.72 pslg
<1.88 psig HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION O Pl oc+ W o I a'
lD c+
C M Q O 0 Qk c
r+
MI (Q
~ ~
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 H20
> 104 psig
< 10 psig
< 167 F
< 89 F
< 147 F
1670F IIII
< 367 inches H20 90 psig
< 20 psig
<174 F
<98F
<154 F
< 174 F
- Lhese trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
AD TRIP FUNCTION I
h.
HPCI Pipe Routing Area A Temperature
- High i.
Manual Initiation TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP SETPOINT 89 F¹¹ NA ALLOWABLE VALUE 98(>F¹¹ NA j.
Drywel 1 Pressure
- High
<1. 72 ps i g
<1.88 psig 4J I
C)
O Pl 0
g+ W O Q Cf 0 tD Me C
M lD CI v
Q
~ g+
LO Q Q)
~ ~
7.
RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION a.
Reactor Vessel Water Level-Low, Level 3
b.
Reactor Vessel (RHR Cut-in Permissive)
Pressure
- High c.
RHR Equipment Area 6 Temperature
- High d.
RHR Equipment Area Temperature-High e.
RHR Flow - High f.
Manual Initiation g.
Drywell Pressure
- High
> 13.0 inches*
< 98 psig
<89F
< 167 F
< 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 F>gure B 3/4 3-1.
¹Lower setpoints for TSH-G33-1N600 E,
F and TOSH-G33-1N602 E,
F.
k¹15 minute time delay.
- This trip function 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 TRIP FUNCTION 3.
MAIN STEAM LINE ISOLATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST OPERATIONAL CHANNEL CONDITIONS FOR WHICH CALIBRATION SURVEILLANCE RE UIRED C.
- Low, Low Low, Level 1
Main Steam Line Radiation - High Main Steam Line Pressure Low NA 1
2 3
1,2;3 d.
Main Steam Line Flow High S
e.
Condenser Vacuum -
Low NA f.
Reactor Building Main Steam Line Tunnel Temperature
- High 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 NA 1,
2 3
2*%'
A'*
1,2,3 1, 2, 3*
I 1
2 3
1 2,
3 O Fl 0
O 0 O'
Ill <<+
5 Me to 00 fQ Me
~ ~
LD b.
f.
g.
RWCU d Flow - High RWCU Area Temperature
- High RWCU Area Ventilation Q
Temperature
- High SLCS Initiation Reactor Vessel Water Level -
Low Low, Level 2
RWCU Flow - High Manual Initiation S
NA NA NA S
S NA Q
NA R
R NA 1,2,3 1, 2, 3
i, 2, 3" 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 SURVEILI ANCE RE UIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR MHICH TRIP FUNCTION CHECK TEST CALIBRATION SURYEILLANCE RE UIREO 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION O Pl C1 c+
h o I C7 0I c+
wo C
Me O O Ql
~ c+
Me Q)
~ ~
NA NA a.
b.
HPCI Steam Line 6 Pressure
- High HPCI Steam Supply Pressure Low HPCI Turbine Exhaust Diaphragm Pressure
- High a.
RCIC Steam Line 6 Pressure High NA b.
RCIC Steam Supply Pressure-Low NA c.
RCIC Turbine Exhaust Diaphragm Pressure
- High d.
RCIC Equipment Room Temperature
- High NA e.
RCIC Equipment Room a Temperature
- High f.
RCIC Pipe Routing Area Temperature High NA g.
RCIC Pipe Routing Area b, Temperature
- High NA h.
RCIC Emergency Area Cooler Temperature
- High NA i.
Manual Initi ation 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
1 2
3 "These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
O Pl n
g+
O lD a'
CD 5
44 C
P4 Q O
~ g+
W lD QO
~ ~
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.
HPCI Equipment Room Temperature
- High M
Q 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
'hTgfefg(r(outN%lhhree NA M
6 Temperature
- High NA M
i.
Manual Initiation NA R
NA j.
Drywell Pressure
- High NA M
R 7.
RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION a.
Reactor Vessel Water Level-Low, Level 3
S M
R b.
Reactor Vessel (RHR Cut-in Permissive)
Pressure
- High M
1,2,3 c.
RHR Equipment Area 6 Temperature
- High NA M
Q 1,2,3 d.
RHR Equipment Area Temperature-High M
1, 2, 3
e.
RHR Flow - High M
R 1
2 3
f.
Manual Initiation R
NA 1,2,3 g.
Drywell Pressure
- High M
R 1,2,3 NA 1
2, 3
1, 2, 3
3**)k*
1, 2, 3
1, 2, 3
1, 2, 3
NA NA S
NA NA When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
"" When reactor steam dome pressure
> 1043 psig and/or any turbine stop valve is open.
- "" When VENTING or PURGING the drywell per Specification
- 3. 11.2.8.
"*""This trip function need not be OPERABLE from October 19, 1989 to January 19, 1990.
AD m
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 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.
e.
Hain Steam Line Flow - High D
Condenser Vacuum - Low UA Reactor Building Main Steam E
Line Tunnel Temperature
- High Reactor Building Main Steam E
Line Tunnel 6 Temperature
- High Manual Initiation NA i.
Turbine Building Main Steam Line E
" Tunnel Temperature High 4.
REACTOR MATER CLEANUP SYSTEM ISOLATION 2
2/line 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 I
24 21 om n m t+ W O 0 C7 0 lD c+
C po I Cl v
Q WQ (Q
~ ~
g.
RWCU 6 Flow - High RWCU Area Temperature
- High RMCU Area Ventilation 6 Temperature
- High SLCS Initiation Reactor Vessel Mater Level -
Low Low, Level 2
RWCU Flow - High Manual Initiation J
NA 123 1, 2, 3
1 2
3 1,
2 3
1, 2
3 1,
2 3
1, 2
3 23 23 n*
23 23 23 24
" these trip functions need not be OPERABLE from October 19,
.1989 to January 1, 1990.
TABLE 3. 3. 2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION MINIMUM ISOLATION OPERABLE CHANNELS SIGNAL(S)(a)
PER TRIP SYSTEM (b) a.
RCIC Steam Line 6-Pressure
-High K
S b.
RCIC Steam Supply KB Pressure Low c.
RCIC Turbine Exhaust Diaphragm Pressure
- High d.
RCIC Equipment Room Temperature
- High e.
RCIC Equipment Room 6 Temperature
- High f.
RCIC Pipe Routing Area Temperature
- High g.
RCIC Pipe Routing Area 6 Temperature
- High 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
ACTION 23 23 23 23 23 h.
RCIC Emergency Area Cooler Temperature
- High 1, 2, 3
O Pl 0
i.
Manual Initiation NA 5 A
~
)
)
C j.
Diywell Pressure
- High Z
2
~
~
"These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
23 24 23
TABLE 3.3. 2-1 (Cont inued)
ISOLATION ACTUATION INSTRUMENTATION HPCI Steam Line d Pressure-High 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 MINIMUM ISOLATION OPERABLE CHANNELS TRIP FUNCTION SIGNAL(S)(a)
PER TRIP SYSTEM (b) 6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION APPLICABLE OPERATIONAL CONDITION 1
2 3
1 2,
3 1
2 3
1 2
3 1,2,3 1, 2, 3
l 2
3 ACTION 23 23 23 23 23 23 23 O Pl 0c+ W O
tO O O lD c+
5 Ma M Q O
v Q
Me Q)
~ ~
LO h.
HPCI Pipe Routing Area h Temperature
- High i.
Manual Initiation j.
Drywell Pressure
- High 1, 2, 3
1, 2, 3
1, 2, 3
- This trip function need not be OPERABLE from October 19, 1989 to January 19, 1990.
23*
24
TRIP FUNCTION TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE MAIN STEAN LINE ISOLATION (Continued) e.
'Condenser Vacuum - Low f.
Reactor Building Main Steam Line Tunnel Temperature High g.
Reactor Building Main Steam Line Tunnel 6 Temperature
- High h.
Manual Initiation i.
Turbine Building Main Steam Line Tunnel Temperature High 4.
REACTOR MATER CLEANUP SYSTEM ISOLATION
> 9.0 inches Hg vacuum
< 177 F
<99F NA
< 177 F
> 8.8 inches Hg vacuum
< 184 F
< 108'F*
NA
< 184 F
om 0
C+
O Q O O lD-c+
$ ~e C
M 4 Cl O Ql I
c+
C) tD
'Q)
~ ~
d.
e.
f.
g.
RMCU 5 F 1 ow High RMCU Area Temperature
- High RMCU/Area Ventilation L 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
< 69'F or 35.3'F¹ NA
> -38 inches" 426 gpm NA C.
RCIC Steam Line 6 Pressure
- High
< 153" H>0 RCIC Steam Supply Pressure Low
> 60 psig RCIC Turbine Exhaust Diaphragm Pressure
- High
< 10.0 psig 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
< 80 gpm
< 154 F or 125.3 F¹
< 78 F or 44.3 F¹*
NA
> -45 inches 436 gpm NA
< 165" H~O
> 53 psig
< 20.0 psig "lnese trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
TRIP FUNCTION TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE r
4 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 Orywell Pressure
- High
<167F
< 89 F
< 167'F¹¹
< 89 F¹¹
<147F NA
< 1.72 psig 1.
J
~
6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Continued)
< 174 F
< 98 F"
< 174 F¹¹
< 98 F¹¹*
< 154 F
NA
< 1.88 psig O Pl 0
E+
h O
lD CP O lD c+
5 Mo M Q v
Q Dl
~ c+
4D Q (Q
~ ~
LD a.
b.
C.
h.
HPCI Steam Line Flow - High HPCI Steam Supply Pressure Low HPCI Turbine Exhaust Diaphragm Pressure
- High HPCI Equipment Room Temperature
- High HPCI Equipment Room D, Temperature High HPCI Emergency Area Cooler Temperature - High HPCI Pipe Routing Area Temperature
- High HPCI Pipe Routing Area 6 Temperature
- High Manual Initiation Drywell Pressure
- High
< 275 inches H~O
> 104 psig
< 10 psig
< 167 F
< 89 F
< 147 F
< 167 F¹¹
< 89'F¹¹ NA
< 1.72 psig
< 292 inches H>0 90 psig
< 20 psig
< 174 F
< 98'F
< 154 F
< 174'F¹¹
< 98 F¹¹*
NA
< 1.88 psig
- lhese trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
TABLE 4. 3. 2. 1-1 (Continued)
OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED CHANNEL CHECK 1
2, 3
1, 2, 3
1 1,
2 3
]
2A'*
3A*
1,2 3
1, 2, 3*
1, 2, 3
1, 2
3 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION TEST CALIBRATION 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
Q 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
g.
Reactor Building l1ain Steam Line Tunnel 6 Temperature-High NA-M h.
Manual Initiation NA R
NA Turbine Building Main Steam Line Tunnel Temperature
- High NA M
4.
REACTOR WATER CLEANUP SYSTEM ISOLATION S
NA RWCU 6 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 b.
C.
NA NA NA R
R NA O Pl d.
R e.
S M
f.
S M
g.
NA R
Cl v
"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 (Conti nued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS om 0r+ W O tD tZ O tD <<0 Wo C
MQ C) v Q
H c+
M lD (Q
~ ~
tQ a.
RCIC Steam Line 6 Pressure High NA b.
RCIC Steam Supply Pressure-Low NA c.
RCIC Turbine Exhaust Oiaphragm Pressure
- High NA d.
RCIC Equipment Room Temperature
- High NA e.
RCIC Equipment Room 6 Temperature
- High 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.
Orywell Pressure High NA HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION NA a.
b.
HPCI Steam Line 6 Pressure
- High HPCI Steam Supply Pressure Low HPCI Turbine Exhaust Oiaphragm Pressure
- High NA NA CHANNEL CHANNEL FUNCTIONAL TRIP FUNCTION CHECK TEST 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION CHANNEL CALIBRATION NA R
OPERATIONAL CONOITIONS FOR MHICH SURVEILLANCE RE UIREO 1, 2, 3
1, 2, 3
1 2
3 1, 2, 3
X, Z, 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
se trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
(A AD m
30'RIP FUNClION CHANNEL CHANNEL FUNCTIONAL CHECK TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR MHICH SURVEILLANCE RE UIRED TABLE 4. 3. 2. 1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREHENTS HIGH PRESSURE COOLANT INJECTION SYSTEH ISOLATION (Continued)
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 6 Temperature
- High Hanual Initiation Drywell Pressure
- High NA NA NA NA NA NA NA R
1, 2, 3
1, 2, 3
1, 2, 3
1 2
3
]
2 3)k)%*A 1, 2, 3
1, 2, 3
7.
RHR SYSTEH SHUTDOWN COOLING/HEAD SPRAY NODE ISOLATION O Pl 0 W O 0 O 0 fD c+
Mo P4 Q Cl v
Q
~ c+
C) tD
~
~ ~
e.f.
g.
When with
- When
"'"Mhen AxhAThgs Reactor Vessel Mater Level-Low, Level 3
Reactor Vessel (RHR Cut-in Permissive} Pressure
- High RHR Equipment Area a Temperature
- High RHR Equipment Area Temperature
- High RHR Flow - High Manual Initiation Drywell Pressure
- High NA NA NA S
NA NA R
NA R
1 2
3 1, 2, 3
1, 2
3 1
2 1, 2, 1, 2,
-1 2
operations handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and 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.