ML20100F419
| ML20100F419 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/14/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20100F423 | List: |
| References | |
| NPF-39-A-112, NPF-85-A-074 NUDOCS 9602210284 | |
| Download: ML20100F419 (28) | |
Text
1l W aru j
p i
UNITED STATE 3 g
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 200stM1001
\\...../
PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 j
LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.112 License No. NPF-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated July 28, 1995, complies with the standards and l
requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and 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 rules and 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; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l l
l 1
9602210284 960214 i
PDR ADOCK 05000352 P
PDR j
..m.
.m-..
m._
, 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-39 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 112, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days.
FOR THE NOCLEAR REGULATORY C0fMISSION I
Jo n F. Stolz, Direc r P oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 14,1996
l ATTACHMENT TO LICENSE AMENDMENT NO.112 FACIllTY OPERATING LICENSE No. NPF-39 DOCKET NO. 50-352 i
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 3-14 3/4 3-14 3/4 3-15 3/4 3-15 l
3/4 3-17 3/4 3-17 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 1
3/4 3-25 3/4 3-25 3/4 3-26 3/4 3-26 3/4 3-30 3/4 3-30 3/4 3-31 3/4 3-31 3/4 6-22 3/4 6-22 3/4 6-26 3/4 6-26 4
A C
TABLE 3.3.2-1 (Continued) iR ISOLATION ACTUATION INSTRWlENTATION 5
R NININUN APPLICA8LE ISOLATION OPERABLE CHANNELS OPERATIONAL hTRIPFUNCTION SIGNAL
PER TRIP SYSTEN '*3 ColGITION AfJJgi 5
- 6.
PRINARY CONTAllelENT ISOLATION a.
Low, Low - Level 2 8
2 1, 2, 3 20 2)
Low, Low, Low - Level 1 C
2 1, 2, 3 20 b.
Drywell Pressure - High H
2 1, 2, 3 20 c.
North Stack Effluent '
Radiation - High
W l
1, 2, 3 ~
23 d.
Deleted Y%
e.
Reactor Enclosure Ventilation Exhaust Duct-Radiation - High S
2 1, 2, 3 23 f.
Deleted l
t g.
Deleted h.
Drywell Pressure - High/
y Reactor Pressure - Low G
2/2 1, 2, 3 26
$g 1.
Primary Containment Instrument N
1 1, 2, 3 26 Gas Line to Drywell A
!?
Pressure - Low i
j.
Manual Initiation NA 1
1, 2, 3 24 2
m
I l
l
~
l C
. TABLE 3.3.2-1 (Continued) i5 ISOLATION ACTUATION INSTIMENTATION 5
i R
MININLM APPLICABLE ISOLATION OPERABLE CHANNELS OPERATIONAL hTRIPFUNCTION S IGNAL"' *"'
PER TRIP SYSTEN '*8 ColEITION gIlg
}
7.
SEColdlARY CONTAll0ENT ISOLATION a.
Reactor Vessel Water Level Low, Low - Level 2 8
2 1, 2, 3 25 I
+
b.
Drywell Pressure - High H
2 1, 2, 3 25 c.l.
Refueling Area Unit 1 Ventilation Exhaust Duct Radiation - High R
2
- f 25 2.
Refueling Area Unit 2 Ventilation 3
Exhaust Duct Radiation - High R
2 25 Y
d.
Reactor Enclosure Ventilation Exhaust G
Duct Radiation - High S
2 1, 2, 3 25 I
e.
Deleted 5
i a
f.
Deleted j
8 t
a g.
Reactor Enclosure
(
Manual Initiation MA 1
1, 2, 3 24 z
P h.
Refueling Area Manual Initiation MA 1
25 t
=
.O
=
=
' :.iI 4
.=
4 TABLE 3.3.2-1 (Continued) i TABLE NOTATIONS j
(c)
Actuates secondary containment isolation valves shown in Table 3.6.5.2.1-1 and/or 3.6.5.2.2-1 and signals B, H, S, and R also start the standby gas l
treatment system.
(d)
RWCU system inlet outboard isolation valve closes on SLCS "8" initiation.
RWCU system inlet inboard isolation valve closes on SLCS "A" or SLCS "C" initiation.
j (e)
Manual initiation isolates the steam supply line outboard isolation valve and only following manual or automatic initiation of the system.
(f)
In the event of a loss of ventilation the temperature - high setpoint may be reised by 50"F for a period not to exceed 30 minutes to permit restoration of the ventilation flow without a spurious trip. During the 30 minute wriod, an operator, or other qualified member of the technical staff, shall osserve the temperature indications continuously, so that, in the event of rapid increases in temperature, the main steam lines shall be manually isolated.
(g)
Wide range accident monitor per Specification 3.3.7.5.
LIMERICK - UNIT 1 3/4 3-17 Amendment No. 28,53,112
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUNENTATION SETPOINTS i
ALLOMA8LE g TRIP FUNCTION TRIP SETPOINT VALK
[6.
PRIMARY CONTAllBENT ISptATI(31 a.
Low, Low - Level 2 2 -38 inches
- 2 -4S inches 2.
Low, Low, Low - Level 1 2 -129 inches
- 2 -136 inches b.
Drywell Pressure - High s 1.68 psig s 1.8b esig c.
North Stack Effluent' Radiation - High 5 2.1 pC1/cc s 4.0 pC1/cc d.
Deleted
[
e.
Reactor Enclosure Ventilation Exhaust Duct - Radiation - High s 1.35 mR/h 5 1.5 mR/h f.
Dcleted l
g.
Deleted k
h.
Drywell Pressure - High/
s 1.68 psig/
s 1.88 psig/
a Reactor Pressure - Low 2 455 psig (decreasing) 2 435 psig (decreasing) 8 5
1.
Primary Containment Instrument 2 2.0 psi 2 1.9 psi Gas to Drywell a Pressure - Low z
P J.
Manual Initiation N.A.
N.A.
=
d
--- <a-
__----_-,-------_c-----_-.---e a-
l i
i 1
Y i
{
TABLE 3.3.2-2 (Continued) m ISOLATION ACTUATION INSTR 15ENTATION SETPOINTS i
n i
ALLOWABLE i
g TRIP FUNCTION TRIP SETPOINT VALUE
~
[7.
SEC0lNIARY CONTAll0ENT {SopTIM a.
Low, Low - Level 2 2 -38 inches
- 2 -45 inches
[
b.
Drywell Pressure - High s 1.68 psig s 1.88 psig c.l.
Refueling Area Unit 1 Ventilation Exhaust Duct Radiation - High s 2.0 mR/h s 2.2 mR/h 2.
Refueling Area Unit 2 Ventilation w
2 Exhaust Duct Radiation - High 5 2.0 mR/h s 2.2 mR/h
[
d.
Reactor Enclosure Ventilation Exhaust Duct Radiation - High s 1.35 mR/h 5 1.5 mR/h m
i e.
Deleted f
g
{
i.
Deleted ma g.
Reactor Enclosure Manual 2
Initiation M.A.
N.A.
A h.
Refueling Area Manual Initiation N.A.
N.A.
t z
?
?
E C
- See Bases Figure B 3/4 3-1.
- The low setpoints are for the RWCU Heat Exchanger Rooms; the high setpoints are for the pump rooms.
l TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESDONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#
6.
PRIMARY CONTAIMENT ISOLATION a.
Low, Low - Level 2 s 13")
2)
Low, Low, low - Level I s 13"'
b.
Drywell Pressure - High 5 13")
c.
North Stack Effluent Radiation - High N.A.
d.
Deleted e.
Reactor Enclosure Ventilation Exhaust Duct - Radiation - High N.A.
f.
Deleted l
g.
Deleted h.
Drywell Pressure - High/
Reactor Pressure - Low N.A.
1.
Primary Containment Instrument Gas to N.A.
Drywell A Pressure - Low
.j.
Manual Inittaiton N.A.
7.
SECOMARY CONTAIMENT ISOLATION a.
Reactor Vessel Water Level Low, Low - Level 2 N.A.
b.
Drywell Pressure - High N.A.
c.1.
Refueli Area Unit 1 Ventilation Exhaust et Radiation - High N.A.
2.
Refuelig Area Unit 2 Ventilation Exhaust het Radiation - High N.A.
d.
Reactor Enclosure Ventilation Exhaust Duct Radiation - High M.A.
e.
Deleted l
LINERICK - UNIT 1 3/4 3-25 Amendment 23,112
=.. -. -. - -. -. _ ~ - -. -
_.. _. _. ~ - -. _ - --.
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#
f.
Deleted l
g.
Reactor Enclosure Manual 3
Initiation
-N.A.
h.
Refueling Area Manual Initiation N.A.
TABLE NOTATIONS (a)
Isolation system instrumentation response time specified inc1udes 10 seconds diesel generator starting and 3 seconds for sequence loading delays.
(b)
DELETED Isolation system instrumentation response time for MSIV only. No diesel generator delays assumed for MSIVs.
Isolation system instrumentation response time for associated valves except MSIVs.
Isolation system instrumentation response time specified for the Trip i
Function actuating each valve group shall be added to isolation time shown in Tables 3.6.3-1, 3.6.5.2.1-1 and 3.6.5.2.2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.
With 45 second time delay.
i l
t LIMERICK - UNIT 1 3/4 3-26 Amendment No, g,gg.112 l
=
b f
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUNENTATION SURVEILLANCE REQUIRENENTS
^
i CHANNEL OPERATIONAL e
CHANNEL FUNCTIONAL CHAfMIEL C0fSITIONS FOR WHICH i
5 TRIP FUNCTION CHECK TEST CALIBRATION SURVEILL M E REQUIRE 6.
PRIMARY CONTAllWElfT ISOLATION
(
~
a.
Ifeactor Vessel Water Level 1)
Low, Low - Level 2 S
Q R
1, 2, 3 2)
Low, Low, Low - Level 1 S
Q R
1, 2, 3 b.
Drywell Pressure ## - High S
Q R
1, 2, 3 c.
North Stack Effluent I
Radiation - High S
Q R
1, 2, 3 l
1 l
d.
Deleted m
i e.
Reactor Enclosure Ventilation Exhaust Duct - Radiation - High S
Q R
1, 2, 3 f.
Deleted l
g E
g.
Deleted i
5 i
5 h.
Drywell Pressure - High/
j Reactor Pressure - Low Q
R 1, 2, 3
=
(
k 1.
Primary Containment Instrument Gas to Drywell a Pressure - Low N.A.
M Q
1, 2, 3 L
iG j.
Manual Initiation N.A.
R N.A.
1, 2, 3 l
P
l TABLE 4.3.2.1-1 (Continued)
~
ISOLATION ACTUATION INSTRIMENTATION SURVEILLANCE SEQUIRENfqTS N
CHANNEL OPERATIONAL E
CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH R
TRIP FUNCTION
_ CHECK TEST CALIBRATION SURVEILLANCE REQUIRED L
i c
7.
SECOMARY CONTAllNEllT ISOLATION 1
5 a.
[
[
Low, Low - Level 2 S
Q R
1, 2, 3 l
b.
Drywell PressureN - High S
Q R
1, 2, 3
(
i c.l.
Refueling Area Unit 1 Ventilation Exhaust Duct Radiation - High S
Q R
2.
Refueling Area Unit 2 Ventilation Exhaust Duct Radiation - High S
Q R
i d.
Reactor Enclosure Ventilation
[
m l
3 Exhaust Duct Radiation - High S
Q R
1, 2, 3 l
t
[
e.
Deleted j
f.
Deleted F
g.
Reactor Enclosure l
[
Manual Initiation N.A.
R N.A.
1, 2, 3 a
h.
Refueling Area
[
Manual Initiation N.A.
R N.A.
O t
U
- Required when (1) handling irradiated fuel in the refueling area secondary containment, or (2) during CORE l
b ALTERATIONS, or (3) during operations with a potential for draining the reactor vessel with the vessel head removed and fuel in the vessel.
j w
'g
- When not administratively bypassed and/or when any turbine stop valve is open.
- During operation of the associated Unit 1 or Unit 2 ventilation exhaust system.
b ffThese trip functions (2a, 6b, and 7b) are common to the RPS actuation trip function.
(
TABLE 3.6.3-1 (ContinggQ
~
PART A - PRIMARY CONTAllelENT ISOLATION VALVES INBOARD OUTBOARn
- ISOL, C PENETRATION FUNCTION ISOLATION ISOLATION MAX. ISOL.
SIGNAL (S), NOTES P&ID E NUISER BARRIER BARRIER TINE. IF APP.
IF APP.
5 JSEC) (26)
(20) n 025 DRYWELL PURGE SUPPLY HV57-121(X-201A) 5**
B,H,S,W,R 3,11,14 57 e
HV57-123 5**
B,H,S,W,R 3,11,14 5
HV57-109 6**
8,H,S,W,R 11 (X-201A)
~
HYS7-131 5**
B,H,S,W,R 11 (X-201A)
HV57-135 6**
B,H,5,W,R 11 HYDROGEN RECCfBINER *B" HV57-163 9
B,H,R,5 3,11,14 INLET FV-C-00-1018 90 B H,R,5 11 026 DRYWELL PURGE EXHAUST HV57-Il4 5**
B,H,S W.R 3.11,14,33 57 HV57-Ill 15**
B,H,S,R 11 SV57-139 5
10 HV57-Il5 6**
B,H,S,W,R 11,33 g,
HV57-Il7 5**
B,H,S,R 11 m
SV57-145 5
B,H,R,5 11 HYDROGEN RECCISINER "A" HV57-161 9
B,H,R,S, 3,11,14 2
INLET FV-C-00-101A 90 B,H,R,5 11
%o 027A CONTAllelENT INSTRt30ENT 59-ll28(CK)
NA 59
==
GAS SUPPLY TO ADS VALVES HV59-151A 45 N
g H,N,&S 3 028A-1 RECIRC LOOP SAMPLE HV43-IF019 10 B
43
'g HV43-IF020 10 B
C 028A-2' DRYWELL H2/02 SAMPLE SV57-132 5
B,H,R,5 11 57 SV57-142 5
B,H,R,5 11 028A-3 DRYWELL H2/02 SAMPLE SV57-134 5
B,H,R.S 11 57 SV57-144 5
B,H,R,5 11
i
~
TABLE 3.6.3-1 (Continued)
PART A - PRIMARY CONTAll8ENT ISOLATION VALVES l
C INBOARD OUTBOARD ISOL.
i R
PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.
SIGNAL (S),
NOTES P&ID E
NUMBER SARRIER BARRIER TINE.IF APP.
IF APP.
R (SEC)(26)
(20) i l
s t
c SV57-191 5
B,H,R,5 11 5
(X-2204) l
-4 t
~
116 S1Af08Y LIQUID CONTROL 48-IF007(CK)
NA 48 (X-42)
HV48-IF0068 60 29 l
1178-1 DRYWELL RADIATION SV26-190A 5
8,H,R,5 11 26 MONITORING SUPPLY SV26-1908 5
8,H,R.S 11 t
1178-2 DRYWELL RADIATION SV26-190C 5
8,H,R,5 11 26 MONITORING RETURN SV26-1900 5
8,H,R,5 11 i
201A SUPPRESSION POOL PURGE HV57-124 5**
8,H.S W,R 3,11,14 57 m1 SUPPLY HV57-131(X-25) 5**
8,H,S,W,R 3,11,14 HV57-109(X-25) 6**
8,H,S,W R 11 A,
HV57-147 6**
8,H,S,W,R 11 l
HV57-121(X-25) 5**
8,H,S,W,R 11 l
HYDROGEN RECON 8INER "8" HV57-164 9
8,H,R,S 3,11,14 EXHAUST HV57-169 9
8,H,R,S 11 iii I
<o 202 SUPPRESSION POOL PURGE HV57-104 5**
8,H.S W,R 3.11,14,33 57 l
E EXHAUST HV57-105 15**
8,H,S,R 11 l
2 HV57-Il2 6**
8,H,S,W,R 11,33 l
A HV57-Il8 5**
8,H,S,R 11 SV57-185 5
8,H,R,5 11 p
=
HYDR 0 GEN REC 0fBINER "A" HV57-162 9
8,H,R,5 3,11,14 l
h EXHAUST HV57-166 9
8,H,R,5 11 l
h h
203A(8,C,D) RHR Ptw SUCTION HV51-IF004A(8, 240 29,35 51 C,0) i PSV51-IF0304 NA 35 l
(B C.D)
I C
i
q puerug p
UNITED STATES s
j NUCLEAR REGULATORY COMMISSION
%..... #j WASHINGTON, D.C. 20066 0001 PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENS1 Amendment No.74 License No. NPF-85 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated July 28, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and 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 rules and 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; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuancs of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l-1 l {
l l
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 74
, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance, to be l
implemented within 30 days.
t FOR THE NUCLEAR REGULATORY COMISSION l
o F. Stolz, Dire r
ject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 14, 1996 l
i i
l
\\
1 l
1
r ATTACHMENT TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and i
contain vertical lines indicating the area of change.
Remove Insert 3/4 3-14 3/4 3-14 3/4 3-15 3/4 3-15 3/4 3-17 3/4 5-17 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-25 3/4 3-25 3/4 3-26 3/4 3-26 3/4 3-30 3/4 3-30 3/4 3-31 3/4 3-31 3/4 6-22 3/4 6-22 3/4 6-26 3/4 6-26 i
1
C TABLE 3.3.2-1 (Continued)
R ISOLATI(NI ACTUATION !NSTRMATION 5
Q MINIIRM APPLICABLE ISOLATION OPERABLE CHAlsIELS OPERATIONAL h TRIP FUllCTION SIGilAL" PER TRIP SYSTEM "
C01EITION jfdig U 6.
PRIMARY CollTAllBENT ISOLATI(NI m
a.
Low, Low - Level 2 8
2 1, 2, 3 20 2)
Low, Low, Low - Level I C
2 1, 2, 3 20 b.
Drywell Pressure - High H
2 1, 2, 3 20 c.
North Stack Effluent Radiation - High
- W I
1, 2, 3 23
{
d.
Deleted Y
e.
Reactor Enclosure Ventilation Exhaust Duct-Radiation - High S
2 1, 2, 3 23 f.
Deleted g.
Deleted a
h.
Drywell Pressure - High/
Reactor Pressure - Low G
2/2 1, 2, 3 26 1.
Primary Containment Instrument M
1 1, 2, 3 26 Gas Line to Drywell a Pressure - Low E
j.
Manual Initiation NA 1
1, 2, 3 24 9
3 o-
h TABLE 3.3.2-1 (Continued) g ISOLATION ACTUATION INSTRLMENTATION
- s M
NININUN APPLICABLE ISOLATION OPERA 8LE CHANNELS OPERATIONAL E TRIP FUNCTION SIGNAL"3 *"8 PER TRIP SYSTEN "3 COMITION Ellg
-[7.
SECO M ARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level Low, Low - Level 2 8
2 1, 2, 3 25 b.
Drywell Pressure - High H
2 1, 2, 3 25 c.1.
Refueling Area Unit 1 Ventilation Exhaust Duct Radiation - High R
2
- f 25 w
2.
Refueling Area Unit 2 Ventilation 1
Exhaust Duct Radiation - High R
2 25 5
d.
Reactor Enclosure Ventilation Exhaust Duct Radiation - High S
2 1, 2, 3 25 e.
Deleted k
f.
Deleted E
2 g.
Reactor Enclosure 3
Manual Initiation NA 1
1, 2, 3 24 h
h.
Refuelir.g Area Manual Initiation NA 1
25 E
A
TABLE 3.3.2-1 (Continued)
TABLE NOTATIONS (c)
Actuates secondary containment isolation valves shown in Table 3.6.5.2.1-1 and/or 3.6.5.2.2-1 and signal 8, H, S, and R also start the standby gas l
treatment system.
(d)
RWCU system inlet outboard isolation valve closes on SLCS "B" initiation.
RWCU system inlet inboard isolation valve closes on SLCS "A" or SLCS "C" initiation.
1
-(e)
Manual initiation isolates the steam supply line outboard isolation valve and only following manual or automatic initiation of the system.
(f)
In the event of a loss of ventilation the temperature - high setpoint may be i
raised by 50"F for a period not to exceed 30 minutes to permit restoration of the ventilation flow without a spurious trip. During the 30 minute period, an operator, or other qualified member of the technical staff, shall observe the temperature indications continuously, so that, in the event of rapid increases in temperature, the main steam lines shall be manually isolated.
(g)
Wide range accident monitor per Specification 3.3.7.5.
i LIMERICK - UNIT 2 3/4 3-17 Amendment No. 17,74
s l
l l
t l
l TABLE 3.3.2-2 (Continued) m I
ISOLATION ACTUATION INSTRtflENTATION SETPOINTS x
8 ALLOWA8LE g TRIP FUNCTION TRIP SETPOINT VALUE 6.
PRINARY CONTAllelENT I$0LSTION a.
Low, Low - Level 2 2 -38 inches
- 2 -45 inches 2.
Low, Low, Low, Level 1 2 -129 inches
- 2 -136 inches b.
Drywell Pressure - High s 1.68 psig s 1.88 psig c.
North Stack Effluent t
Radiation - High 5 2.1 pC1/cc s 4.0 pct /cc d.
Deleted f
e.
Reactor Enclosure Ventilation Exhaust Duct - Radiation - High s 1.35 mR/h 5 1.5 mR/h f.
Deleted l
g.
Deleted i
N 8
h.
Drywell Pressure - High/
$ 1.68 psig/
s 1.88 psig/
Reactor Pressure - Low 2 455 psig (decreasing) 2 435 psig (decreasing) 1.
Primary Containment Instrument 2 2.0 psi 2 1.9 psi Gas to Drywell A Pressure - Low j.
Manual Initiation N.A.
M.A.
I
C TABLE 3.3.2-2 (Continued)
Ri'i ISOLATION ACTUATION INSTRUNENTATI0ll SETPOINTS R
ALLONABLE TRIP FUNCTION TRIP SETPOINT VALK g
]7.
SEC0fNIARY CONTAllSENT ISOLATION a.
Low, Low - Level 2 2 -38 inches
- 2 -45 inches b.
Drywell Pressure - High s 1.68 psig s 1.88 psig c.l.
Refueling Area Unit 1 Ventilation Exhaust Duct Radiation - High 5 2.0 mR/h s 2.2 mR/h 2.
Refueling Area Unit 2 Ventilation Exhaust Duct Radiation - High 5 2.0 mR/h s 2.2 mR/h 4
Y d.
Reactor Enclosure Ventilation Exhaust U
Duct Radiation - High s 1.35 mR/h s 1.5 mR/h e.
Deleted y
f.
Deleted n>
E g.
Reactor Enclosure Manual l
Initiation N.A.
N.A.
l c+
g h.
Refueling Area Nanual Initiation N.A.
N.A.
if
- See Bases Figure 8 3/4 3-1.
- The low setpoints are for the RWCU Heat Exchanger Rooms; the high setpoints are for the pump rooms.
i
i TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME I.[tIP FUNCTION RESPONSE TIME (Seconds)f 6.
PRIMARY CONTAINMENT ISOLATION a.
Low, Low - Level 2 s 13(*)
2)
Low, Low, Low - Level 1 s 13(*)
b.
Drywell Pressure - High s 13(*)
c.
North Stack Effluent Radiation - High N.A.
d.
Deleted e.
Reactor Enclosure Ventilation Exhaust Duct - Radiation - High N.A.
f.
Deleted g.
Deleted h.
Drywell Pressure - High/
Reactor Pressure - Low N.A.
1.
Primary Containment Instrument Gas to Drywell A Pressure - Low N.A.
j.
Manual Initiation N.A.
7.
SECONDARY CONTAllelENT ISOLATION a.
Reactor Vessel Water Level Low, Low - Level 2 N.A.
b.
Drywell Pressure - High N.A.
c.l.
Refueling Area Unit 1 Ventilation Exhaust Imet Radiation - High N.A.
I 2.
Refueling Area Unit 2 Ventilation Exhaust Duct Radiation - High N.A.
d.
Reactor Enclosure Ventilation Exhaust Duct Radiation - High N.A.
1 e.
Deleted l
LIMERICK - UNIT 2 3/4 3-25 Amendment No. 74 1
l i
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TINE (Seconds)#
f.
Deleted l
g.
Reactor Enclosure Manual Initiation N.A.
h.
Refueling Area Manual Initiation N.A.
TABLE NOTATIONS (a)
Isolation system instrumentation response time specified includes 10 seconds diesel generator starting and 3 seconds for sequence loading delays.
(b)
DELETED Isolation system instrumentation response time for MSIV only. No diesel generator delays assumed for MSIVs.
Isolation system instrumentation response time for associated valves except MSIVs.
Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown in Tabl2s 3.6.3-1, 3.6.5.2.1-1 and 3.6.5.2.2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.
With 45 second time delay.
LIMERICK - UNIT 2 3/4 3-26 Amendment No. 52,74
h TABLE 4.3.2.1-1 (Continued) m ISOLATT)N ACTUATION INSTRIMENTATION SURVEILLANCE REQUIREMENTS i
i CHAMEL OPERATIONAL i
e CHANNEL FUNCTIONAL CHAlelEL CONDITIONS FOR WICH TRIP FUNCTION CHECK TEST CALIDRATION SURVEILL$NCF REQUIRE l
6.
PRIMARY CONTAllpElg ISOLATION a.
Reactor Vessel Nater Level 1)
Low, Low - Level 2 S
Q R
1, 2, 3 2)
Low, Low, Low - Level 1 S
Q R
1, 2, 3 b.
Drywell Pressure ## - High S
Q R
1, 2, 3 l
c.
North Stack Effluent Radiation - High S
Q R
1, 2, 3 l
w1 d.
Deleted i
w e.
Reactor Enclosure Ventilation Exhaust Duct - Radiation - High S
Q R
1, 2, 3 f.
Deleted l
Er g.
Deleted 8
i l
h.
Drywell Pressure - High/
i 8
Reactor Pressure - Low S
Q R
1, 2, 3
<+
t i.
Primary Containment Instrument Gas to Drywell a Pressure - Low N.A.
N Q
1, 2, 3 L
4 g
j.
Manual Initiation N.A.
R N.A.
1, 2, 3
[
x TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUNENTATION SURVEILLANCE REQUIRENENTS h
CHANNEL OPERATIONAL g
CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH g
TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRE n
i 7.
SEC0f0ARY CONTAlletENT ISOLATION Reactor Veysel Water Level g
a.
Low, Low - Level 2 S
Q R
1, 2, 3 b.
Drywell Pressure ## - High S
Q R
1,' 2, 3 c.l.
Refueling Area Unit 1 Ventilation Exhaust Duct Radiation - High S
Q R
2.
Refueling Area Ur.it 2 Ventilation Exhaust Duct Radiation - High S
Q R
d.
Reactor Enclosure Ventilation Exhaust Duct Radiation - High S
Q R
1, 2, 3 w1 e.
Deleted m
f.
Deleted g.
Reactor Enclosure Manual Initiation N.A.
R N.A.
1, 2, 3 h.
Refueling Area g
Manual Initiation N.A.
R N.A.
n>5 g
- Required when (1) handling irradiated fuel in the refueling area secondary containment, or (2) during CORE ALTERATIONS, or (3) during operations with a potential for draining the reactor vessel with the vessel g
head removed and fuel in the vessel.
5
- When not administratively bypassed and/or when any turbine stop valve is open.
"m
- During operation of the associated Unit I or Unit 2 ventilation exhaust system.
ya ffThese trip functions (2a, 6b, and 7b) are common to the RPS actuation trip functibn.
I 1ARLE l l.J-1 (Continued)
PART A - PRIMARY CONTAlletENT ISOLATION VALVES INBOARD OUTBOARD ISOL.
g PENETRATION FUNCTION ISOLATION ISOLATION MAX. ISOL.
SIGIIAL(S), N01ES P&IO g IRNBER BARRIER BARRIER TINE. IF APP. IF APP.
g (SEC) (26)
(201 x
025 DRYWELL PURGE SUPPLY HV57-221(X-201A) 5**
B,H,5,W,R 3.11,14 57 g
HV57-223 5**
8,H.S.W,R 3,11,14 q
HV57-209 6**
8,H,5,W,R l{
(X-201A) m HV57-231 5**
8,H,S W,R 11,
(X-201A)
HV57-235 6**
8,H,S,W,R 11 1
HYDROGEN REC 0fBINER HV57-263 9
8,H,R,5 3.11,14 "B" INLET FV57-DO-2018 90 B,H,R,S 11,34 026 DRYWELL PURGE EXHAUST HV57-214 5**
8,H.S.W.R 3,11,14,33 57 HV57-211 15**
8,H,S.R 11 w7 SV57-239 5
10 HV57-215 6**
8,H,S,W,R 11,33
.4 HV57-217 5**
B,H,S,R 11 SV57-245 5
8,H,R,S 11 HYDROGEN RECONBINER HV57-261 9
B,H,R,5 3,11,14 "A" INLET FV57-DO-201A 90 8,H,R,5 11,34 h!
k 027A CONTAllelENT INSTRUMENT 59-2128(CK)
NA 59 SAS SUPPLY TO ADS VALVES HV59-251A 45 N
F H,M,&S
$ 028A-1 RECIRC LOOP SAMPLE HV43-2F019 10 8
43 y
HV43-2F020 10 8
028A-2 DRYWELL H2/02 SANPLE SV57-232 5
B,H,R,S 11 57 SV57-242 5
8,H,R,5 11 028A-3 DRYWELL H2/02 SAMPLE SV57-234 5
B.H,R,5 11 57 SV57-244 5
B,H,R,5 11
TABLE 3.6.3-1 (Contin w )
PART A - PRIMARY CONTAIISENT IMM ATION VALVES C
INBOARD OUTBOARD ISOL.
M PENETRATION FUNCTION ISOLATION ISOLATION NAX.ISOL.
SIGNAL (S),
NOTES P&ID NulWER BARRIER BARRIER TINE.IF APP.
IF APP.
n 13ECif26)
(20) e SV57-291 5
B H,R,5 11 g
(X-220A)
[
116 STANDBY LIQUID CONTROL 48-2F007(CK)
NA 48 (X-42)
HV48-2F0068 60 29 1178-1 DRYWELL RADIATION SV26-290A 5
B,H R S 11 26 NONITORING SUPPLY SV26-2908 5
B,H,R,5 11
{
1178-2 DRYWELL RADIATION SV26-290C 5
B,H,R,S 11 26 NONITORING RETURN SV26-2900 5
B,H,R S 11 201A SUPPRESSION POOL PURGE HV57-224 5**
B,H,S.W,R 3,11,14 57 SUPPLY HV57-231(X-25) 5**
B,H,S,W,R 3,11,14 w1 HV57-209(X-25) 6**
B,H,S,W R 11 "57-247 6**
B,H,S,W,R 11 A.,
W57-221(X-25) 5**
B,H,S W,R 11 HYDROGEN REC 0fBINER HV57-264 9
B,H,R.S d,11,14 "B" EXHAUST HV57-269 9
B,H,R,5 11 g
202 SUPPRESSION POOL PURGE HV57-204 5**
B,H,S,W,R 3,11,14.33 57 g
EXHAUST HV57-205 15**
B,H,S,R 11 g
HV57-212 6**
B,H,S,W R 11,33 g
HV57-218 5**
B,H,S,R 11
<+
SV57-285 5
B,H,R,5 11 HYDROGEN REC 0fBINER HV57-262 9
B,H,R.S 3,11,14 g
"A" EXHAUST HV57-266 9
B,H,R,5 11 2
203A(8,C,D) RHR PtNIP SUCTION HV51-2F004A 240 29,36 51 (B,C,D)
PSV51-2F0304 NA 36 (B,C D)
..-