ML20037D183
| ML20037D183 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/18/1981 |
| From: | Hukill H METROPOLITAN EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| IEB-79-01B, IEB-79-1B, L1L-161, NUDOCS 8105220177 | |
| Download: ML20037D183 (22) | |
Text
Metropolitan Edison Company Post Office Box 480 gj g
Middletown, Pennsylvania 17057 Writer's Direct Dial Number May 18,1981
[M'h'.3 LlL 161 t
(\\
)
Otfice of Nuclear Reactor Regulation Attn:
Mr. John F. Stolz, Chief
- Gh[g -
Q Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission 6
Washington, D.C.
20555
?
f V >..
3
\\
Dear Sir:
fs p
y, Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Equipment Qualification for Small Breaks This letter is in response to your letter dated May 1,1981 which requested information on environeental qualification for equipment needed to respond to design basis small break loss of coolant accidents (SB LOCA). Break sizes between 0.01 FT2 and 0.5 FT2 have been addressed considering a loss of offsite power, loss of Main Feedwater, and a worst case single failure. The sdverse environmental parameters associated with the worst case SB LOCA have also been addressed. The qualifications of the various equipment has been referenced from our response to IE Bulletin 79-OlB dated January 30, 1981 (LlL 026).
Sincerely,
/
. D.
dkill Director, TMI-l HDH:CWS:hh Attachment cc:
L. Barrett l
- 3. Silver i
R. Jacobs l
\\
8105220 lng
[
Metropohtan Edison Cornpany ts a Member of the General Pubhc Utsties System
Equipment Qualification for Small Break Loss of Coolant Accidents (SB LOCA)
The essential systems and components list consists of those Class IE electrical items, located in a SB LOCA harsh environment that are re. quired to bring the plant to a safe shutdown. The following systems, or portions thereof, from the response to IE Bulletin 79-01B are required:
Main Steam Makeup and Purification Decay Heat Removal Reactor Building Isolation Reactor Protection Engineered Safeguards Actuation Reactor Building Emergency Cooling Core Flood Nuclear Services Cloced Loop Cooling Additional Accident Monitoring Equipment The following systems from the response to IE Bulletin 79-01B are required but are not located in a SB LOCA harsh environment:
Emergency Feedwater Decay Heat Closed Loop Cooling I
f Reactor Building Emergency Cooling River Water The analysis has considered the worst single failure in P
addition to the loss of offsite power which results in a loss of Main Feedwater. The worst single failure is the loss of one i
emergency diesel generator. This results in only one reactor building fan coil unit being available for cooling.
l i
..,m.,7
__m.,
2.
The Component List Sheets are arranged by system. The equipment qualification is based upon our January 30, 1981 response to IE Bulletin 79-OlB. The attached table makes appropriate reference to the submission for each compenent. The building location is shown for each component including the common equipment. The only harsh environments resulting from the small break LOCA are those in the Reactor Building and the Auxiliary Building. The most severe small break LOCA harsh environment is shown for each component on the Component List Sheets.
For components located in the Auxiliary Building the only harsh-environment is radiation. The remarks column provides qualification information in addition to that previously submitted. Where there is no comment or reference in the remarks column, the SER of March 24, 1981 indicated no deficiency that would be applicable for those small break LOCA's.
The evaluation has considered break sizes in the range from 0.01 FT2 2
to 0.5 FT. The lower limit of 0.01 FT2 insures that emergency feedwater will be activated, since it is required for 2
breaks smaller than 0.02 FT. The most severe credible small break is that of the largest Reactor Coolant System branch line 2
with a cross-sectional area of less than 0.5 FT. The L eved 14 inch diameter core flood line which has a break area of 0.44 FT2 is the largest such line. This break results in a reactor building peak pressure of slightly below 30 PSIC. The Reator Building Spray System will not activate until 30 psig is reached so chemical spray on the equipment is not considered. The Reactor Building pressure 2
and temperature resulting from chis 0.44 FT break are assumed as an upper bound for qualifica:ica requirements for the equipment.
3.
The calculation of the accumulated radiation dose is based on the 2
degree of fuel failures predicted for a 0.44 FT break (i.e., no fuel failures beyond those, assumed in the FSAR for worst case normal operation is predicted to occur by licensing basis SB LOCA analyses).
A methodology similar to that of Appendix D to NUREG 0588 was then used to evaluate the equipment radiation exposure due to the small break fuel failures. The 40' year integrated dose was added to the 180 day post accident dose to obtain the total dose.
i i
l r
l l
i l
l t
- - -. - ~
.=
COMPONENT LIST NOTES i
y Note 1 - SUBMERGENCE
- Valve will perform its function of containment isolation prior to becoming submerged.
Note 2
.IADIATION DOR Guidelines Appendix C, Table C-1 were used in the evaluation J
DEGRADATION conducted. Other documentation was also reviewed where DOR Cuide-1 lines did not address specific materials or where more definitive j
data was available elsewhere. Review was based upon 80% retention of the appropriate property based upon the prudent engineering i
judgement of the materials function. The January 30, 1981 submittal j
contains supplemental pages to each Systems Component Evaluation Worksheet where a materials evaluation was done stating the materials, the documentation reference, and the radiation valve from that refer-
]
ence.
Note 3 - REFER TO LER 80 Qualification of motor brakes for certain Limitorque operators.
+
Note 4 - RELOCATION
-. Equipment was relocated to an elevation above the calculated Flood Level.
New transmitters LT-775, 776, 788 and LT-789 are being installed for control room and remote shutdown panel indication. These Rosemount j
1153D type transmitters are undergoing NUREG-0588 Cat. #1 qualification
]
program (NRC EQ Branch participation).
j Note 5 - MODEL PL-14B2
- Used on Rosemount narrow range RC pressure transmitters.
Note 6 - MODEL SA-1000
- New electrical seal assemblies are being installed on the other 79-01B I
listed transmitters, RTD(s), and pressure switches located inside con-0 tainment. Qualification to 75 PSIG, 340 F,100% humidity and 2 x 10 R per Conax Bulletin SA-1000/IPS-409/IPS-325.
4 Note 7 - RB ENVIRONMENT 30 PSIG/245 F/100% humidity /5.4 x 10 R.
_ The Foxboro transmitters used at TMI-1 are the 4-20 mA type and are i
POTENTIN. DEFICIENCIES not subject to the concern identified by NRC letter dated April 23, 1981 or IE Circular 81-06 for 10-50mA type transmitters.
i t
de i
f i
s l
e I '
a Y
u Q
7 1
fo
\\
1 e
8 g
s a
k e
P r
t a
o m
N e
R tne hm sn 7
ro e
iar n
e s
i l
t v
o n
N E
1 2
0 9
1 1
1 El t
t
& a e
e I t e
e t
h h
oi S
S s
T t m S
b S
S I
eu M
M e
L cs n
I I
T eB N
r1 E
e0 l
l N
f -
o o
O e9 V
V P
R7 S
S M
D D
O E
E C
no i
ta co B
B B
'B L
R R
R R
s s
s s
3 s
s s
n e
e e
e o
r r
r r
P P
P P
i t
e e
e e
p g
g g
g r 'r rr i
rr rr r
ae ae ae ae c
ht ht ht ht s
ct ct ct ct e
e si si si si D
im im i m i m D s D s Ds D s n
n n
n G a G a G a G a m
S r S r S r S r a
TT TT TT 6T e
t O
O O
~
S
)
n i
o a
N M
D 1
2 1
2 I
T T
T T
m P
P P
P A-e t
B B
t n
A s
a 6
6 6
6 y
l P
P P
P S
P S
S S
S
~
j
,]'
1 i :j ii Ifi A
4
Pegn 2 of 17 COMPONENT LIST System Make-up and Purification 3
p_. _.
_. ~. _ _ _ _ _. _...... _
Reference to I&E liarsh Plant ID No.
Description Location 79-01B Submittal Environment Remarks Qualified 4
MU-PIA Pump Motor AB EDS Vol. I MU Sheet 1 3 5 x 10 R Yes AB 2
i gPumpMotor MU-PIB
)
MU-PIC lPumpMotor AB 3
e 1
I
! Pump Motor (Aux. 011)
AB 4
MU-P2A l
lPumpMotor(Aux. Oil)
AB 5
MU-P2B i
MU-P2C Pump Motor (Aux. Oil)
AB 6
l
'MU-P3A Pump Motor (N in Oil)
AB 7
Pump Motor (Main Oil)
AB 8
MU-P3B MU-P3C Pump Motor (Main Oil)
AB 9
MU-P4A Pump Motor (Cear 011)
AB 10 i
c MU-P4B Pump Motor (Cear Oil)
AB 11 51U-P4C Pump Motor (Cear Oil)
AB 12
)
MU-V-2A Let down cooler outlet 13 Note 7 Note 1 Valve Motor Operator RB i
ML-V-2B Letdown cooler outlet RB 14 Note 7 Note 1 q
Valve llotor Operator 4
LSA/MUV-3 Letdown cooler outlet AB
'?
15 1 8 x 10 R Note 2 i
Valve Limit Switch g,
e o..-.
...-we_-
=e ir==.e owe 4
Prgy 3 of 17 __ _,
COMPONENT LIST
' System Make-up and Purification f-Reference to I&E liarsh Plsnt ID No.
Description Location 79-01B Submittal Environment Remarks 0ualified LSB/MUV-3 Letdown cooler outlet AB
'EDS Vol. I MU Sheet 16 1.8 x 10 R Note 2 Yes 4
Valve Limit Switch
'SV/MUV-3 Letdown cooler outlet AB 17 Note 2 Valve Solenoid Valve i
t L
~MU-V-12
- Pump Suction AB 18 1.8 x 10 R I 4
Valve Motor Operator 4
p-V-14A Pump Suction From BWST AB 19 1,8 x 10 R l
Valve Motor Operator i
4 MU-V14B Pump Suction From BWST AB 20 1.8 x 10 R Valve Motor Operator 4
l MU-V16A Pump discharge AB 21 1.8 x 10 R i
Valve Motor Operator i
p-V-16B Pump discharge AB 22 Valve Motor Operator MU-V-16C Pump discharge AB 23 Valve Motor Operator MU-V-16D Pump discharge AB 24 Valve Motor Operator SV/MUV -18 Charging line isolation AB 25 Note 2 valve-Solenoid Valve j
i 1
Prga 4 of 17_.-.--
COMPONENT LIST System Make-up and Purification l
Reference to I&E liarsh Plant ID Na.
Description Locat ion 79-01B Submittal Environment Remarks Qualified LSA/MUV-18 Charging Line Isolation AB
.EDS Vol. 1 MU Sheet 26 1 8 x 104R Note 2 Yes Valve - Limit Switch LSB/MUV-18 Charging Line Isolation AB 27 Valve - Limit Switch
[LSA/MUV-20
' Seal Isolation Valve AB 28 jLimit Switch i
,LSB/MUV-20 Seal Isolation Valve AB 29 Limit Switch i
I hV/MUV-20 Seal Isolation Valve AB 30 l
'MU-V-25 RCP Letdown Cooler Isola-RB 31 Note 7 tion Valve Motor Operator AB 32 3.5 x 1@ R Note 2 LSA/MUV-26 RCP letdown Cooler Isolation
, Valve - Limit Switch LSB/MUV-26 RCP Letdown Cooler Isola-.
AB 33 tion Valve - Limit Switch SV/MUV-26 RCP Letdown Cooler Isola-AB 34 tion Valve - Solenoid Valve MU-V-36 Recirculation Valve Motor AB 35 1.8 x 104 R Operator MU-V-37 Recirculation Valve Motor AB 36 Operator 4
P d
e i
f i
s l
e a
Y u
Q 7.
1 fo 5
sg P
s 2
k r
e t
am o
e N
R tj l
I t_
R n
4 e
0 hm 1
sn ro x
iar iv 5
l n
3 E
]
8 9
3 3
3 El t
& a e
I t e
t h
oi S
T t m S
b U
I eu M
L cS I
n T
eB N.
rl l
v eO o
i f -
V lo e9 P
R7 S
M D
O E
C n
o i
ta B
B B
c A
A A
o L
=
no n
i o
t i
h h
h a
t c
c c
c p
t t
t i
i f
r i
i i
w w
w i
c S
S S
r s
u e
P D
el el el ri ri ri d
uO uO uO n
s s
s a
se se se eb eb eb p
ru ru ru u
PL PL PL e
l i
k a
o M
N D
I m
A B
C e
t 0
0 0
t n
8 8
8 s
a 4
4 4
y l
S S
S S
P P
'PIi lI;l t
I' I6 l
(
l
,4 1.
i,
4 4
i j"
- 3 1
1
- I j.
1
Psgm 6 cf 1_7_ _._~
COMPONENT I.IST l
System Decay lleat Removal
_.. - l 4
Reference to I&E liarsh Plant ID No.
Description Location 79-01B Suhmittal Environment Remarks Qualified 4
Yes Dil-PIA Pump Motor AB
'EDS Vol. I DHR Sheet 1 1.8 x 10 R Dil-PIB Pump Motor AB 2
Dil-V-1 Drop line Valve Motor Oper.
RB 3
Note 7 DH-V-2
' Drop line Valve Motor Oper.
RB 4
l Dll-V-3
' Suction Valve Motor Oper.
AB 5
1 8 x 10 R 4
4 DH-V=4A Discharge Valve Motor Oper.
AB 6
1.8 x 10 R yes(Note 3) 4 bil-V-4B Discharge Valve Motor Oper.
AB 7
1.8 x 10 R 4
pil-V-5A
'BWST Suction Valve Motor AB 8 1.8x 10 R Operator 4
DH-V-5B
-BWST Suction Valve Motor AB 9 1.8x IO R
. Operator yes DH-V-6A RB Sump Pump Suction AB 10 1.8 x 10 R j
Valve Motor Operator DH-V-6B RB Sump Pump Suction AB 11 1.8 x 10 R
~
Valve Motor Operator 0
DH-V-7A
'MU System Discharge AB 12 1.8 x 10 R
~
Valve Motor Operator 4
~
3H-V-7B MU System Discharge AB 13 1.8 x 10 R Valve Motor Operator i
~
k.. -..
_ _. - ~...
Prgs 7 of 17__,.
COMPONENT LIST System Reactor Building Isolation j
Reference to I&E liarsh Plsnt ID No.
Description Location 79-OlB Submittal Environment Remarks Qualified 4
LSA/AHV-1A RB Purge Valve Limit Switch AB EDS Vol. I RBIS Sht.1 3.5 x 10 R Note 2 Yes LSB/AHV-1A RB PurgeValve Limit Switch AB 2
SV/AHV-1A1
j SV/AHV-1A2
' RB Purge Valve Solenoid AB 4
l
%-V-1 lPz Sample Valve Motor Oper.
RB 11 Note 7 4
'LSB /CAV-2 RCS Sample Valve Limit Valve AB 14 l
$V/CAV-2 RCS Sample W1ve Solenoid "
AB 12 CA-V-3 Pz Water Sample Valve RB 15 Motor Operator i
CA-V-4A SG FW Isolation Valve RB 16
. Motor Operator CA-V-4B SG FW 1 solation RB 17 Motor Operator CA-V-13 RCS Letdown Sample RB 24 Valve Motor Operator LSA/CAV-189 Demin. Water Isolation W1ve AB 25 1.8 x 16 R Note 2 j
, Limit Switch LSB/CAV-189 Demin. Water Isolation Valve AB 26 Limit Switch i
r
4 Pcg3 8 of 17 COMPONENT LIST
. System Reactor Building Isolation p _.__
Reference to I&E liarsh Plant ID No.
Description Location 79-01B Submittal Environment Remarks Oualified 4
4 l
SV/CAV-189 Demin. Water Isolation Valva AB
'EDS Vol. I RBIS Sht.27 1 8 x 10 R Note 2 Solenoid Valve i
5 All-V-1B RB Purge Valve Motor Oper.
RB Note 7 Note 3 j
t All-V-1C
.RB Purge Valve Motor Oper.
RB 6
JC-V-2 IC Closed Loop Isolation RB I:DS Vol. I RBIS Sht.40 Valve Motor Operator t
4 i
.!20/ ICV-3 IC Return Isolation AB 41 1 8 x 10 R Note 2 4
{
l Solenoid Valve 33/ ICV-3 IC Return, Isolation AB 42 Limit Switch f
LSB/ ICV-3 IC Return Isolation AB 43 Limit Switch a
WDG-V-3 RB Vent header Isolation RB 54 Note 7 Vc.1ve Motor Operator 4
j SV/WDG-V4 IB Vent header Isola. Valve AB 55 3.5 x 10 R Solenoid Valve ISA/WDG-V4 Ve t n
S itc 57 I
LSB/WDG-V4 RB Vent header Isola. Valve AB i
WDL-V-303
!RCS Drain tank Outlet Isola. RB 58 Note 7
- valve Motor Operator 4
LSA/WDL-V304 RCS Drain Isolation Valves AB 59 3,5 x 10 R Note 2 Limit Switch i
Pcga 9 of 17 COMPONENT 1.IST
,$E**
ReacLgr.Buildi_pg Isolatiott.__
Reference to I6E liarsh Plsnt ID No.
Description Location 79-01B Submittal Environment Remarks Qualif8ed 4
Yes LSB/WDL-V304 RC Drain Isolation Valve AB EDS Vol. 1 RBIS Sht. 60
- 3. 5 x 10 R Note 2 Limit Switch l
t SV/WDL-V304
'RC Drain Isolation Valve AB 61 Solenoid Valve l
l 4
.SV/WDL-V534
- RB Sump Outlet Isolation AB 64 1 8 x 10 R Solenoid Valve i
- LSA/WDL-V534 RB Sump Isolation AB 62 Limit Switch
' LSB/WDL-V534 RB Sump Isolation AB RDS Vol. I.RBIS Sht.63 Limit Switch LSAfWDL-V535 RB Sump Isolation AB 65 u
'LSB/WDL-V535 IRB Sump Isolation AB 66 n
' Limit Switch SV/WDLrV535 RB Sump Isolation AB 67 Solenoid Valve
/ /
Prgs 10 of 17 COMPONENT LIST iSystem Reactor Protection Reference to I&E l!arsh t
Plant ID No.
Description location 79-01B Submittal g ', nment Remarks Qualified
-=
Yes RC3A-PTl RC NR RB EDS Vol. lA RPS Sht.1 Note 7 Note 2 Pressure Transmitter RC3A-PT2 RC NR RB 2
Pressure Transmitter l
RC3B-PTl RC NR Pressure Transmitter RB 3
I kC3B-PT2 RC NR Pressure Transmitter RB 4
'EC4A-TE2 RC Outlet Temp RTD RB 5
RC4A-TE3 RC Outlet Temp RTD RB 6
i RC4B-TE2 RC Outlet Temp RTD RB 7
l l
RC4B-TE3
4 PS-672 RB Pressure Switch AB 13 3 5 x 10 R Note 2 PS-673 RB Pressure Switch AB 14 n
PS-674 RB Pressure Switch AB 15 u
l PS-675 RB Pressure Switch AB 16 l
Sh::t 11 of 17 COMPONENT 1.IST
[
, System Engineered Safeguards Actuation Reference to I&E liarsh
- Plant ID No.
Description Locati.qn 79-01B Suhmittal Environment Remarks Oualified
_.e__.
=
4 Yes PS-283 RB Pressure Switch AB EDS Vol. IA ESAS 2
- 3. 5 x 10 R Note 2 PS-284 lRB Pressure Switch AB 3
8 n
j PS-286
4 S-287 RB Pressure Switch AB 6
i n
'S-289 RB Pressure Switch AB 8
PS-290 RB Pressure Switch AB 9
i
~
hC3A-PT3 RC WR Pressure Transmitter RB 10 Note 7 C3A-PT4 RC WR Pressure Transmitter RB 11 RC3B-PT3 RC WR Pressure Transmitter RB 12 5
d PT-282 RB Pressure Transmitter AB 1
3.2 x 10 R
'PT-285 RB Pressure Transmitter AB 4
j PT-288 RB Pressure Transmitter AB 7
I e
e em
_i= =
s e.
e w 4
d e
i f
s i
e n
l Y
au Q
s 7
k 1
ra f
m o
e R
2 1
! i.
s t
g n
s P
e hm sn 7
ro ar e
i i
l t
v o
n N
E 1
2 3
El
& a I t t
- oi B
e T
t m R
S hi I
ei L
cS A
n I
T eB N
r1 l
E e0 o
N f -
O e9 V
P R7 S
M D
O E
C n
o i
t a
B B
B c
R R
R g
o n
L i
l_
o.
o _.
C _.
y__
cn_
r r
r e_
n o
o o
g.
o t
t t
r _.
o o
o i
~
e t
M M
M m
p E
i n
n n
r a
a a
F F
F g
c n
s i
e r
r r
d-D e
e e
l l
l l
i o
o o
u o
o o
B C
C C
r B
B B
o R
R R
t
- ,i l<
ii
!i i,
1 ca e
o R
N D
I m
A B
C e
t l
l I
t n
E E
E s
a y
l H
H H
S,_,
A
,A A
- i il l
i P
i
)4
,'jJ1i
.l:
4 l:
1 4
4 1<
)
i i.
Psga 13 of 17 COMPONENT LIST
! System Core Flood Reference to I6E liarsh Plant ID No.
Description Location 79-01B Submittal Environment Remarks Qualified CF-V-2A CF Sample Isolation RB
- EDS Vol, lA CF Sht.3 Note 7 Yes Valve Motor Operator
'CF-V- 2 B
iValve Motor Operator CF-V-3A CF Vent RB 5
j l
Valve Motor Operator g
l i
l Valve Motor Operator D A/CFV-19A CF Makeup Valve Limit Switch AB 7
3.5 x 1(/* R Note 2 LSB/CFV-19A CF Makeup' Valve LimitSwitch AB 8
LSA/CFV-19B CF Makeup Valve Limit Switch AB 9
LSB/CFV-19B CF Makeup Valve Limitswitch AB 10 e AB 11 20/CFV-19A CF Makeup Valve Solenoid W1v AB 12 20/CFV-19B CF Makeup Valve SolenoidValv e
4 a
LSA/CFV-20A CF Sample Isolation AB 13 Limit Switch 14 l
LSB/CFV-20A 1CF Sample Isolation AB
' Limit Switch 4
j
Pigs 14 of 17 QMPONENT LIST System Core Flood t'
Reference to I&E Ilarsh l
Plant ID No.
Description location 79-01B Submittal Environment Remarks Qualified SV/CF-V20A CF Sample Isolation AB
$DS Vol. IA CF Sht. 17 3.5 x 10 R Note 2 Solenoid Valve 15 LSA/CFV-20B CF Sample Isolation AB
) Limit Switch I
n l
16 LSB/CFV-20B CF Sample Isolation AB t
n hV/CF-V20B CF Sample Isolation AB 18 l
Solencid Valve i
I i
i I
Y e
e..e se ee em _
amuser es -- meea m.=.e
- E j
COMPONENT LIST System Nuclear Services Closed Loop Cooling Reference to I&E liarsh Plant ID No.
Description Location 79-01B Submittal Environment Remarks Qualified i;
4 NS-V-4 RCP Cooler Isolation AB
- 3. 5 x 1G R Yes Valve Motor Operator 5
)1S-V-32 Non-nuclear Equip. Cooler AB 6
o l
Isolation Valve Motor Oper, i
i NS-V-35 FCP Cooler' Isolation Valve RB.
7 Note 7 Materials list not fotor Operator yet received from Limitorque for i
evaluation for rad-intion affect's, how-l ever, raoiation dose for SB LOCA is not high enough to be of I
concern.
i f.
I
,i..
i
g.
Page 16 of 17 t
COMPONENT LIST System Additional Accident Monitoring Equipment
+
Reference to I6E liarsh i
Plsnt ID No.
Description Location 79-01B Submittal Environment Remarks Qualified
)
SPlA-LT2 OTSG Level 'Iransmitter RB
,EDS Vol, lA AAME/RCS Note 7 Note 4 Yes Sheet 1 4
n i
RB 2
SPlB-LT2 jOTSGLevelTransmitter RCl-LTl PE-Level Transmitter RB 5
i
',RCl-LT2 lPB Level Transmitter RB 6
[RCl-LT3 PZ Level Transmitter RB 7
8 lRCSA-TEl RC Inlet Temp. RTD RB i
l F
I
!RC5A-TE2 RC Inlet Temp. RTD RB 9
~
'RCSA-TE3 RC Inlet Temp. RTD RB 10 i
i
!RC5A-TE4 RC Inlet Temp. RTD RB 11 l
'RCSB-TEl RC Inlet Temp. RTD RB 12 RCSB-TE2 RC Inlet Temp. RTD-RB 13 3
?.C5B-TE3 RC Inlet Temp. RTD RB 14 4
RC5B-TE4 RC Inlet Ters. RTD RB 15 2
SPlA-LT4 OTSG Level Transmitter RB 3
Note 4' SPIB-bT4' OTSG Level Transmitter RB 4
n n
l i
i l
l
=
i i
1
Page 17 of 17 COMPONENT 1.IST Common Equipment
' System 1
l Reference to IEE liarsh Plant ID No.
Description I.ocation 79-OlB Submittnl Environment Remarks Qualified Heat Shrink Tubing RB EDL 7ol, lA Comm.
Note 7 Yes l
Sheet 1 Elec. Penetration Assy.
RB 3
i Instrument Cable RB/AB s'
4 Power & Control Cable RB/AB 5
i jConax i
Connectors RB 9
Note 5 and 6 l
2 3.5 x 104 Terminal Block AB R
Note 2 i
4 I
1 T
l j
4 3
e 4
me - ease en eed m e>
messame a w.-*
ogn.
ae em e = we e-
.. <.