ML19350F132
| ML19350F132 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 06/17/1981 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19350F131 | List: |
| References | |
| PROC-810617, NUDOCS 8106240251 | |
| Download: ML19350F132 (37) | |
Text
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G ATTACHMENT B lion Unit 1 Inservice Valve Test Program 8106 24 08f/
t
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y Systems MAIN STEAM ZION UNIT 1 Page 47 of 83 INSERVICE TEST PROGRAM Rev. O Drwg 8:
M-20 ASME CODE. CLASS 1e 2e AND 3 VALVES TEST V N CC DL Si VT A-E ST L-RR A U OL RO In
-A Y C
X TI E
E RM A
LQ V B ES WA Eh VE-U A
.OE K
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IT VALVE e
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T I
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FS REMARKS GO O
S.
(sec)
E T
N A
-B-C~
D _
E R
E HOV-MS0001 2
E-5 X
34 AGb hO Q/C 5
NO NOTE 1 HOV-MS0002 2
D-5 X
34
,AGb HO Q/c 5
NO
- NOTE l' i
HOV-MS0003 2
C-5 X
34 AGb HO Q/C 5
NO NOTE 1 HOV-MS0004 2
- A-5 X'
34 AGb HO Q/C 5
NO NOTE-1 MS0014 2
E-7 X
6 R
S I
NO' MS0015 2
E-7 X
6 R
S I
NO MS0016 2
E-6 X
6 R
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- NO MS0017 2
E-6 X
6 R
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NO
-MS0018 2'
E-6 X
6 R
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NO MS0019 2
D-7 X
6 R
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NO HS0020 2'
D-7 X
6 R
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NO MS0021 2
D-6 X
6 R
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NO HS0022 2
D-6 X
6 R
S I
NO MS0023 2
D-6 X
6 R
S I
NO MS0024 2
B-7 X
6 R
S
.I NO MS0025 2
B-7 X
6 R
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NO HS0026 2
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NO MS0027 2
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NO MS0029 2
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Syztem FEEDWATER ZION UNIT 1 Page 48 of 83 INSERVICE TEST PROGRAM Rev. O Drwg 9:
M-22 ASME CODE CLASS 1, 2, AND 3 VALVES TEST V N CC DL S1 VT A
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-(sec)
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B
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D-3 X
16 G
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B-3 X
16 G
MO C3 80 NO NOTE 3 MOV-W0019 2
A-3 X
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P-2 X
3 C
S Q
NO NOTE 4 FWOO67 2
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S Q
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C-2 X
3 C
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S Q
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3 E-10 X
4 C
S Q
NO NOTE 4 FW0032 3
E-9 X
4 C
S Q
NO NOTE 4 FWOO33 3
E-8 X
4 C
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E-10 X
6 Gb M
NO LOCKED OPEN FWOO35 3
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.4 Gb M
NO LOCKED CLOSED WOO 36 3
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4 Gb M
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M NO LOCKED CLOSED FW0038 3
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H NO LOCKED OPEN FWOO39 3
D-10 X
1 1/2 Gb M
NO LOCKED OPEN WOO 40 3
D-9 X
1 1/2 Gb M
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4-System: SERVICE WATER ZION UNIT 1 Page 50 of 83 INSERVICE TEST PROGRAM Rev. O i
Drwg 8:
M-32-2 ASME CODE CLASS 1, 2, AND 3 VALVES TEST V N CC DL Si VT A
E ST L
X TI E
E RM A
LQ V B ES WA Eh VE U
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T I
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FS REMARKS GO O
S (sec)
E T
N A
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R E
MOV-SW0001 3
D-6 X
20 G
MO O
100 NO MOV-SWOOO2 3
D-5 X
20 G
MO Q
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A-3 X
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B-4 X
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D-5 X
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. Systems S_ERVICE MATER ZION UNIT 1 Fage 51 of 83 E
INSERVICE TEST PROGRAM Rev. O Drwg 9:
M-34
. ASME CODE CLASS 1, 2, AND 3 VALVES lCC l
TET V N DL Si VT A
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NI CATEGORY a
T I
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E T
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B C
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R E
OAOV-SWOO20 3
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System: ISOLATION VALVE ZION UNIT l'
' Page. 52 of 83 '
-SEAL WATER INSERVICE TEST PROGRAM Rev. 0
+
Dewg la M-39 ASME CODE CLASS 1, 2, AND 3 VALVES TEST V N CC DL Si VT A
E ST L
.C X
TI E
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V B ES WA Eh VE U
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~
N A
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R E
LCV-IWOl NA C-1 X
1 G
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60 YES NOTE 27 j
LCV-IWO2 NA B-1 X
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1/2 G
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3/4 G
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1/2 G
AO Q
60 NO FCV-IW12 NA B-3 X
1/2 G
AO Q
60 NO j
FCV-IW13 NA B-3 X
1/2 G
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60-NO FCV-IW14 NA B-7 X
1/2 G
AO Q
60 NO FCV-IW15 NA B-7 X
3/4 G
AO Q
60 NO f
FCV-IW16 NA B-3 X
3/4 G
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60 NO 1
FCV-IW17 NA B-3 X
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3/8 C
S C
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3/8 C
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-~
i IWOO75 NA D-3 X
3/8 C
S C
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3/8 C
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IWOO77 NA D-3 X
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YES NOTE 10 IWOO78 NA D-3 X
3/8 C
S C
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IWOO79 NA D-3 X
3/8 C
S C
YES NOTE 10 IW0181 NA D-5 X
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IW0182 NA D-5 X
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-X 3/8 C
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YES NOTE 10 IW0184 NA D-6 3/8 C
S C
YES-NOTE 10 IWO185 NA D-6 X
3/8 C
S C
YES NOTE 10 IWO198 NA C-4 X
1/2 C
S C
YES NOTE 10 IWOO58 NA B-4 X
1/2 C
S C
YES NOTE 10'.
IWOO59
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B-4 X
1/2 C
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YES-NOTE 10:
4
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System: ISOLATION VALV.E ZION UNIT 1 Page 53 of 83 SEAL WATER INSERVICE TEST PROGRAM Rev. 0-
-Drwg la M.ASME CODE CLASS 1, 2, AND 3. VALVES TEST V
N-CC DL Si VT A
E ST L
X TI
E RM.
R OE K
IU E E
-S IT VALVE e
E A
C K
A EE R
NI CATEGORY s
T I
E G
FS REMARKS GO O
S (sec)
E T
N A
B C lD E
R E
IWOO60 NA B-4 X
1/2 C
S C
YES NOTE 10
.IWOO61 NA B-4 X
1/2 C
S C
YES NOTE 10 IWOO62 NA B-5 x
1/2 0
S C
YES NOTE 10 IWOO63 NA B-6 X
1/2 C
S
.C YES NOTE 10 IWOO64 NA B-5 X
1/2 C
S C
YES NOTE 10 IWOO65 NA B-5 X
1/2 C
S C
YES NOTE 10 IWOO66 NA B-6 X
1/2 C
S C
YES NOTE 10 IWOO67 NA C-3 X
1/2 C
S C
YES NOTE 10 IWOO68 NA C-3 X
1/2 C
S C
YES NOTE 10 IWOO69 NA C-3 X
1/2 C
S C
YES NUrE 10 1
IWOO70 NA C-4 X
1/2 C
S C
YES NOTE 10.
IWOO72 NA C-4 X
1/2 C
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YES NOTE 10 IWOO80 NA D-3 X
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.u Systete: Qt<TAllMEWF SPRAY ZION UNIT 1 Page'54 of 83 INSERVICE TEST PROGRAM Rev. O Dcwg 8:
M-44, ASME CODE CLASS 1, 2, AND 3 VALVES TEST V N CC DL Si VT A
E ST L
X TI E
E RM A
LQ V B ES WA Eh VE U
R OE K
IU E E S
IT VALVE e
E A
C K
A EE R
NI CAYEGORY a
T I
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PS REMARKS GO O
S (sec)
E T
N A
B C
D E
R E
MOV-CS0002 2
B-4 X
10 G
MO Q
50 R-YES NOTE 7 MOV-CS0003 2
C-3 X
10 G
MO Q
50 NO MOV-CS0004 2
D-4 X
10 G
MO Q
50 R-YES NOTE 7 MOV-CS0005 2
D-3 X
10 G
MO Q
50 NO MOV-CS0006 2
F-4 X
10 G
MO Q
50 R-YES NOTE 7 MOV-CS0007 2
P-3 X
10 G
MO Q
50 HO MOV-CS0008 3
C-4 X
3 G
MO Q
15 NO MOV-CS0009 3
E-4 X
3 G
MO Q
15 NO MOV-CS0010 3
F-4 X
3 G
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15 NO CS0002 2
B-8 X
14 G
M NO LOCKED OPEN CS0003 2
B-8 X
10 C
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NO NOTE 4 CS0004 2
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b Q
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D-8 X
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M NO LOCKED OPEN CS0009 2
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F-8 X
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M NO LOCKED OPEN CS0011 2
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CSOO1" 3
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M NO LOCKED OPEN CSO'20 3
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NO LOCKED OPEN CS00.f1 2
E-8 X
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YES NOTE 8 CS0022 2
E-8 X
3 G
M NO LOCKED OPEN
m System: COttrAtte(ENT SPRAY ZION UNIT 1 Page y of g INSERVICE TEST PROGRAM Rev. D_
Drwg 9:
M-44 ASME CODE CIASS 1, 2, AND 3 VALVES TEST V N CC DL Si VT A
E ST L
X TI E
E RH A
LQ V B ES WA Eh VE U
R OE K
IU E E S
IT VALVE e
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T I
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FS RDtARKS GO O
S (sec)
E T
N A
B C
D E
R E
CS0023 2
D-4 X
6 C
S Q
NO NOTE 4 CS0024 3
A-4 X
3 G
M NO LOCKED OPEN CS0025 3
F-5 x
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NO LOCKED OPEN CS0026 2
F-8 X
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H NO LOCKED OPEN CS0028 2
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1 Gb M
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l Gb M
NO I4CKED CLOSED CS0031 2
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NO LOCKED CLOSED CS0032 2
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NO LOCKED CLOSED CS0033 2
F-9 X
1 Gb M
NO LOCKED CLOSED CS0034 2
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1 Gb M
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B-4 X
X 6
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X 1
G M
R-YES I4CKED CLOSED NOTE 7 CS0045 2
E-4 X
X 1/2 Gb H
R-YES LOCKED CI4 SED, NOTE 7 CS0049 3
C-5 X
3 Gb M
NO LOCKED CLOSED CS0050 3
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NO LOCKED CLOSED CS0051 3
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NO I4CKED CLOSSD I
. V.
Systemt, - STEAM GEAERATOR BLOWDOWN ZION UNIT 1 Page'56 of 83 INSERVICE TEST PROGRAM Rev. O D rtrg 8 :
M-45-1 ASME CODE CLASS 1, 2,'AND 3 VALVES
~
.A E
ST L
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LQ V B ES WA Eh VE U
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IT VALVE e
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+
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T I
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FS REMARKS GO O
S (sec)
E T
j H
A B
C D
E R
E FCV-SS02 2
E-7 X
3/8 G
AO Q
60 NO FCV-SS03 2
D-7 X
3/8 G
AO Q
60 NO FCV-SSO4 2
B-7 X
3/8 G
AO Q
60 NO j
FCV-SS05 2
A-7 X
3/8 G
AO Q
60 NO FCV-SS17 2
B-6 X
2 1/2 G
AO Q
60 NO AOV-BD0001 2
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2 G
AO Q
60 NO AOV-BD0002 2
E-8 X
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AO Q
60 NO.
AOV-BD0003 2
D-8 X
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AO Q
60 NO l
AOV-BD0004 2
D-8 X
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AO Q
60 NO l
AOV-BD0005 2
C-8 X
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AO Q
60 NO AOV-BD0006 2
C-8 X
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AO Q
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System: VOLUME CONTROL IION UNIT 1 Page 59 of 83 INSERVICE TEST PROGRAM Rev. O Drwg 8:
M-54 ASME CODE CIASS.1, 2, AND 3 VALVES TEST V N CC DL Si VT A
E ST L
X TI E
E RM A
LQ V B ES WA Eh VE U
R OE K
IU E E S
IT VALVE e
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C-K A
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T I
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FS REMARKS GO O
S (sec)
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AOV-VC8152 2
A-6 X
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60 YES NCtFE 9 AOV-VC8153 2
A-6 X
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F-3 X
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M C1 YES NOTES 11 & 9 VC8369C 2
F-5 X
1 N
M C1 YES NOTES 11 & 9 VC8369D 2
F-7 X
1 N
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P-1 X
1 Gb M
C1 YES NOTES 11 & 9 VC8372B 2
F-3 X
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C1 YES NOTES 11 & 9 VC8372C 2
F-5 X
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j IystsO: VOLUME CONTROL ZION UNIT 1 Page 60 of 83 INSERVICE TEST PROGRAM Rev. 0 1rw9 la M-55 ASME CODE CLASS 1, 2, AND 3 VALVES 1
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MOV-LCV-VC112B 2
D-6 X
4 G
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D-6 X
4 G
MO Q
10 NO MOV-IEV-VCll2D 2
F-7 X
8 s
G MO Q
10 NO MOV-IfV-VCll2E 2
F-7 X
8 G
MO Q
10 NO MOV-V08100 2
C-2 X
4 DG MO C1 10 YES NOTES 9 & 29 MOV-VC8105 2
A-2 3
3 G
MO Q
10 YES NOTE 9 MOV-VC8106 2
A-2 X
3 G
MO Q
10 YES NOTE 9 MOV-VC8110 2
D-4 X
2 G
MO Q
10 NO MOV-VC8111 2
D-4 X
2 G
MO Q
10 NO VC8124 2
F-6 X
3/4 R
S I
NO VC8471A 2
F-6 X
6 G
M NO LOCKED OPEN VC8471B 2
G-6 X
6 G
H NO LOCKED OPEN VC8480A 2
D-1 X
2 Gu M
YES NOTES 9 & 12 VC84800 2
E-1 X
2 Gb M
YES NOTES 9 & 12 VC8481A 2
P-2 X
4 C
S Q/C2 YES NOTE 13 VC8481B 2 G-2 X
4 C
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F-6 X
8 C
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I Tystac: RESIDUAL llEAT REMOVAL ZION UNIT 1 Page 61 of 83 INSERVICE TEST PROGRAM Rev. 0 erwg la M-62 ASME CODE CLASS 1, 2, AND 3 VALVES TEST
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l MOV-RH8700A 2
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D-7 X
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B-9 X
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F-4 X
12 G
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A-8 X
3 R
S I
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3/4 R
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MOV-RH8716A 2
B-2 X
8 G
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10 NO MOV-RH8716B 2
C-2 X
8 G
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C-2 X
8 G
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B-5 X
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M RH8724B 2
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A-3 X
4 G
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B-3 X
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E-4 X
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/ztco: SAFETY INJECTION ZION UNIT 1 Page 66 of 83 INSERVICE TEST PROGRAM Rev. O j
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SAFET'.' INJECTION ZION UNIT 1 Page 67 of 83 l
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B-4 X
3/8 Gb AO Q
60 YES NOTE 9 SS9355B 2
B-4 X
3/8 Gb AO Q
60 YES NOTE 9 SS9356A 2
C-4 X
3/8 Gb AO Q
60 YES NOTE 9 SS9356B 2
C-4 X
3/8 Gb AO Q
60 YES NOTE 9 SS9357A 2
C-4 X
3/8 Gb AO Q
60 YES NOTE 9 SS9357B 2
C-4 X
3/8 Gb AO Q
60 YES NOFE 9 I
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I l
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System: HEATING SYSTEM IION UNIT 1 Page 75 of 83 INSERVICE TEST PROGRAM Rev. O i
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Systems. NASTE DRAIN IION UNIT 1 Page 76 of 83 INSERVICE TEST PROGRAM Rev. O Drwg 8:
M-87 ASME CODE CLASS 1,.2, AND 3 VALVES TEST V N CC D L~
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DT9160B I
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i NOTES 1)
Closure r:f the mainsteam isolation valves during unit operation would result in reactor trip and safety injection actuation. To avoid this transient, these valves will be partially stroked every three months. Full stroke testing will be done during cold shutdown.
2)
Full stroke exercising of this check valve will be demonstrated by establishing steam flow to the auxiliary feedwater pump turbine.
Acceptable pump operation will demonstrate acceptable check valve opening.
3)
Closure of the main feedwater isolation valves during unit operation would result in a reactor trip. These valves provide water as the normal heat removal for the steam generators. To avoid any transient, these valves will not be stroke tested during unit operation or I. '. shutdown conditions. These valves can only be tested at cold shutdown whenever the feedwater and condensate systems are not in operation.- In cold shutdown the steam generators are placed in the " wet layup" conditions with the secondary side essentially filled with feedwater. Stroke testing in this condition with the feedwater or condensate systems in operation would introduce an overfill of the steam generators f 8lling the main steam piping.
The potential of overpressurizing the secondary side of the steam generators would then exist. This testing perico will be each refueling outage as a maximum.
4)
Acceptable full stroke exercising of this check valve will be demonstrated by establishing proper pump discharge flow during ceriodic pumo testing.
5)
These check valves are passively open during normal operation and their required position to perform their safety function is to be open. The service water and component cooling system are continuously operated and monitored regarding their ability to provide adequate cooling. Upon system start up after a system shutdown the check valve is verified as opening by verification of proper system operation.
6)
Same as Note 5.
Additionally, the periodic test of the diesel generators demonstrates proper flow through these check valves by verification of proper engine fluids temperatures.
7)
These valves will be leak tested in accordance with 10CFR50, Appendix J.
1 Dage 78 of 83
8)
Check' valves'in the spray additive system cannot be exercised without introducing NaOH contaminants into the spray system. Operability of these three valves will be verified at a frequency of one valve each
. year. Operability will be verified by either' disassembly of the valve to check for free movement of the moving parts or by a special full flow flushing procedure.
9)
.These valves function as containment isolation valves. Relief is requested from performirq seat leakage testing required by IWV-3420.
As an alternative these valves are tested in accordance with 10 CFR 50 Appendix J as required by Tech. Spec. 4.10.
Additionally these L
valves are supplied by an Isolation Valve Seal Water System, which is functionally tested as part of this program and Tech. Spec. 4.9.1.
These alternative tests as described in Note 10, will adequately f
ensure that the erntainment isolation valves perform their intended function as described in the FSAR.
- 10) These IVSW check valves can only be tested by observing flow through downstream tell-tale drain or by disassembly of the valve to verify procer disk freedom of movement. This testing would render the system unable to perform its safety function. These valves will be tested at-a refueling outage frequency, as an alternative to t
containment isolation valve seat leakage testing.
- 11) Manually operated valves in the reactor coolant pump seal infection lines remain in a normal 11y open condition during unit operation.
Manually operated needle valves are adjusted to regulate seal injection flow to maintain correct pressure differentials at the pumn
~j seals. The seal injection system remains in operation following any postulated accident contributing to the safety injection to the reactor coolant system while maintaining and protecting the pump seals. Should it be required during a piotracted accident these
. valves may be closed and provided with isolation valve seal water.
These valves will be manually stroke tested each cold shutdown providing all reactor coolant pumos are not in operation. This testing period will be each refueling outage as a maximum.
Relief is taken from measuring stroke time on manual valves.
- 12) These manual valves are maintained passively closed during unit i
operation and are not required to function, other than provide containmet isolation, to safely shutdown the reactor or mitigate the consequences of an accident. Exception is taken to the performance of exercising tests as required by IWV-3410.
l L
i Page 79 of 83
.... - - -... =
- 13) Full stroke exercising of the' charging pump discharge check valves cannot be demonstrated during unit operation as the reactor coolant system pressure prevents the pumps from reaching full injection flow conditions. Partial stroke exercising of these check valves will ce demonstrated by establishing proper pump discharge flow during periodic pumo testing.
Full stroke exercising of this check valve will be demonstrated during cold shutdown providing the reactor vessel head is removed.
Performance of this test with the reactor coolant system intact could lead to an inadvertant overpressurization.of the system. The alternative rRethod of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge
' volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
- 14) Full stroke exercising of the charging pump suction check valve cannot b:: demonstrated during unit operation as the reactor coolant system pressure prevents the pumps from reaching full injection flow conditions. Partial stroke exercising of this check valve will be demonstrated by verifying charging flow is maintained when the charging pump suction path is transferred from the Volume Control Tank to the Refueling Water Storage Tank during the quarterly valve exercise test.
Full stroke exercising of this check valve will be demonstrated during cold shutdown providing the reactor vessel head is removed.
Performance of this test with the reactor coolant system intact could lead to an inadvertant overpressurization of the system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
l i
- 15) These check valves cannot be full stroke tested during unit operatton as the shut off head of the pumps are lower than reactor coolant l
system pressure.
Cartial stroke exercising of these check valves will be demonstrated f
by establishing proper pump discharge flow during periodic pump testing.
i Full stroke exercising of this check valve can only be demonstrated during cold shutdown providing the reactor vessel head is removed.
This condition is required to establish suction from the RWST and provide system flow conditions similar to design injection flow.
Performance of this testing with the reactor coolant system depressurized but intact would not provide adequate scrge volume for i
influx from the RWST to allow the RHR injection systec to reach these design flows. The alternative method of providing a surge volume by i
i partial draining of the reactor coolant system is not considered a safe practice due to concerns of maintaining adequate water level i
above the reactor core.
1 Page 80 of 83
-y
- 16) The3e Check valves Cannot be tested during unit operation as the shutoff head of the pumps are lower than reactor coolant system r ll' stroke testing of all the branch run check valves u
pressure.
will be demonstrated by total pump discharge flow during cold shutdown prGdding the reactor vessel head is removed. Performance of this test 5ith the reactor coolant system depressurized but intact could lead to an inadvertant overpressurization of the system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of aaintaining adequate water level above the reactor core.
- 17) These check valves cannot be tested during unit operar!on as the injection of cold, highly borated water would result..i e change in reactor core reactivity and undue thermal cycling o. the injection nozzles.
Full stroke exercising of all the branch run check valves will be demonstrated by total pump discharge flow during cold shutdown providing the reactor vessel head is removed. Performance of this test with the reactor coolant system intact could lead to an inadvertant overpressurization of the system. The alternative method l
of protecting against overpressurization by partial draining of the l
reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
18) these check valves cannot be full stroke tested during unit operation I
es the shut off head of the pumps are lower than reactor coolant system pressure.
Partial stroke exercising of these check valves will be demonstrated by establishing proper cump discharge flow during periodic pump i
testing.
I Full stroke exercising of this check valve will be demonstrated during cold shutdown providing the reactor vessel head is removed.
l Performance of this test with the reactor coolant system intact could lead to an inadvertant overpressurization of the system. The alternative method of protecting against overpressurization by i
partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
- 19) These check valves cannot be tested during unit operation as the shutoff head of the pumps are lower than reactor coolant system pressure.
I l
Page 81 of 83 l
3_
Full stroke exercising of all the branch run check valves can only be
~ demonstrated by total pump discharge during cold shutdown providing the reactor vessel head is removed. This condition is required to estaolish suction from the RWST and provide system flow conditions similar to design injection flow. Performance of this testing with the reactor conlant system depressurized but intact would not provide adequate surge volume for influx from the RWST to allow the RHR injection system to reach these design. flows. The alternative method of providing a surge volume by partial draining of the reactor coolant system is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
- 20) The accumulator check valves cannot be tested during unit operation due to the pressure differential between the accumulators (
600 psig) and the reactor coolant system (2235 psig). These valves cannot be full stroke tested except by a rapid depressurization of the reactor coolant system as would occur during the design basis cold leg double guillotine break. These valves will be partial stroke tested during cold shutdown.
- 21) Comoonent cooling water flow to the reactor coolant pumps is required at all times the pumps are in operation. Failure of one of these valves in a closed position during exercise test would result-in a loss of the cooling flow to the pumps. Exemption is taken to the quarterly exercise test. The valves will be exercise tested during cold shutdown providing all reactor coolant pumps are not in coeration. This testing period will be each refueling outage as a maximum.
- 22) This check valve is in the containment air particulate and gas monitor return line. The containment monitor is in continuous operation during unit operation and is also required for containment sampling in the event of an accident since it is passively open and required to stay open. The continued procer operation of the system serves to demonstrate proper check valve operation.
- 23) This manual valve is in the containment air particulate and gas monitor return line. Quarterly closing of this valve during operation would render the system unable to perform its sampling function. Full stroke testing will be performed during cold shutdown. Relief is taken from measuring stroke time on manual valves.
Page 82 of 83 f
v r
~
- 24) The recuirement for the containment air particulate and gas monitor return line isolation is one valve. The leak test can only be performed using both the check valve (PR0029) and the relief valve in
,eries as nne containment isolation boundary.
- 25) Closure of these valves during normal unit operation would result in a loss of letdown flow resulting in a reactor in a reactor coolant inventory transient and a subsequent reactor trip. These valves will be full stroke exercised during cold shutdown as reqired by ASkE Section XI, IW-3410(b) (1).
- 24) These valves *are located in a closed valve containment assembly which is designed as an extension of the containment boundary. These valves are inaccessable during plant operation. The valves can be made accessable during plant shutdown by disassembly of the valve containment assembly. This requires approximately 100 man-hours per valve in a radiation field uo to 50 mr per hour. Verification that the valve position, indication switches have changed in relation to valve position can be made by observing that no significant change in valve stroke time has occurred. Que to the burden in manpower and radiation exposure to perform the direct observation, relief is taken from the requirements of IW-3000.
- 27) These valves can only be full stroke tested by rendering their control systems inoperable. These valves will be full stroke tested during cold shutdown.
- 28) The RHR Suction valves from the reactor coolant system cannot be stroke tested during power operation. These valves are interlocked with reactor coolant system and are prohibited from opening above 425 osig. Opening these valves would cause a depressurization of the reactor coolant system and overpressurization of the RHR System.
These valves will be full stroke tested during cold shutdown.
- 29) This motor operated valve in the reactor coolant pump seal injection return line must remain in a normally open condition during unit coeration in order to maintain proper pump seal flow.
This valve will be stroke tested each cold shutdown providing all reactor coolant pumos are not in operation. This testing period will be each refueling cutage as a maximum.
Page 83 of 83
ATTACHMENT C lion Unit 2
[nservice Valve Test Program i
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System SERVICR MATER ZION UNIT 2 Page 50 of 83 INSERVICE TEST PROGRAM Rev. U Drwg la M-32-2.
ASME CODE CLASS 1, 2, AND 3 VALVES TEST V N CC DL Si VT A
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T I
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FS REMARKS I
S (sec)
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D-6 X
20 G
MO Q
100 NO, MOV-SWOOO2 3
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A-3 X
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A-3 X
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150 NO MOV-SWOOO9 3
B-3 X
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150 NO MOV-SWOO10 3
B-3 X
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System ISOLATION VALVE ZION UNIT 2 Page 52 of 83 SEAL WATER INSERVICE TEST PROGRAM Rev. O Drwg $3-M-512 ASME CODE CLASS 1, 2, AND 3 VALVES TEST j
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T I
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N A
B C
D E
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LCV-IWOL NA C-1 X
1 G
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60 YES NOTE 27 YES NOTE 27 LCV-IWO2 NA B-1 X
1 G
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60 NO FCV-IW10 NA B-6 X
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' System: ISOLATION VALVE ZION UNIT 2 Page. 53 of 83 SEAL WATER INSERVICE TEST PROGRAM Rev. O Drwg 4: M-512 ASME CODE CLASS 1, 2, AND 3 VALVES TEST V N CC DL Si VT A
E ST L
RR A'
X T1 E
E RM A
LQ V B ES WA Bh VE U
R OE K
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E A
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T I
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FS REMARKS GO O
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E T
H A
B C
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IWOO60 NA B-4 X
1/2 C
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YES NOTE 10 3
IWOO61 NA B-4 X
1/2 C
S C
YES NOTE 10 IWOO62 NA B-5 X
1/2 C
S C
YES NOTE 10 IWOO63 NA B-6 X
1/2 C
S C
YES NOTE 10 IWOO64 NA B-5 X
1/2 C
S C
YES NOTE 10 IWOO65 NA B-5 X
1/2 C
S C
YES NOTE 10 IW0066 NA B-6 X
1/2 C
S C
YES NOTE 10 IWOO67 NA C-3 X
1/2 C
S C
YES NOTE 10 IWOO68 NA C-3 X
1/2 C
S C
YES NOTE 10 IWOO69 NA C-3 X
1/2 C
S C
YES NOTE 10 IWOO70 NA C-4 X
1/2 C
S C
YES NOTE 10 IWOO72 NA C-4 X
1/2 C
S C
YES NOTE 10 IWOO80 NA D-3 X
1/2 C
S C
YES NOTE 10 IW0081 NA E-5 X
1/2 C
S C
YES NOTE 10 IWOO82 NA D-6 X
1/2 C
S C
.YES NOTE 10 IW0083 NA D-6 X
1/2 C
S C
YES NOTE 10 IWOO84 NA D-4 X
1/2 C
S C
YES NOTE 10 IW0160 NA B-2 X
1 R
S C
YES NOTE 10 IW0162 NA C-1 X
3/4 C
S C
YES NOTE 10 IWOO90 NA F-3 X
1/2 C
S C
YES NOTE 10 l
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1/2 C
S C
YES NOTE 10 IWOl86 NA E-4 X
3/8 C
S C
YES NOTE 10 1
4 T
4 1
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Systems COKFAlle4Elfr SPRAY ZION UNIT 2 Page 54 of 83 INSERVICE TEST PROGRAM Rev. O Drwg la M-514 ASME CODE CLASS 1, 2, AND 3 VALVES
~
E ST L
X TI E
E RM A
LQ V B ES MA Eh VE U
R OE K
IU E E S
IT VALVE e
E A
C K
A EE R
NI CATEGORY a
T I
E G
FS REMARKS GO O
S (sec)
E T
N A
B C
D E
R E
MOV-CS0002 2
B-4 X
10 G
MO Q
50 R-YES NOTE 7 NO MOV-CS0003 2
C-3 X
10 G
MO Q
50 MOV-CS0004 2
D-4 X
10 G
MO Q
50 R-YES-NOTE 7 NO MOV-CS0005 2
D-3 X
10 G
MO Q
50 MOV-CS0006 2
F-4 X
10 G
MO Q
SO R-YES NOTE 7 NO MOV-CS0007 2
F-3 X
10 G
MO Q
50 MOV-CS0008 3
C-4 X
3 G
MO Q
15 NO MOV-CS0009 3
E-4 X
3 G
MO Q
15 NO 1
MOV-CS0010 3
F-4 X
3 G
MO Q
15 NO NO IDCKED OPEN CS0002 2
B-8 X
14 G
h CS0003 2
B-8 X
10 C
S IQ NO NOTE 4
- NO LOCKED OPEN CS0004 2
B-8 X
10 G
M NO NOTE 4 CS0005 2
B-4 X
10 C
S Q
NO LOCKED OPEN CS0006 2
D-8 X
14 G
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D-8 X
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S Q.
HO LOCKED OPEN I
CS0008 2
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10 G
M NO NOTE 4
{
CS0009 2
D-5 X
10 C
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14 G
H NO LOCKED OPEN NO NOTE 4 CS00ll 2
F-8 X
10 C
S Q
NO LOCKED OPEN CS0012 2
F-8 X
10 G
M NO NOTE 4 CS0013 2
D-4 X
10 C
S Q
NO IDCKED OPEN-CS0014 3
A-4 X
3 G
M NO LOCKED OPEN CS0015 3
D-5 X
3 Gb M
YES NOTE 8 CS0016 2
C-8 X
3 C
S T
NO LOCKED OPEN Cb0017 2
C-8 X
3 G
M NO NOTE 4 CS0018 2
C-9 X
6 C
S Q
NO LOCKED OPEN CS0019 3
A-4 X
3 G
M NO IDCKED OPEN l
CS0020 3
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3 Gb M
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V Sy: tem: CONTAItMENT SPRAY ZION UNIT 2 Page 55 of 83 INSERVICE TEST PROGRAM Rev. O Drwg la M-514 ASME CODE CLASS 1, 2, AND 3 VALVES l
TET Si VT A
E ST L
X TI E
E RH A
LQ V B ES WA Eh VE U
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IU E E S
IT VALVE e
E A
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T I
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S (sec)
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GO
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A NO NOTE 4 CS0023 2
D-4 X
6 C
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A-4 X
3 G
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CS0026 2
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M CS0028 2
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C-9 X
1 Gb M
CS0030 2
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1 Gb M
NO IDCKED CLOSED CS0031 2
E-9 X
1 Gb M
NO LOCKED CIDSED CS0032 2
E-9 X
1 Gb M
NO IDCKED CLOSED CS0033 2
F-9 X
1 Gb M
NO LOCKED CLOSED CS0034 2
F-9 X
1 Gb M
NO LOCKED CLOSED CS0037 2
B-4 X
X 6
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C-4 X
X 6
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CS0041 2
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/Otc3 VOLUME CONTROL ZION UNIT 2 Page 60 of 83 I
INSERVICE TEST PROGRAM Rev. O rwg is M-518 ASME CODE CLASS 1, 2, AND 3 VALVES TEST l
E ST L
X TI E
E RM A
LQ 7 V D ES WA Eh VE l U
R OE K
IU E E S
IT VALVE e
E l
A C
K A
EE R
NI CATEGORY s
i T
I E
G FS REMARKS l
GO O
S (sec)
E T
N A
B C
D E
R E
iOV-LCV-VCll2B 2
D-6 X
4 G
MO Q
10 NO lOV-LCV-VC112C 2
D-6 X
4 G
MO Q
10 NO (OV-LCV-VCll2D 2
F-7 X
8 G
MO Q
10 NO s
'3V-LCV-VC112E 2
F-7 X
8 G
MO Q
10 NO MOV-VC8100 2
C-2 X
4 DG MO C1 10 YES NOTES 9 & 29 MOV-VC8105 2
A-2 X
3 G
MO Q
10 YES NOTE 9 MOV-VC8106 2
A -2 x
3 G
MO Q
10 YES NOTE 9 MOV-VC8110 2
D4 X
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10 NO MOV-VC8111 2
D-4 X
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3/4 R
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6 G
M NO LOCKED OPEN VC8471B 2
G-6 X
6 G
H NO LOCKED OPEN VC8480A 2 D-1 X
2 Gb M
YES NOTES 9 & 12 VC8480B 2 E-1 X
2 Gb M
YES NOTES 9 & 12 VC8481A 2 P-2 X
4 C
S Q/C2 YES NOTE 13 g
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IyatGO: RESIDUAL HEAT REMOVAL ZION UNIT 2 Page 61 of 83 INSERVICE TEST PROGRAM Rev. O srwg 0 M-520 ASME CODE CLASS 1, 2, AND 3 VALVES
~
TEST i
Si VT l A
l E
V N CC DL I
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TI E
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NI CATEXIORY s
T I
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FS RD4ALJCS GO O
S (sec)
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N Al B C1 Di E R-E MOV-RH8700A 2
B-7 X
14 G
MO Q
120 NO MOV-RH87008 2
D-7 X
14 G
MO' Q
120 NO MOV-R118701 1
B-9 X
14
,G MO C
120 NO NOTE 28 HO NOTE 28 h0V-RI9702 1
B-10 X
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MO C
120 MOV-RH3703 2
F-4 X
12 G
MO Q'
120 NO NO Rii8708 2
A-8 X
3 R
S I
R!i8709 2
F-3 X
3/4 R
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NO MOV-RII6716A 2
B-2 X
8 G
MO Q
10 NO MOV-Rl!8716B 2
C-2 X
8 G
MO Q
10 NO MOV-R118716C 2
C-2 X
8 G
MO Q
10 NO R118724A 2
B-5 X
10 G
H NO LOCKED OPEN RH8724B 2
D-5 X
10 G
M HO LOCKED OPEN RH8728A 2
B-6 X
10 G
M NO LOCKED OPEN lM Rii8728B 2
D-6 X
10 G
NO LOCKED OPEN R118730A 2
B-6 X
10 C
M Q/C2 YES NOTE 15 RH8730B 2
D-6 X
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NOTE 19 RiiS9498 1
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12 G
MO Q
15 NO MOV-SI8804A 2
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8 G
MO Q
10 NO MOV-CS0049 2
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Systems. SAFETY IlOBCTION ZION UNIT 2 Page 63 of 33 INSERVICE TEST PROGRAM Rev. O Drwg is M-521 ASME CODE CLASS 1, 2,- AND 3 VALVES TEST V N CC DL Si VT A
.E ST
X TI E
E RM A
LQ
.V B
ES WA Eh VE U
R' OE K
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-E S
IT VALVE e
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NI CATEGORY s
T I
E G
F-S RD4 ARKS GO O
S (sec)
E T
N A
B C
D E
R E
SI8900A 1
A-1 X
1 1/2 C
S C2 YES NOTES 17 YES NOTES 17 SI8900B 1
B-1 X
1 1/2 C
S C2 SI8900C 1
B-1 X
1 1/2 C
S C2 YES NOTES 17 SI89000 1
C-1 X
1 1/2 C
S C2 YES NOTES 17 MOV-SI880CA 2
A-2 X
1 1/2 G3 MO Q
10 -
NO MOV-SI88008 2
B-2 X
1 1/2 Gb MO Q
10 NO MOV-sis 000C 2
B-2 X
1 1/2 Gb MO Q
10 NO MOV-SI8800D 2
C-2 X
1 1/2 Gb MO Q
10 NO MOV-SI8801A 2
A-3 X
4 G
MO Q
10 NO MOV-SI8801B 2
B-3 X
4 G
MO Q
10 NO MOV-SI8802 2
E-4 X
4 G
MO Q
10 NO MOV-SI8803A 2
C-6 X
4 G
MO Q
10 NO MOV-SI8803B 2
C-6 x
4 G
MO Q
10 NO MOV-SI8804B 2
F-7 X
8 G
MO Q
10 NO MOV-SI8806 2
E-8 X
8 G
MO Q
10 NO MOV-SIB 807A 2
E-7 X
4 G
MO Q
10 NO MOV-SI8807B 2
D-7 X
4 G
MO Q
10 NO RI8810A 2
A-2 X
1 1/2 Gb M
NO LOCKED THROTTLED SI8810B 2
B-2 X
1 1/2 Gb H
NO LOCKED THROTTLED SI8810C 2
B-2 X
1 1/2 Gb M
NO LOCKED THROITLED s
SI8810D 2
C-2 X
1 1/2 Gb M
NO
' LOCKED THROTTLED MOV-SI8813 2
B-9 X
2 Gb MO Q
10 NO MOV-SI8814 2
C-9 X
2 Gb
,MO Q
10 NO SI8852 2
A-4 X
3/4 R
S I
NO SI8853 2
E-5 X
3/4 R
S I
NO SI8858 2
D-7 X
3/4 R
S I
NO SI8870A 2
A-5 X
1 Gb AO Q
10 NO SI8870B 2
A-5 X
1 Gb AO Q
10 NO SIB 883 2
B-5 X
1 Gb AO Q
10 NO SI8905A 1
E-3 X
4 C
S C2 YES NOIE 16
Systems SAFErY INJECTION ZION UNIT 1 Page 64-of 8 3 INSERVICE TEST PROGRAM Rev. O Dreg 4:
M-64 ASME COCE CLASS 1, 2, AND 3 VALVES TEST V N CC DL Si VT A'
E ST L
X TI E
E RH A
LQ V B ES WA Eh VE U
R'
.O E K
'I U E E S
IT VALVE e
E A
C K
A EE R
NI CATEGORY s
T I
E G
FS REMARKS GO O
S (sec)
E T
N A
B C
D E
R E
YES NOTES 16 SI89058 1
D-3 X
4 C
S C2 NO NOTES' 4 SIB 919A 2
E-5 X
3/4 C
S Q
NO NOTES 4 SI8919B 2
F-5 x
3/4 C
S Q
NO LOCKED OPEN-8 SI8920A 2
E-5 X
3/4 Gb M
NO LOCKED OPEN SI8920B 2
F-5 x
3/4 Gb M
SI8921A 2
E-5 X
4 G
M NO LOCKED OPEN NO LOCKED OPEN SI8921B 2
F-5 X
4 G
M SI8922A 2
E-S X
4 C
S C2 YES NOTE 16 YES NOTE 16 SI8922B 2
F-5 X
6 C
S C2 MOV-SIB 923A 2
E-1 X
6 G
MO Q
10 NO MOV-SI8923B 2
E-7 X
1 G
MO Q
10 NO SI8925 2
B-6 X
8 Gb M
NO LOCKED CLOSED YES NOTE 18 SI8926 2
E-7 X
8 C
S Q/C2 SI8943C 1
F-2 X
8 C
S C2 YES NOTE 16 YES NOTE 16 SIPS 49D 1
F-2 X
2 C
S C2 YES NOTE 16 SI9P94C 1
F-3 X
2 C
S C2 YES NOTE 16 SI90u4D 1
F-3 X
4 C
S C2 MC"-JI9010A 2
E-4 X
4 G
MO Q
10 NO NO MOV-SI9010B 2
E-4 X
4 G
MO Q
10 MOV-SI90llA 2
E-4 X
4 G
MO Q
10 NO NO MOV-SI 90 llB 2
F-4 X
2 G
MO Q
10 YES NOTE 16 SI9012A 1
F-1 X
2 C
S C2 YES NOTE 16 SI9012B 1
F-1 X
2 C
S C2 SI9012C l
E-1 X
2 C
S C2 YES NOTE 16
'YES NOTE 16 SI9012D 1
E-1 X
2 C
S C2 SI9013A 2
F-2 X
2 Gb M
NO 7,0CKED THROTTLED NO-LOCKED THROTTLED SI9013B 2
F-2 X
2 Gb M
SI9013C 2
E-2 X
2 Gb M
NO L YKED THROTTLED NO LOCKED THROTTLED SI9013D 2
E-2 X
2 Gb M
l
Systems SAFETY INJECTION ZION UNIT 2 Page 65 of 83 INSERVICE TEST PROGRAM Rev. O Drwg 8: M-521 ASME CODE CLASS 1, 2, AND 3 VALVES TEST V N CC DL Si VT A
E ST L
X TI E
E RM A
LQ V B ES WA Eh VE U
R OE K
IU E E S
IT VALVE e
E A
C K
A EE R
HI CATEGORY s
T I
E G'
FS REMARKS GO O
S (sec)
E T
N A
B C
D E
R E
SI9003A 2
D-3 X
2 Gb M
NO LOCKED OPEN NO LOCKED OPEN SI9003B 2
E-3 X
2 Gb M
NO LOCKED OPEN SI9003C 2
F-3 X
2 Gb M
SI9003D 2
P-3 X
2 Gb M
NO IDCKED OPEN SI9030 2
E-4 X
3/4 R
S I
NO SI9031 2
F-4 X
3/4 R
S I
NO SI9032 2
B-2 X
3 C
S C2 YES NOTE 17 I
Q6 jb
-s t
Jite:n: SAFETY INJECTION ZION UNIT 2 Page 66 of 8'10
h s
INSERVICE TEST PROGRAM Rev. O.
..j ;
49 8:- M-522.
ASME CODE CLASS I, 2,.AND 3 VALVES TEST
-V N
E ST L
-X-
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LQ L M DA AC V B ES WA En VE U
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. REMARKS.
GO O
S (su c)
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N
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[X 10 G-MO Q
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W-S I880 8B 2
3-6 X !
10 G
MO Q
12 NO
)V-SI88080 2
B-7 i
v.
i 10 G
_MO Q
12 NO W-SI8 80 8D 2
B-4 X
10 G
MO Q
12 NO
- )V-S I 6 80 9 A 2
D-3 X
10 G
MO Q
12.
NO 10 G
MO Q
12 NO U-SI8809B 2
E-3 X
j 18 G
MO Q
22 YES NOTE 26 N-SOS 811A 2
P-3
, X j-
>V-SIB 811B 2
F-3 IX 6
18 G
MO Q
22 YES NOTE 26 N-SIS 912A 2*
D-8 X
12' G
MO Q
15 NO NO IV-SI8812B 2
D-9 x
12 G
MO Q
15 NO SI8855A 2
A-3 X
1 R
S I
SI8855B 2
A-6 X
1 R
S I
NO SI8855C 2
A-8 X
1 R
S I
NO NO SI8855D 2
A-5 X
1 R
S I
NO SI8856A 2
D-3 X
2 R
S I
NO SI8856B 2
D-3 X
2 R
S I
SI8830 2
A-9 x
1 Gb AO Q
60 NO SIS 948A 1
C-2 X
10 C
S C2 YES-NOTE 20 qSI~ AdB 1
C-2 X
1G C
S C2 YES NOTE 20 YES NOTE 20 Q SI8948C 1
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ZION UNIT 2 Page 68'of'S3-INSERVICB TEST PROGRAM Rev, O Drwg 9:
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9 System SERVICE AIR ZION UNIT 2 Page 72 of 83 INSERVICE TEST PROGRAM Rev. 0
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.c Systems WASTE DRAIN ZION UNIT 2 Page'76 of 83.
INSERVICE TEST PROGRAM Rev. O Drwg 9:
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NOTES 1)
Closure of the mainsteam isolation valves during unit operation would result in reactor trip and safety injection actuation. To avoid this transient, these valves will be partially stroked every three months. Full stroke testing will be done during cold shutdown.
- 2) - r ll stroke exercising of this check valve will be demonstrated by.
u establishing steam flow to the auxiliary feedwater pump turbine.
Acceptable pump operation will demonstrate acceptable check valve opaning.
3)
Closure of the main feedwater isolation valves during unit operation would result in a reactor trip. These valves provide water as the normal heat removal for the steam generators. To avoid any transient, these valves will not be st;oke tested during unit noeration or hot shutdown conditions. These valves can only be tested at cold shutdown whenever the feedwater and condensate systems are not in operation. In cold shutdown the steam generators are
.placed in the " wet layuc" conditions with the secondary side essentially filled with feedwater. Stroke testing in this condition with the feedwater or condensate systems in operation would introduce an overfill of the steam generators filling the main steam piping.
The potential of overpressurizing the secondary side of the steam generators would then exist. This testing period will be each refueling outage as a maximum.
4)
Acceptable full stroke exercising of this. check valve will be demonstrated by establishing proper pump discharge flow during periodic pump testing.
5)
These check valves are passively open during normal operation and their required position to perform their safety function is to be open.
The service water and component cooling system are continuously operated and monitored regarding their ability to provide adequate cooling. Upon system start up after a system shutdown the check valve is verified as opening by verification of procer system operation.
6)
Same as Note 5.
Additionally, the periodic test of the diesel generators demonstrates proper flow through these check valves by verification of proper engine fluids temperatures.
7)
These valves will be leak tested in accordance with 10CFR50, Appendix J.
j Page 78 of 83
8)
Check valves in the spray additive system cannot be exercised without introducing NaOH contaminants into the spray system. Operability of these three valves will be verified at a frequency of one valve each year. Operability will be verified by either disassembly of the valve to check for free movement of the moving parts or by a special full flow flushing procedure.
9)
These valves function as containment-isolation valves. Relief is requested from performino seat leakage testing required by IWV-3420.
As an alternative these valves are tested in accordance with 10 CFR 50 Appendix J as required oy Tech. Spec. 4.1'J.
Additionally these valves are supplied by an Isolation valve Seal Water System, which is functionally tested as part of this program and Tech. Spec. 4.9.1.
These alternative tests as described in Note 10, will adequately ensure that the containment isolation valves perform their intended function as described in the FSAR.
- 10) These IVSW check valves can only be tested by observing flow through downstream tell-tale drain or by disassembly of the valve to verify proper disk freedom of movement. This testing would render the system unable to perform its safety function. These valves will be tested at a refueling outage freauency, as an alternative to containment isolation valve seat leakage testing.
- 11) Manually operated valves in the reactor coolant pump seal infection lines remain in a normallly open condition during unit operation.
Manually operated needle valves are adjusted to regulate seal injection flow to maintain correct pressure differentials at the pump seals. The seal injection system remains in operation following any postulated accident contributing to the safety injection to the reactor coolant system while maintaining and protecting the pump seals. Should it be required during a protracted accident these calves may be closed and provided with isolation valve seal water.
These valves will be manually stroke tested each cold shutdown providing all reactor coolant pumps are not in operation. This testing period will be each refueling outage as a maximum.
Relief is taken from measuring stroke time on manual valves.
- 12) These manual valves are maintained passively closed during unit operation and are not required to function, other than provide containmet isolation, to safely shutdown the reactor or mitigate the consequences of an accident. Exception is taken to the performance of exercising tests as required by IWV-3410.
Page 79 of 83
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- 13) Full ' stroke exercising of the' charging pump discharge check valves cannot be demonstrated during' unit operation as the reactor coolent system pressure prevents the pumps from reaching full injection flow conditions. Partial stroke exercising of these check valves will be demonstrated by establishing proper pump discharge flow during periodic pump testing.
Full stroke exercising of this check valve will be demonstrated during cold shutdown providing the reactor vessel head is removed.
Performance of this test with the reactor coolant syste.m intact could lead to an inadvertant overpressurization Of the system. The alternative dethod of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
- 14) Full stroke exercising of the charging pomo suction check valve cannot be demonstrated during unit operation as the reactor coolant system pressure prevents the pumps from reaching full injection flow conditions. Partial stroke exercising of this check valve will be demonstrated by verifying charging flow is maintained when the charging pump suction path is transferred from the Volume Control Tank to the Refueling Water Storage Tank during the quarterly valve exercise test.
Full stroke exercising of this check valve will be demonstrated during cold shutdown providing the reactor vessel head is removed.
Performance of this test with the reactor coolant system intact could lead to an inadvertar.t overpressurization of the system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
1
- 15) These check valves cannot be full stroke tested during unit operation as the shut off head of the pumps are lower than reactor coolant system pressure.
partial stroke exercisirq of'these check valves will be demonstrated by establishing proper pump discharge flow during periodic pump testing.
Full ?troke exercising of this check valve can only be demonstrated during cold shutdown providing the reactor vessel head is removed.
This condition is required to establish suction from the RWST and provide system flow conditions similar to design injection flow.
Performance of this testing with the reactor coolant system depressurized but intact would not provide adequate surge volume for influx from the RWST to allow the RHR injection system to reach these design flows. The alternative method of providing a surge volume by partial draining of the reactor coolant system is not considered a safe practice due to concerns of maintaining adequate water level above the reactor-core.
i Page 80 of 83
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- 16) These check valves cannot be tested during unit operation as the shutoff head of the pumps are lower than reactor coolant system pressure. Full stroke testing of all the branch run check valves will be demonstrated by total pump discharge flow during cold shutdown oroviding the reactor vessel head is removed. Performance of this test with the reactor coolant system depressurized but intact could lead to an inadvertant overpressurization of the system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor care.
- 17) These check valves cannot be tested during unit operation as the injection of cold, highly borated water would result in a change in reactor core reactivity and undue thermal cycling of the injection nozzles.
Full stroke exercising of all the branch run check valves will be demonstrated by total pump discharge flow during cold shutdown providing the reactor vessel head is removed. Performance of this test with the reactor coolant system intact could lead to an inadvertant overpressurization of the system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe oractice due to concerns of maintaining adequate water level above the reactor core.
- 18) These check valves cannot be full stroke tested during unit operation as the shut off head of the pumps are lower than reactor coolant system pressure.
Partial stroke exercising of these check valves will be demonstrated by establishing proCer pump discharge flow during periodic pump testing.
Tull stroke exercising of this check valve will be demonstrated during cold shutdown providing the reactor vessel head is removed.
Performance of this test with the reactor coolant system intact could lead to an inadvertant overpressurization of the system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adecuate water level ahove the reactor core.
- 19) These check valves cannot be tested during unit operation as the shutoff head of the pumps are lower than reactor coolant system pressure.
Page 81 of 83
Full stroke exercising of all the branch run check valves can only be demonstrated by total pump discharge during cold shutdown providing
- the' reactor vessel head is removed. This condition is required to establish suction from the RWST and provide system flow conditions similar to design injection flow. Performance of this testing with the reactor coolant system depressurized but intact would not-provide adequate surge volume for influx from the RWST to allow the RHR injection system to reach these design flows. The alternative method of providing a surge volume by partial draining of the retctor coolant system is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
- 20) The accumulator check valves cannot be tested during unit operation due to the pressure differential between the accumulators (
609 psig) and the reactor coolant system (2235 psig). These valves cested except by a rapid depressurization of cannot be full strow the reactor coolant system as would occur during the design basis cold leg double guillotine break. These valves will be partial stroke tested during cold shutdown.
- 21) Component cooling water fM w to the reactor coolant pumps is required at all times the pumps are in operation. Failure of one of these valves in a closed position during exercise test would result in a loss of the cooling flow to the pumps. Exemption is taken to the quarterly exercise test. The valves will be exercise tested during cold shutdown providing all reactor coolant pumps are not in operation. This testing period will be each refueling outage as a maximum.
- 22) This check valve is in the containment air particulate and gas monitor return line. The containment monitor is in continuous operation during unit operation and is also required for containment sampling in the event of an accident since it is passively open and required to stay open. The continued proper operation of the system serves to demonstrate proper check valve operation.
- 23) This manual valve is in the containment air particulate ano gas monitor return line. Quarterly closing of this valve during operation would render the system unable to perform its sampling function. Full stroke testing will be performed during cold shutdown. Relief is taken from measuring stroke time on manual valves.
Page 82 of 83
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- 24) The requirement for the containment air particulate and gas monitor return line isolation is one valve. The leak' test can only be performed using both the check valve (PR0029) and the relief valve in series as one containment isolation boundary.
- 25) Closure of these valves during normal unit operation wculd result in a loss.of letdown. flow resulting in a reactor in a reactor coolant inventory transient and a subsequent reactor trip. There valves will be full stroke exercised during cold shutdown as reqired by' AST
- Section.XI, IW 3410(b) (1).
- 26) These valver are' located in a closed valve containment assembly which is designed as an extension of the containment boundary. These valves are inaccessable during plant operation. The valves can be made accessable during plant shutdown by disassembly of-the valve containment assembly. This requires approximately 100 man-hours per valve in a. radiation field up to 50 mr per hour. Verification that the valve position indication switches have changed in relation to valve position can be made by observing that no significant change in valve stroke time has occurred. Due to the burden in manpower and radiation exposure to perform the direct observation, relief is taken from the requirements of IW-3000.
27)_ These valves can only be full stroke tested by rendering their control systems inoperable. These valves will be full stroke tested during cold shutdown.
- 28) The RHR Suction valves from the reactor coolant system cannot be stroke tested during' power operation. These valves are interlocked with reactor coolant system and are prohibited from opening above 425 psig. Opening these valves would cause a depressurization of the reactor coolant system and overpressurization of the RHR System, 7hese valves will be full stroke tested during cold shutdown.
- 29) This motor operated valve in the reactor coolant pump seal injection return line must remain in a normally open condition during unit operation in order to maintain proper pump seal flow.
This valve will be stroke tested each cold shutdown providing all reactor coolant pumos are not in operation. This testing period will be each refueling outage as a maximum.
Page 83 of 83