ML19323D085
| ML19323D085 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/15/1980 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19323D083 | List: |
| References | |
| 616, PROC-800515, TAC-10985, TAC-11316, NUDOCS 8005200629 | |
| Download: ML19323D085 (195) | |
Text
' '
80 052 0 0 /a
.SECTION I PUMP TECT PROGRAM TABLE OF CONTENTS Page A.
PROGRAM
SUMMARY
I-l B.
PUMP TEST PROGRAM TABLE FORMAT.
I-l C
PUMP PROGRAM TABLE I-3 Pump Test Program.
I-4 D.
CODE EXCEPTIONS I-6 Pump Past Performance Data.
I-10 Pump Past Performance Statistical Analysis I-24 4
. - + -
6 e
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I.
PUMP TEST PROGRAM A.
PROGRAM
SUMMARY
The Pump Test Program identifies test requirements for all safety related pumps both those pumps tested in accordance with the requirements of Subsection IWP of the ASME Boiler and Pressure Vessel Code, 1977 Edition, and Addenda through Summer 1978 Addenda and those pumps for which the Code re-quirements have been found to be impractical.
The Pump Test Program will be applicable for the remainder of the 120-month interval, which etarted on June 27, 1977 after which the Pro-gram will be reviewed and updated, as appropriate, with that Edition of the Code and Addenda in effect not ; ore than 12 months prior to the start of the next 120-month interval.
Individual pump test requirements are presented in Section
'C' by a coded Pump Test Program Table.
The codes used for this Table are defined in Section
'B'.
The Pump Test Program Table of Section 'C' is arranged in numerical sequence by Inservice Inspection Instrument Drawing (ISID) numb ~ err Section 'D' provides justifications for exceptions taken to code test requirements as provided for in 10 CFR 50.55a(g)(5)(iii). Justifications are general in nature and pertain to requirements found to be im-practical for all pumps.
Code exceptions are numbered and refer -
enced by number on the Pump Test Program Table.
B.
PUMP TEST PROGRAM TABLE FORMAT The Pump Test Program Table has been coded to provide the following information:
1.
System and Drawing Number.
System the pump is in and the ISID number.
2.
Coordinates.
Location on the ISID where the pump is found.
3.
Pump Numbe_r_.
Unique number assigned to each pump.
4.
Speed ;.
These parameters are andressed with one of the following entries, which indicate test interval or appli-cability.
e NR - not required e NA - not available e M - monthly test e Q - quarterly test I-l a
5.
Inlet Pressure P. Same as Number 4.
i o
6.
Differential Pressure op. Same as Number 4.
7.
Flow Rate Q.
Same as Number 4.
8.
Vibration Amplitude V.
Same as Number 4.
9.
Bearing Temperature T. Same as Number 4.
b 10.
Lubrication Level or Pressure. Same as Number 4.
11.
Code Exception. If the pump is being tested in ac-cordance with Section XI requirements, this column will be blank. However, for pumps which the Section XI requirements have been found tc be impractical, a reference number is entered in the column.
The reference 4
number is addressed in Section
'D' with a complete explana-tion of the specific exception and justification for that ex'ception.
m I-2
=-
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C.
PUMP PROGRAM TABLE This section provides a tabulation of all safety related pumps
~
both those pumps that are tested in accordance with the require-ments of Subsection IWP of the ASME Boiler and Pressure Vessel Code, 1977 Edition, and Addenda through Summer 1978 Addenda and those pumps for which the code requirements have been found to be impractical. The Table is arranged sequentially by ISID number.
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9 DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 PUMP TEST PROGRAM Page 1
of 2 SYSTEM TEST PARAMETER MEASURED y
INLET DIFFERENTIAL FLOW VIBRATION BEARING LUBRICANT DRAWING PUMP SPEED PRESSURE PRESSURE RATE AMPLITUDE TEMPERATURE LEVEL OR CODE g$
NUMBER U
NO.
n*
Pi Op Q
V T
PRESSURE EXCEPTION b
AUXILIARY J-8 P14-1 NR Q
Q Q
Q NR NR 1,2,3 FEEDWATER 006B K-9 P14-2 NR Q
Q Q
Q NR NR 1,2,3 HIGH E-9 P58-1 NR Q
Q Q
Q NR NR 1,2,3 PRESSURE INJECTION C-9 P58-2 NR Q
Q Q
Q NR NR 1,2,3 y
033 LOW H-7 P42-1 NR Q
Q Q
Q NR NR 1,2,3 PRESSURE INJECTION G-10 P42-2 NR-Q Q
Q Q
NR NR 1,2,3 033 CONTAINMENT D-9 P56-1 NR Q
Q Q
Q NR NR 1,2,3 SPRAY 034 C-9 P56-2 NE Q
Q Q
Q NR NR 1,2,3 COMPONENT H-2 P43-1 NR Q
Q Q
Q NR NR 1,2,3,4 COOLING 036 J-2 P43-2 NR Q
Q Q
Q NR NR 1,2,3,4 K-2 P43-3 NR Q
Q Q
Q NR NR 1,2,3,4 l
- SYNCHRONOUS OR INDUCTION MOTORS DO NOT REQUIRE SPEED CHECK (IWP-4400),
w-
=...
DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 PUMP TEST PROGRAM' Page 2 of 2 SYSTEM TEST PARAMETER MEASURED y
INLET DIFFERENTIAL FLOW VIBRATION BEARING LUBRICANT DRAWING PUMP SPEED PRESSURE PRESSURE RATE AMPLITUDE TEMPERATURE LEVEL OR CODE NUMBER v$
NO.
n*
Pi 6p Q
V T
PRESSURE EXCEPTION b
SERVICE J-5 P3-1 NR Q
Q Q
Q NR NR 1'2'3'4 WATER 041 J-7 P3-2 NR Q
Q Q
Q NR NR 1,2,3,4 J-9 P3-3 NR Q
Q Q
Q NR NR 1,2,3,4.
Yw a
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i t
' SYNCHRONOUS OR INDUCTION MOTORS DO NOT REQUIRE SPEED CllECK (IWP-4400).
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D.
CODE EXCEPTIONS This section provides justification for the exceptions taken to Code test requirements as provided for in 10 CFR 50.55a(g) (5)-(iii).
Each Code exception is identified by a unique number and identifies the pump (s) for which the Code exception is being taken. The specific Code test requirement found to be impractical is defined and the basis for exclusion from Code requirements is presented.
Any testing performed. in lieu of Code requirements is specified.
Code exceptions are numbered and referenced by number on the Pump Test Program Table for specific pumps. This section also precents a summary of past pump testing.
1.
Code Exceptions a.
Code Exception Number 1
- Components: Auxiliary Feedwater Pumps P14-1, P14-2 High Pressure Injection Pumps P58-1, P58-2 Low Pressure Injection Pumps P42-1, P42-2 Containment Spray Pumps PS6-1, P56-2 Component Cooling Pumps P43-1, P43-2, P43-3 Service Water Pumps P3-1, P3-2, P3-3 e Function: Emergency Core Coolwg Safety Related Equipment Cooling e Class:
2 and 3 e Test Requirement: Monthly Inservice Test e Basis for Exception: Monthly Section XI operability testing has been a Technical Specification requirement for these pumps since April 22, 1977. An analysis of the results of these tests and comparable data from other operating plants has shown no significant changes in performance.
Based on this analysis, the continuation of Section XI monthly testing would not significantly increase plant safety.
The Auxiliary Feedwater, High Pressure Injection, Low Pressure Injection and Contain-ment Spray Pumps are standby pumps whose continuous operation is not required. The Service Water and Component Cooling Water ptnps are continuously running and any significant degradation will be detected during normal operation.
,s Monthly pump testing requires a total of at least 270 hours0.00313 days <br />0.075 hours <br />4.464286e-4 weeks <br />1.02735e-4 months <br /> per year of pump operation; at least 714 man-hours per year for data acquisition; at least 60 man-hours I-6
per year for data reduction, analysis, and record keeping. This amounts to a total of 774 man-hoers 12r year. At a conservative total cost of $20 per man-hour, this amounts to $15,480 per year.
Based upon the average exposure rates in the areas of the Auxiliary Feedwater, High Pressure' Injection, Low Pressure Injection and Containment Spray Pumps, the total man rems exposure per year for pump testing is approximately 2.0 man rems.
At the present conser-vatively estimated cost of $10,000 per man rem to plant personnel, this exposure costs an additional
$20,000 per year.
Total cost to our customers is approximately $35,480 per year, for no significant increase in safety.
e Alternate Testing:
Pumps will be tested in compliance with'ASME Section XI once per quarter.
This is in agreement with present changes that are being imple-mented in Subsection IWP of the Code.
The revision to change pump testing to a three-month interval in IWP-3400 has been approved and will be included in future Addenda. See minutes of the
~~1-November 28, 1979 meeting of the Operating and Main-tenance Working Group - Testing of Pumps and Valves, in San Jose, California, dated January 9, 1980.
b.
Code Exception Number 2 e Components: Auxiliary Feedwater Pumps P14-1, P14-2 High Pressure Injection Pumps P58-1, P58-2 Low Pressure Injection Pumps P42-1, P42-2 Containment Spray Pumps P56-1, P56-2 Component Cooling Pumps P43-1, P43-2, P43-3 Service Water Pumps P3-1, P3-2, P3-3 e Function: Emergency Core Cooling Safety Related Equipment Cooling e Class: 2 and 3 o
e Test Requirements: Measure pump bearing temperature yearly.
e Basis for Exception: The referenced Editon of the Code requires bearing temperature to be recorded annually.
It has been demonstrated by experience that bearing temperature rise occurs only minutes prior to bearing failure. Therefore, the detection of possible bearing failure by a yearly temperature measurement l
I-7
-a
is extremely unlikely.
It requires at least an hour of pump operation to achieve stable bearing tempera-tures. The small probability of detecting bearing failure.by temperature measurement does not justify the additional pump operat ng time required to obtain the measurements.
e Alternate Testing:
NONE.-
This is in agreement with present changes that are being implemented in Sub-section IWP of the Code. The revision to delete yearly bearing temperature measurement.
Deletion of 3
bearing temperature has been approved and will be included in future Addenda. See minutes of the November 28, 1979 meeting of,the Operating and Maintenance Working Group Testing of Pumps and Valves in San Jose, California, dated January 9, 1980.
c.
Code Exception Number 3 e Components: Auxiliary Feedwater Pumps P14-1, P14-2 High Pressure Injection Pumps P58-1, P58-2 Low Pressure Injection Pumps P42-1, P42-2 Containment Spray Pumps P56-1, P56-2 Component Cooling Pumps P43-1, P43-2, P43-3 Service Water Pumps P3-1, P3-2, P3-3 e Function:
Emergency Core Cooling Safety Related Equipment Cooling e Class:
2 and 3 Test Requirements: Observation of proper lubrication e
level or pressure.
e Basis for Exception: The observation of lubrication level or pressure is a maintenance function not an operability test function. Pump lubrication require-ments are determined by the pump manufe:turer and plant operation.
e Alternate Testing: Pump lubrication requirements are part of the plant maintenance procedures rather than Section XI operability test requirements. This is in agreement with present changes that are being imple-mented in Subsection IWP of the Code. The revision to eliminate observation of lubrication level or pressure from the Code has been approved and will be included in future Addenda. See minutes of the November 28, 1979 meeting of the Operating and Main-tenance Working Group - Testing of Pumps and Valves, in San Jose, California, dated January 9, 1980.
l i
I-8
d.
Code Exception Number 4 e Components: Component Cooling Pumps P43-1, P43-2, P43-3 Service Water Pumps P3-1, P3-2, P3-3 e Function: Safety Related Equipment Cooling e Class:
3 Test Requirements: Operability testing of installed e
spare pumps, o Basis for Exception: Any one of the three componeat cooling or three service water pumps is an installed spare.6 One pump is nonnally running, the second is aligned as an automatic backup to the operating pump and the third pump is electrically disconnected and manually valved out of the system.
In the event of failure of the operating pump, the second automatically starts and the installed spare is electrically connected
^
and manually valved in as the reserve pump.
AiternateTesting: The normally operating and reserve e
pump will be tested. The installed spare need to be tested only when it is connected to the system.
2.
Past Pump Performance The following information is submitted for your' review:
a.
Pump Past Performance Data b.
Piunp Past Performance Statistical Analysis I-9
- m-;
- c -_= - __..--~,na, a,- n
,,_.,.,,__m.__,.,,x,___._x x
DAVIS-BESSE NUCLEAR POWER STATION PUMP T
RFORMANCE-PUMP NO.
1-1 DATA A = AXIAL NA = NOT AVAILABLE DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY
...AUG.
SEPT.
OCT.
NOV.
DEC.
PUMP V
.11
.14
.14
.11
.14
.076
.15
.12
.09
.045 1NaOAno 2:
(MILS)
.20
.14
.17
.14
.15
.17
.16
.23
.16
.062 0
^
.60
.55
.54
.28
.43
.38
.38
.30
.40
.068 28 y
ag PUMP
.09
.15
.15
.11.
.11
.12
.088
.10
.13
.052
.28
.25
.22
.22
.19
.24
.' 2 2
.24
.21
.071 M
A
.70
.52
.52
.25
.44
.32
.28
.26
.28
.041 U
FLOW s
(GPM) 1250 1260 1310 1260 1290 1250 1290 1300 1275 1300 lh
?
S TDH I4 (PSID) 176 178 175 175 174 177 171 175 175 175 a.
DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
V PUMP
.11
.11
.11
.12 13
.13
.14
.20
.13
^
g
.16
.13
.14
.17
.15
.16
.15
.17 s16 A
.42
.32
.45
.34
.28
.38 g
.38 l
N PUMP
.42
.12
.11
.11
.13
.17
.10
.20
.11 g
ONE H
.27
.22
.22
.28
.22
.26
.20
.24
.22 (MILS)
A
.34
.32
.34
. 26'
.23
.34
.36
.60
.38 6
rLOW (GPM) 1300 1275 1325 1318 1280 1314 1310 1305 1290 o
S TDH g
(PSID) 175 175 204 204 173 173 A69 175 173
j DAVIS-BESSE NUCLEAR POWER STATION l
PUMP CONTAINMENT SPRAY UNIT NO. 1 PUMP PAST* PERFORMANCE.
~V = VERTICAL PUMP NO.
1-2
, DATA H = HORIZONTAL A = AXIAL NA = NOT AVAILABLE i
DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
PUMP V
.20
.15
.20
.34
.42
.24
.52
.18 1.9
.49
.46 INBOARD H
(MILS) 1.5
.23
.34
.62
.30
.40
.36
.23
.22
.60
.80 g@
E
^
3.20
.45
.62 2.40 2.70 1.20 2.35
.68
.40 a.40 3.50 18 y
ag PUMP
.60
.18
.17 1.40
.37
.38
.52
.23
.38
.82
.70
.50
.25
.15 1.30
.28
.80
.24
.24
.28
.46
.18 M
A 3.60
.48
.30 3.80 2.G0 1.40 2.75
.84 2.60 3.70 3.80 I
1300 1300 1300 1326 1250 1275 1300 1300 1300 1325 1307.5
)
BAh TDH M
(PSID) 174 170 172 177 171 170 163 175 172 175.40 173.30 m
DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
Y PUMP
.50
.53
.43
.19
.72
.32
.18
.32 INBOARD H
- r,
.32
.38
.35
.34
.39
.38
.28
.32 o@
'(MILS)
A g
2.20 2.30 2.00
.62 3.20
.56
.52
.54 mN PUMP
.60
.74
.52
.30
.64
.28
.18
.24 V
O N OARD H
.40
.30
.27
.29
.24
.35'
.32
.24 (MILS)
^
2.30 2.50 2.00 1.10 2.80
.78
.64 1.20 U
FLOW (GPM) 1275 1300 1300 1320 1320 1320 1300 1290 bAh TDH W
(PSID) 175 175.70 175.40 176.30 175 175 168 166 m
DAVIS-BESSE NUCLEAR POWER STATION
~ ~ " "
PUMP HIGH PRESSURE INJECTION UNIT NO. 1 PUMP PAST*PERFOR N CE' p, yg PUMP NO.
1-1 DATA H = HOMON A = AXIAL NA = NOT AVAILABLE DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
PUMP V
.06
.06
.062
.12
.17
.13
.13
.62
.12
.12
.12
.17 INBOARD H
z (MILS)
.28
.30
.13
.30 1.00 1.60
.92
.68 1.30
.56
.49
.41 h
.08
.11
.12'
.12 428
.38
.15
.74
.40
.15
.16
.21 IO y
mg
. PUMP
.14
.28
.21
.18
.23
.16
.058
.42
.80
.15
.078
.084
.30
.54
.38
.28 1.00 1.50 1.20
.68 1.40
.92
.98
.87 A
.20
.13
.10
.12
.16 2.10
.09
.54 1.8
.10
.12
.14 U
FIDW
- y (GPM) 280 290 286 290 288 290 290 304.3 290 290 288 290 mh TDHs N
(PSID) 1569 1569 1553 1566 1566 1568 1570 1560 1563 1569 1554 1562 m
DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
pg V
.19
.12
.80
.069
.054
.065
.072
.058
.054
' INBOARD H
2
.84
.99 1.60
.66
.68
.62
.56
.52
.52 O@
'(MILS) gg
.24
.305
.34
.11
.13
.10
.12
.12
.084 mN PUMP
.11
.12
.08
.08
.084 4078
.086
.064
.086 OUTBOARD H
1.30
.130 1.60
.20
.21
.20
.20
.28
.19 i
(MILS)
A
.13
.21
.19
.10'
.12
.12
.13
.20
.11 U
FLOW h
(GPM) 290 285 290 285 290 290 288 280 290 IR DO hg TDH N
(PSID) 68.50 1548.50 1578 1568. M 1568 1572 1579 1568 m
l
DAVIS-BESSE NUCLEAR POWER STATION PUMP HIGH PRESSURE INJECTION V=
p PUMP NO.
1-2 DATA A = AXIAL NA = NOT AVAILABLE DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
PUMP V
.11
.14
.15
.14
.11
.17
.095
.18
.12
.11
.11
.14 INBOARD g
(MILS)
.74
.76 80
.74
.70
.84
.99 1.00
.92
.84
.86
.80 50
.11
.88
.13
.12 211
.16
.070
.11
.08
.18
.19
.28 88 y
$g PUMP
.12
.12
.20
.089
.081
.11
.11
.30
.12
.10
.11
.10
.50
.38
.27
.45
.24
.25
.32
.28
.19
.30
.23
.30 M
A
.10
.13
.13
.12
.12
.15
.099
.11
.11
.11
.15
.15 d
FIM (GPM) 290 285 290 285 290
- 290, 290 290 284 290 290 290 Y I U
mh TDH W
(PSID) 1569 1569 1563 1561 1567 1578 1559 1569 1600 1571 1566.20 1570.20 m
DATE 1979 JAN.
FEB.
MAR.
APR.'
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
V
.26
.085
.42
.10
.13
.11
.12
.092
.11 PUMP INBOARD H
g
. (MIM)
.90
.82
.78
.95
.84
.27,
.88
.90
.80 5g A
.24
.10
.18
.11
.15
.15
.088
.086
.26 V
PUMP
.2R
.11
.08
.11
.11 l11
.105
.10
.11 OUTBOARD H
.24
.59
.22
.18
.24
.27
.19
.18
.28 (MIM)
.14
.13
.14
.11'
.13
.10
.11
.12
.14 U
FLOW (gpg) 286 290 290 285 290 290 290 289.40 286.30 mm TDH g
(PSID )
1567 1567 1567 1580.70 1576.5 1566.5 1561 1559.3 1564.6
8
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V 2
6 3
6 0
2 O
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2 1
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2 3
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5 8
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DAVIS-BESSE NUCLEAR POWER STATION PUMP SERVICE WATER V = VERTICAL PUMP HO.
1-2 H = HORIZONTAL A = AXIAL NA = NOT AVAILABLE r-DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE.
JULY AUG.
SEPT.
OCT.
NOV.
DEC.
PUMP V
.29
.23 NA
.36
.3
.24
.34
.16
.31
.40 INBOARD g
(MILS)
.17
.12 NA
.27
.13
.038
.12
.32
.12
.13 EO A
.032
.065
.NA 115
.084
.11
.07
.12
.055
.10 28 v
gg PUMP OUTBOARD H
(MILS)
U FIDW Y
(GPM) 9343 9150 NA 9121 9100 9400 9200 9000 9000 9000 b
os h TDH N
(PSID) 79.5 79.5 NA 79.5-79.6 79.5 79.5 79
~79 79.03 p.
DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
V
.26
.28
.21
.29
.38
.29
.22 pg INBOARD H
z
.12
.12
.41
.11
.13
.11
.34 o@
-(MILS)
"g A
.09
.10
.14
.068
.09
.07
.13 I
.N PUMP V
5 OUTBOARD H
1 (MILS)
D FLOW (CPM) 9000 9029 9100 8400 9086 8871 9040 oA TDH
- O M
(PSID) o.
e
N DAVIS-BESSE NUCLEAR POWER STATION PUMP SERVICE WATER UNIT NO. 1 PUMP PAST' PERFORMANCE-PUMP NO' l-3 DATA H = HORIZONTAL A = AXIAL NA = NOT AVAILABLE i
DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
PUMP V
.16
.13
.17
.18
.22
.24
.10
.13
.17 INBOARD H
2 (MILS)
.22
.17
.20
.26
.20 19
.17
.19
.24 0
^
.11
.08
.12
.11
.44
.12
.07
.08
.11 N
v PUMP OUTBOARD H
(MILS)
U FLOW (GPM) 9000 8800 8600 8625 9000 8800 0000 9100 9071 b
hh TDH g
(PSID) 85.5 86 86 86 86 86 86 86 85.2 DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
V PUMP
.15
.16
.19
.22
.20
.15
.17 BO M H
2
.26
.17
.15
.22
.19
.085
.15 Sg
~(MILS)
A gg
.16
.076
.092
.12
.074
.072
.076 mN PUMP 5
OUTBOARD H
l (MILS) d FLOW (GPM) 9150 9000 9071 8900 8500 9085 8608 h
TDH g
(PSID) 85.6 85.3 85.3 85.5 86.01 83.8 86
O
^
< )
i DAVIS-BESSE NUCLEAR POWER STATION PUMP AUXILIARY FEED PUMP UNIT NO. 1 PUMP PAST* PERFORMANCE-.
PUMP NO.
1-1 DATA H = HORIZONTAL A = AXIAL NA = NOT AVAIT ABLE DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
PUMP V
.074
.07
.11
.082 75
.06
.11
.16 INBOARD g
(MILS)
.120
.18
.26
.160
.15
.13
.18
.215 EO
^
.054
.07
.13
.059
.085
.06
.088
.072 18 y
gg PUMP
.220
.26
.26
.190
.23
.23
.19
.21
.130
.16
.21
.140
.15
.14
.19
.22 g
A
.11
.40
.26
.084
.11
.12
.14
.14 d
FIDW H
(GPM) 817 821 813 825 820 818 815 820 l
S!
i Sh TDH g
(PSID) 1105 1099 1172 1199 1194 1223 1185 1111 DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
V
.13
.088
.022
.C68
.22
.20
~~.14 pg
. INBOARD H
2
.16
.18
.15
.34
.25
.22
.17 o@
~(MILS)
"g A
.078
.06
.064
.050
.08
.13
.10 N
' PUMP
.165
.12
.15
.14
.16
.21
.18 I
g>
OUTBOARD H
.20
.19
.16
.11
.20
.28
.16 (MILS)
A
.14
.12
.12
.090
.14
.14
.17 U
FLOW (GPM) 820 810 808 537 813 NA NA oA TDH g
(PSID)
- 118 1120 1122.5 1100 1128 NA 1197.3
DAVIS-BESSE NUCLEAR POWER STATION PUMP T'P RMANCE-PUMP NO.
1-2 DATA A = AXIAL NA = NOT AVAILABLE DATE 1978 JAN.
FEB.
MAR.
APP.
MAY JUNE
. JULY AUG.
SEPT.
OCT.
NOV.
DEC.
PUMP V
.13
.21
.084
.10
.99
.18
.10.
.17 INBOARD H
g (MILS)
.19
.24
.12
.19
.11
.20
.15
.26 EO
^
.11
.D95
.08
.09
.092
.10
.071 58 y
gg PUMP
.54
.33
.56
.34
. 57
.3 50
.54
.19
.21
.15
.40
.14
.18
.22
.22 (MILS)
.29
.31
.24
.13
.17
.11
.45
.21 U
FIDW H
(GPM) 820 820 806 820 820 825' 813 813 b
bmh TDH g
(PSID) 1255 1258 1210 1250 125G 1257 1280 1267 DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY A'JG.
SEPT.
OCT.
NOV.
DEC.
V PUMP
.24
.072
.08
.26
.07 INBOARD H
.15
.12
.11
.15
.12 y,og
~(MILS)
Eg A
.075
.05
.068
.15
.06 mN PUMP
.50
.38
.34
.42,
.36
.20
.15
.17
.21
.19 (MILS)
A U
.22
.22
.17
.15
.14 FLOW 820 820 820 812 810 (GPM)
TDH 1266 1270.9 1256.7 1215.3 1238 g
(PSID )
y_
DAVIS-BESSE NUCLEAR POWER STATION PUMP DECAY HEAT UNIT NO. 1 PUMP PAST' PERFORMANCE-V = VE m N PUMP NO.
11 H = HORIZOMTAL
' DATA A = AXIAL NA = NOT AVAILABLE DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
.OCT.
NOV.
DEC.
PUMP V
.20
.39
.92
.62
.74
.60
.11
.72
.82
.82
.75
.50 INBOARD j
g (MILS)
.21
.31
.05
.29
.36
.58
.56
.62
.46
.46
.38
.40 5O A
.14
.34 1.0
.82
.86
.94
.12 1.1
.58
.28
.58
.90 18 y
m PUMP
.17
.31 1.0
.78
.67
.40 1.2
.8
.46
.70
.265 1.1
>g OUTBOARD H
.26
.41 1.1
.74
.86
.60
.86
.75 1.0
.86
.86 1.0 (MILS)
A
.14
.29
.70
.59
.53
.54
.78
.62
.52
.34
.34
.44 U
FIDW y
(GPM) 2928 3000 3010 3058 3050 2979 2987 3000 3000 3038 3000 3027 A
b mh TDH N.
(PSID) 159 158 159 159 159 157 156 152 NA 156 157 157 a
DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
V
.70
.60
.64
.56
.52
.80
.79
.86 PUMP
. INBOARD H
z
.80
.41
.40
.34
.36
.50
.38
.46 Og
'(MILS)
"g A
.36
.46
.10
.74 1.1
.67
.64
.78 mN PUMP
.68
.26 1.3 1.2
.82
.40
.62
.45 1
V H
.80
.88
.78
.44
.78
.68
.79
.82 A
.36
.44 4.2
.74
.58
.60
.72
.66 h
(GPM) 2970 3031 2030 3032 3000 3015 2975.7 3050 IR "p
o E
TDH 156 158 146 150 158 156 157 156 g
(PSID)
i DAVIS-BESSE NUCLEAR POWER STATION
- PUMP DECAY HEAT UNIT NO. 1 PUMP PAST*1ERFORMANCE V = VE m N PUMP NO. 1-2 DATA H = HORIZONTAL A = AXIAL NA = NOT AVAILABLE I
DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
i' PUMP V
.39
.50
.59
.80
.012
.62
.40
.46
.52
.43
.45
.49 j
INBOARD g*
(MILS)
.72
.70
.67
.80
-015
.84
.56
.84
.61
.60
.61
.66 c
EE A
.22
.50
.41
.36
.015'
.36
.32
.36
.36
.28
.31
.38 58 v
q gg PUMP
.21
.30
.26
.80
.029
.68
.48
.42
.31
.30
.32
.37 j
NW H
.68
.70
.68
.80
.027
.89
.73
.90
.60
.62
.62
.63 (MILS)
.29
.38
.34
.40
.017
.38
.29
.32
.31
.26
.26
.30 U
FIDW jy (GPM) 2990 3049 3026 3022 3000 3000 3060 3025 3040 2972 3042 3054
!0
$mh i
TDH M
(PSID) 157 152 151 151 152 150 157 159 157 157 157 158 m
DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
ph V
.47
.40
.44
.36
.40
.25
.32
.32
.38 H
m
.76
.41
.62
.62
.55
.71
.58
.55
.48 SQ
'(MILS) g 8
.33
.26
.25
.24
.32
.25
.36
.27
.29
$ N V
PUMP
.60
.24
.62
.52
.62 262
.38
.30
.26 l
ONE H
.75
.64
.21
.72
.80
.81
.70
.67
.60 (MILS)
A
.36
.25
.10
.28
.31
.31
. 3 8'
.26
.32 d
FLOW (CPM) 3579 2900.7 2982 3047 3000 3051 3017 3029 3009 e
m TDH M
(PSID) 155.9 159 159 156 157 156 158 157.7 156 m
e
-~
~,
DAVIS-BESSE NUCLEAR POWER STATION PUMP OOMPONENT COOLING T NO. 1 PUMP PAST' PERFORMANCE-V = VERTICAL PUMP NO.
1 DATA H = HORIZONTAL A = AXIAL NA = NOT AVAILABLE i
DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
'OCT.
NOV.
DEC.
PUMP V
.11
.11
.18
.20
.44
.18
.12
.12
.11
.12 INBOARD H
2 (MILS)
.34
.26
.40
.34
.32
.30
.22
.23
.26
.26 EO A
1.2 2.4
. 24
.7;
.22 1.7
.48
.70
.75
.50 28 v
gg PUMP
.26
.52 1.7
.24
.34
.21
.14
.15
.15
.25
.61
.30
.54
.44
.44
.50
.34
.34
.45
.30 1.4
.20 1.80
.70 2.' 30
.19
.56 1.10 1.10
.60 U
FIDW Y
(GPM) 4700 7300 7400 4800' 7500 4800 7400 7200 7500 7300 0
b mh TDH te (PSID) 81 84 66 81 75 97 82 84 66 m
DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
Y PUMP
.016 1.2
.36
.12
.19
.14
.12
.16
.17 2
.024
.42
.42
.34
.36
.60
.28
.34
.34
'(MILS) g g
.03 1.1 1.1
.78
.52 1.2
.65
.70
.74 mN PUMP
.03
.24
.32
.24
.20
.24
.12
.20
.26 OMM H
.024
.52
.54
.44
.36
.62
.16
.29
.46 (MILS)
A
.016 1.5 1.1
.86
.58 1.4
.80
.78
.76 U
FLOW (GPM) g 7400 4600 4600 4593 7300 7200 4792 7500 4755 oo Ag
.TDH J
g (PSID) 82 79 79.5 81.3 68 67 79.7 65 80.5
+
t a
DAVIS-BESSE NUCLEAR POWER STATION PUMP ccMponpnT coorTNG WATER V = VERI pg
1-2 DATA A = AXIAL NA = NOT AVAILABLE DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
PUMP V
.17
.28
.14
.76
.22
.13
.20
.16
.16 INBOARD H
z (MILS)
.36
.29
.26
.23
.24
.21
.36
.23
.30 EO A
1.40
. 13 1.20 1.30 1.40 1.1 1.00 1.40 1.30
%8 v
gg PUMP
.19
.38
.18
.25
.32
.22
.26
.34
.20 ONE H
.03
.50
.38
.42
.43
.40
.40
.46
.50 (MILS)
^
1.90 1.50
.12 1.50 1.50 1.00 1.80 1.50 1.60 U
FIDW 7
(GPM) 4700 7414 7550 7500 7600 7500 4600 7500 7493 0
bAh TDH g
(PSID) 80.00 68-67 67 66 66 99 67 66.1 DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
ph V
.16
.20
.15
.18
.24
.26
.16
. INBOARD H
2
.19
.75
.22
.19
.40
.22
.20 gg
'(MILS)
A gg 1.10 1.30 1.20 1.40 1.90 1.80 1.70 mN PUMP
.31
.25
.19
.45
.48
.18
.31 ONE H
.36
.45
.42
.48
.46
.46
.45 (MILS)
A 1.20 1.60 1.30 1.50 2.20
.17 1.95 8
rLOw (GPM) 7464.3 7400 7450 7507 4550 7514 7600 DO A g' TDH g
(PSID) 65.33 65 65.28 65.28 79.5 63.70 64 P
o m
Q
~
^
DAVIS-BESSE NUCLEAR POWER STATION PUMP COMPONENT COOLING WATER 5=
p PUMP NO.
1-3 DATA -
A = AXIAL NA = NOT AVAILABLE DATE 1978 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
PUMP V
.56
.28
.42
.20 1.6
.68
.34
.34
.27
.44
.34 INBOARD g
(MILS)
.90
.40
.50
.19
.57
.54
.55
.64
.90
.72
.57 5O 1.30
.27
.70 1.9
.74 1.1
.90 2.50 1.50
.90
.66 IO V
mg PUMP
.70
.15
.50
.32 1.70
.70
.31
.40
.22
.26
.57 1.00
.25
.54
.44
.47
.70
.40
.68 '
.72~
.44
.71 M
1.50
.28
.70 1.00
.73 1.3 1.00 2.50 2.20
.78
.11 U
FLOW y
(GPM) 4700 NA 7203 7250 7300 4650 7400 4600 4500 7250 7250 U
mh TDH N
(PSID) 80 NA 69 69 69 82 83 82 97 NA 67 a.
DATE 1979 JAN.
FEB.
MAR.
APR.
MAY JUNE JULY AUG.
SEPT.
OCT.
NOV.
DEC.
V
.18
.25
.37
.25
.38
.32
.34
.44 p
. INBOARD H
2:
.46
.80 1.0
.84
.65
.56
.58
.84 "g
-(MILS) o A
.72
.20 1.00 1.80 1.10 1.50 1.70 1.10 g
mN PUMP'
.28
.45
.5
.54
.45
.52
.54
.42 V
N OUTBOARD H
.53
.75
.72
.84
.65
.76
.66
.68 (MILS)
A
.71 2.00 1.60 1.80 1.30 1.50 1.60 1.10 7192 4810 4700 4600 4728 4500 4750 4800
)
lla
~
66 81.48 81.0 81.50 81.6c 82.06 81.80 80.e0
DAVIS-BESSE NUCLEAR POWER STATION I
UNIT NO. 1 PUMP PAST PERFORMANCE STATI'STICAL ANALYSIS!
V = VERTICAL
. PUV2 DECAY HEAT H = HORIZONTAL A " MN PUMP NO.
1-2 NA = NOT AVAILIBLE DATE 1978
,1979 MEAN STANDARD DEVIATION
.VARIs CE, V
0.429 0.152 0.C22 p
~
INBOARD H
0.615 0.176 0.030 A
0.307 0.0%
0.008 VIBRATION V
0.411 0.191 0.035 pg OUTBOARD H
0.656 0.201 0.038 A
0.291 0.090 0.008 C
PUMP FIm (GPM) 3042.6 128.1 15632.3
]
TDH (PSID) 155.8 2.84 7.68 PUMP COMPONENT COOLING PUMP NO.
1
)
DATE 1978 - 1979 MEAN STANDARD DEVIATION VARIANCE V
0.219 0.255 0.062
)
pg INBOARD H
0.319 0.122 0.012 A-O.827 0.549 0.286 VIBRATION V
0.306 0.352 0.118 PUM OUTBOARD H
0.404 0.150 0.021 (MILS)
A 0.934 0.572 0.310 i
FIM (GPM) 6244.2 1352.5 1732936.9 PUMP PERFORMANCE TDH (PSID 77.66 8.37 66.18
DAVIS-BESSE NUCLEAR POWER STATION I
IINIT NO. 1 PUMP P.AST PERFORMANCE STATISTICAL ANALYSIS V = VERTICAL
. PUMP COMPONENT COOLING WATER H = HORIZONTAL
^
PUMP NO*
l-2 NA = NOT AVAILABLE VARIANCE MEAN
-STANDARD DEVIATION DATE 1978 - 1979 v
.223 0.150 0.021 puMe INBOARD H'
O.291 0.139 0.018 t
I A
1.29 0.397 0.148 B M ON v
0.282 0.095 0.008 Pue OUTBOARD H-O.4125 O.110 0.01'l A
1.396 0.568 0.303
. C PUMP FIDW (GPM) 6958.9 1163.7 1269483.1 TDH (PSID) 69.64 9.22 79.65 PUMP COMPONENT COOLING WATER PUMP NO.
1-3 DATE 1978 - 1979 MEAN STANDARD DEVIATION VARIANCE V
0.421 0.310 0.091 pg INBOARD H
0.643 0.201 0.038 A.
1.136 0.577 0.316 VIBRATION V
0.502 0.327 0.101 pgg
^ OUTBOARD H
0.628 0.176 0.029 A
1.248 0.632 0.378 FIDW (GPM) 5676.8 1305.8 1610266.5 PUMP PERFORMANCE TDH,(PSID 78.47 7.95 59.4 I-25
DAVIS-BESSE NUCLEAR POWER STATION I
UNIT NO. 1 PUMP PAST PERFOILMANCE STATISTICAL ANALYSIS;
~'
V = VERTICAL
. PUMP CONTAIt: MENT SPRAY H = HORIZONTAL A"
^'
PUMP NO.
1-1 NA = NOT AVAIIABLE DATE 1978 - 1979 MEAN STANDARD DEVIATION VARIANCE 9
V 0.121 0.032 0.001 PUMP INBOARD H'
O.156 0.032 0.001 i
A 0.382 0.123 0.014 VIBRATION v
0.135 0.07F 0.005 Pup
~
OUTBOARD H
C.225 O.J45 0.002 A
0.357 0.149 0.021 C
PUMP FIDW (GPM) 1289.6 22.9 497.7 TDH (PSID) 177.5 9.56 86.6 PUMP CONTAINMENT SPRAY PUMP NO.
1-2 l
l DATE 1978 - 1979 MEAN STANDARD DEVIATION VARIANCE V
0.436 0.388 0.142 p
INBOARD H
0.44 0.295 0.083 I@MI 1.728 1.158 1.271 A.
VIBRATION y
0.487 0.301 0.086 OUTBOARD H
0.373 0.267 0.067 i
IEM) 2.063 1.197 1.359 A
b FIDW (GPM) 1300.4 18.86 337.0 pggp PERFORMANCE TDH (PSID 172.6 3.78 13.6 i
t w
DAVIS-BESSE NUCLEAR POWER STATION I
UNIT NO. 1 PUMP PAST PERFORMANCE STATISTICAL ANALYSIS-,
V = VERTICAL
. PUMP llIGH PRESSURE INJECTION H = IIORIZONTAL
^~
PUMP NO.
1-1 NA = NOT AVAILIBLE DATE 1978'- 1979 MEAN STANDARD DEVIATION VARIANCE V
0.160 0.190 0.034 p
0.405 0.156 INBOARD H'
-0.712 i,
9
^
VIBRATION V
0.170 0.169 0.027 p
OUTBOARD H-0.740 0.501 0.239
("
A 0.329 0.549 0.287 C
PUMP FIDW (GPM) 288.8 4.75 21.48 TDH (PSID) 1566.1 7.42 52.4 PUMP liIG{ PRESSURE INJECTION PUMP NO.
1-2 DATE 1978 - 1979 MEAN STANDARD DEVIATION VARIANCE V
0.143 0.074 0.005 l
p IlmOARD H
0.816 0.149 0.021 j
IM A.
0.180 0.171 0.028 i
VIBRATION V
0.127 0.059 0.003 l
1 PUMP OUTBOARD H
0.264 0.130 0.016 (MILS)
A 0.124 0.017 0.0003 L
FIDW (GPM) 288.6 2.24 4.77 PUMP PERFORMANCE TDH,(PSID 1569.1 9.08 78.46
DAVIS-BESSE NUCLEAR POWER STATION
(
UNIT NO. 1 PUMP PAST PERFORMANCE STATISTICAL ANALYSIS V = VERTICAL
, PUMP SERVICE WATER H = HORIZONTAL A = AXIAL PUMP NO.
1-1 g, g ggg DATE 1978 - 1979 MEAN STANDARD DEVIATION VARIANCE V
0.444 0.192 0.035 e
INBOARD H'
i 0.355 0.225' 4-0.048 A
0.185 0.152 0.022 VIBRATION PUMP OUTBOARD H
(MILS C~
PUMP FLOW.(GPM) 8945.9 247.2 57516.6 j
EMO N G TDH (PSID) 83.25 1.386 1.785 PUMP SERVICE WATER PUMP NO.
1-2 DATE 1978 - 1979 MEAN STANDARD DEVIATION VARIANCE V
0.279 0.060 0.003 p
INBOARD H
0.172 0.104 0.010 I
A.
0.092 0.032 0.001 VIBRATION PUMP OUTBOARD H
(MILS)
A FIDW (GPM) 9052.5 218.7 44823.0 PUMP PERFORMANCE TDH,(PSID 79.30 0.269 0.068 l
DAVIS-BESSE NUCLEAR POWER STATION
(
UNIT NO. 1 PUMP PAST PERFORMANCE STATISTICAL ANALYSIS' V = VERTICAL
. PUMP SERVICE WATER H = HORIZONTAL A"
PUMP NO.
1-3 NA = NOT' AVAIIIBLE 4
DATE 1978 - 1979 MEAN STANDARD DEVIATION VARIANCE i
V 0.171 0.037 0.001 pg INBOARD H'
O.192 0.044 0.002 VIBRATION 0.119
'O.089 0.007 A
PUMP OUTBOARD H
I (MILS C
PUMP FIDW (GPM) 8894.4 210.6 41599.4 EMONG TDH (PSID) 85.64 0.579 0.314 PUMP AUXILIARY FEED PUMP PUMP NO.
1-1 DATE 1978 - 1979 MEAN STANDARD DEVIATION VARIANCE V
0.107 0.054 0.003 pg INBOARD H
0.191 0.058 0.003
'(MILS)
A-0.079 0.025 0.001 VIBRATION V
0.194 0.042 0.002 PUM OUTBOARD H
0.176 0.043 0.002 I"
A 0.152 0.080 0.006 L
FIDW (GPM) 795.2 77.7 5574.6 pggp PERFORMANCE TDH,(PSID 1148.6 43.8 1783.9 4
w
DAVIS-BESSE NUCLEAR POWER STATION
{
UNIT NO. 1 PUMP PAST PERFORMANCE STATISTICAL MIALYSIS V = VERTICAL
, PUMP AUXILIARY FEED PUMP H = HORIZONTAL A = AXIAL PUMP NO.
1-2 g, g gyg g g DATE 1978 - 1979
- MEAN STANDARD DEVIATION VARIANCE V
PUMP O.137 0.067 0.004 INBOARD H'
0.162,
0.050 0.002 A
0.087 0.026 0.0006 VIBRATION V
0.437 0.100 0.009 PUMP OUTBOARD H
0.202 0.065 0.004 (MILS A
0.216 0.093 0.008 PUMP FLOW (GPM) 816.8 5.43 27.2 TDH (PSID) 1252.3 20.37 383.1 DECAY HEAT 1-1 PUMP PUMP NO.
DATE 1978 - 1979 MEAN STANDARD DEVIATION VARIANCE V
0.633 0.212 0.043 PUMP INBOARD H
0.417 0.157 0.023 A
0.626 0.322 0.098 VIBRATION V
0.680 0.345 0.113 p
4*
OUTBOARD H
0.764 0.205 0.040 I
I A
0.707 0.839 0.699 F M (GPM) 2999.0 50.8 2450.6 PUMP PERFORMANCE TDH (PSID 156.1 3.36 10.73 I a
4.
SECTION II VALVE TEST PROGRAM t
4 d
TABLE OF CONTENTS Page A.
PROGRAM
SUMMARY
II-l B.
VALVE TEST PROGRAM TABLE FORMAT II-l C.
VALVE PROGRAM TABLES II-5 Valve Test Program II-6 D.
CODE EXCEPTIONS II-57 VALVE TEST PROGRAM CODES II-71 e
p
,a.
w
II.
VALVE TEST PROGRAM A.
PROGRAM
SUMMARY
The Valve Test Program identifies test requirements for all safety related valves both those valves tested in accordance with the re-quirements of Subsection IWV of the ASME Boiler aad Pressure Vessel Code, 1977 Edition, and Addenda through Summer 1978 Addenda and those valves for which the Code requirements have been found to be impractical.
The Valve Test Program will be applicable for the re-mainder of the 120-month interval, which started on June 27, 1977 8
after which the Program will be reviewed and updated, as appro-
]
priate, wi{h that Edition of the Code and Addenda in effect not l'
more than 12 months prior to the start of the next 120-month interval.
s Individual valve test requirements are presented in Section
'C' by coded valve Test Program Tables. The codes used for these Tables are defined in Section
'B' and summarized in Figure 1.
The Valve Test Program Tables of Section
'C' are arranged in numerical se-
~
quence by Inservice Inspection Instrument Drawing -(ISID) number.
Section
'D' provides justifications for exceptions taken to code test requirements as provided for in 10 CFR 50.55a(g) (5) (iii). Two types of justifications are provided. The first are general in nature and pertain to requirements found to be impractical for all valves. The second type is used to justify code exceptions for specific valves.
Code exceptions are numbered and referenced by number on the Valve Test Program Tables.
B.
VALVE TEST PROGRAM TABLE FORMAT 1.
Valve Number. Unique number assigned to each valve.
2.
Class.
AS!.E Class.
3.
Coordinates. Location on the ISID where the valve is found.
4.
Valve Category. Valve Category as defined in Subsection IWV-2200.
5.
Passive. An
'X' in this column indicates that a valve is passive as defined in Subsection IWV-2100. All other valves are active valves as described. Those valves mechanically I
constrained to prevent changing positions are designated l
as
'L' in the Test Requirement Column. Those valves whose position is controlled by plant administrative procedures only are designated as
'P' in the Test Requirement Column.
i 1
II-l
6.
Size.
Nominal diameter of valve.
7.
Valve Type.
The following is a list of the type of valve with the code used in the Valve Test Pro-gram Tables'to reflect the valve type.
o AN - Angle Valve e PG - Plug e BF - Butterfly e RD - Rupture' Disk.
RG - Regulating e BL - Ball e
e CK - Check e RL - Relief SC - Stop Check e DA - Diaphragm e
GA. ' Gat'e[
'e SK - Spring Check j
e e GL - Globe o TW - Threa Wayi 8
e ND - Needle
- 8.
Actuator Type.
The following is a list of the type of operator used to change the valve position with the code used in the Valve Test Program Tables to reflect the operator type.
e AO - Air Operator e MA - Manual Operator
~'-
o MO - Motor Operator e SA - Self Actuated e SO - Solenoid Operator HO - Hydraulic Operator e
9.
Normal Position. The following is a list of valve positions during normal operation and the code used in the Valve Test Program Tables to reflect that position.
o OP - Open e CL - Closed e ID - Locked Open e LC - Locked Closed e LT - Locked Throttled e TH - Throttled e -- - Valve position determined by other system para-meters as in the case of check valves.
- 10. Test Requirement. This column indicates the Code test requirements which apply to the valve. The following
,is a list of the codes used in the Valve Test Program Tables with the definition of what the code reflects.
e i
II-2
S - Valve shall be exercised to the position required e
to fulfill its function.
Category C check valves will be verified for forward flow, reverse flow, or both forward and reverse flow depending on the safety related function of the valve.
Valves with remote position indicators, which are used to verify valve exercising or timing will have their remote position indicators verified in accordance with Section XI, Subsection IWV-3300.
e F - Valve with fail-safe actuator to be tested by observing the operation upon loss of actuator power.
e T - Valve stroke time to be measured.
e R - Safety and relief valves set points to be tested in accordance with ASME PTC 25.2 - 1976, e D - Explosive actuated valves or rupture disk tested in accordance with IWV-3610 or IWV-3620.
e L - Valve whose position is controlled by the use of physical constraints such as padlocks or seals.
P - Valve whose position is controlled by the use of e
administrative procedures only, 11.
Code Exception. If the valve is being tested in accordance
'with Section XI requirements, this column will be blank.
However, for valves which the Section XI requirements have been found to be impractical, a reference number is entered in the column. This reference number is addressed in Section
'D' with a complete explanation of the specific exception and justification for that exception.
12.
Alternate Testing.
If the valve is being tested in accordance with Section XI requirements, this column will be blank.
However, if the Section XI testing requirements have been found to be impractical for' a valve, this column presents the testing that will be performed in lieu of the Section XI specified test. The coding used for this column is the same as for the Test Requirement Column, see Item 10.
II-3
e 13.
Test Frequency. The codes used in this column indicate the plant operational status that' must be achieved before a particular valve can be safely terted. For simplicity only the three codes are used.
e Q - Quarterly Valves in this category can be tested quarterly during normal operation.
(Technical Specification Modes 1 through 4).
i 9
4 e C - Cold Shutdown Testing of valves in this category must be deferred until cold shutdown in order to avoid possible adverse opera-tional or safety situations.
(Technical Specification Mode 5).
Inservice valve testing is defined as: Valve testing will commence as soon as possible but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching cold shutdown conditions. Valve testin:g will proceed in a normal manner until all testing is complete or the plant is ready to return to power.
A completion of all valve testing is not a prerequisite to return to power and any testing not completed at the end of one cold shutdown will be performed during subsequent cold shutdowns, starting from the last test performed at the previo*s cold shutdown, to meet u
the code specified testing frequency. Cold shutdown conditions are defined per the Davis-Besse Technical Specifications.
e R - Refueling Testing of valves in this Category must be deferred until the plant is in a refueling interval in order to avoid possible adverse operational or safety situa-tions. This. designation is also usud for passive valves to indicate that valve position is administra-tively controlled.
(Technical Specification Mode 6.)
14.
Maximum Stroke Time. This column provides the limiting value of full stroke time for power operated valves.
15.
Remarks. This column is provided for pertinent informa-tion as appropriate.
II-4
C.
VALVE PROGRAM TABLES This section provides a tabulation of all safety related valves, both those valves that are tested in accordance with the require-ments of Subsection IWV of the ASME Boiler and Pressure Vessel Code, 1977 Edition, and Addenda through Summer 1978 Addenda and those valves for which the Code requirements have been found to be impractical. A set of Valve Program Tables is provided for each IEID. These sets are arranged sequentially by ISID number.
4+
0
'II 5
DAVIS-BESSE NUCLEAR POWER STATION UNIT NO, 1 Page 1 of 2 VALVE TEST PROGRAM System MAIN STEAM Drawing No.
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~ ' ~ ~ DAVIS-BESSE NUCLEAR POWER STATION UN.IT_ NO._,1 PCga 7
of 8 VALVE TEST PROGRAM System SERVICE WATER Drawing No.
041 Rev. 26 a
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Remarks 05 #$ e$ 33
- $" 'E V21ve Number A
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- "ONE PUMP IS AN INSTALLED SPARE AND NOT TESTED QUARTERLY.
TWO PUMPS ARE IN SERVICE DURING NOR!!AL OPERATION AND ONLY THE CHECK VALVE ASSOCIATED WITl! Ti!E OPERATING PUMPS.WILL BE TESTED.
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D.
CODE EXCEPTIONS This section provides justification for the exceptions taken to code test requirements as provided for in 10 CFR 50.55a(g) (5) (iii).
Each code exception $s identified by a unique number and identifies the valve (s) for which the Code exception is being taken.
The specific Code test requirement found to be impractical is defined and the basis for exclusion from Code requirements is presented.
Any testing performed in lieu of Code requirements is specified.
Two types of justifications are provided. The first are general in nature and pertain to Code requirements found to be impractical for all valves.
The second type is used to justify Code exceptions for specific valves. Code exceptions are numbered and referenced by number on the Valve Test Program Tables for specific valves.
1.
General Code Exceptions a.
Code Exception Number G-1 e Components: All safety related power operated va.lves.
e Function: ' Power operated valve timing requirements.
- Class: All e Test Requirement: Section XI, IWV-3413(b)
"The stroke time of power-operated valves shall be measured to the nearest second or 10% of the maximum allowable stroke time, whichever is less, whenever such a valve is full-stroke tested."
e Basis for Exception: For valves *ith stroke times less than 10 seconds - this would require measuring stroke times to within a fraction of a second.
Velve timing is performed using a stop watch either by directly observing valve movement or by observing remote position indicators. Neither method can be relied upon to yield results with accuracy of less than a second.
e Alternate Testing: The stroke tina of all power-operated valves shall be measured to the nearest second.
II-57 4
b.
Code Exception Number G-2 o Components: All safety related power operated valves.
e Function: Power operated valve timing requirements.
e Class: All e. Test Requirements: Section XI, IWV-3413 (c)
"If an increase in stroke time of 25% or more from the previous test for valves with stroke time greater than 10 seconds, or 50% or more for valves. with stroke times less than or equal to 10 seconds, is observed, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed."
e Basis for Exception: Operating experience has indicated that individual valve timing is influenced by many factors such as changes 3' temperature, humidity, fluxuation in power source, limit switch adjustment, etc.
Because of these outside factors timing data can exhibit scatter which exceeds the Code criteria but which is still less,than the maximum full stroke time.
Lacking in the Code requirements is any provision for verifying test results prior to placing the valve on an accelerated test frequency.
The present Code does not require any action for valves whose stroke time suddenly decreases a signi-ficant amount. Any marked decrease outside the nor-mal band of stroke times could indicate a major mechanical problem, such as the power operator being disconnected from the valve. Any significant decrease in stroke time should be investigated to determine if the valve and power actuator are capable of performing their function.
e Alternate Testing: Maximum full stroke times shall be established for each valve based upon required valve response time to assure adequate system re-sponse for safety related functions. Valve test times will be acceptable if less than the maximum allowed. If test time exceeds the maximum allowed, the valve will be immediately retested and corrective action taken as appropriate. Any significant de-crease in valve test time will immediately be inves-tigated and appropriate corrective action taken.
II-58
2.
Specific Code Exceptions a.
Code Exception Number 1 o Components: MS100, MS101, o Function: Main Steam Isolation Valve, o Class:
2 Test Requirements: Quarterly stroking.
e e Basis for Exception: Cycling valve during normal operation results in loss of main steam to turbine, which causes a reactor trip.
e Alternate Testing: Valve will be full stroke tested during cold shutdown. Partial stroking during normal operation is not possible because partial stroking can only be performed locally at the valve.
If valve was to inadvertently fail close during test,.the main steam reliefs would lift. The local test station is located in the area which fills with steam from the main steam reliefs. Entry into area is strictly controlled during operation. No remote partial stroke capability is available, b.
Code Exception Number 2 e Components:
SW3, SW4 e Function: Service water check valve to auxiliary feedwater pump suction.
e Class:
3 Test Requirements: Forward Flow Stroking.
e e Basis for Exceptions: Forward flow cycling would introduce service water into the feedwater system which would damage the steam generator and is pre-cluded by plant operating procedure.
e Alternate Testing: NONE.
II-59 e
e.
c.
Code Exception Number 3 e Components:
AF5'99, AF608.
e Function: Auxiliary feedwater isolation valve to the steam generator.
- Class:
2 e Test Requirements: Quarterly stroking.
e Basis for Exception: Failure of valve in closed position daring test would result in total loss of auxiliary feedwater to the steam generator.
A ' subsequent loss of main feedwater would cause extensive damage to the steam generator.
e Alternate Testing: Valve will be full stroke tested at cold shutdown. Valve design precludes partial stroke testing during normal operation.
d.
Code Exception Number 4 e Components: AF39, AF43, AF72, AF73, AF74, AF75 e Function: Auxiliary feedwater check valves to the steam generators e Class:
3 e Test Requirements: Quarterly forward flow stroking.
e Basis for Exception: Cycling valve would require injection of auxiliary feedwater into the steam generator, which would thermal shock the auxiliary feedwater nozzles.
e Alternate Testing: Valve will be forward flow cycled during refueling when the steam generator is cold.
Valve can not be partial stroked during normal operation without. injecting auxiliary feedwater into the steam generator.
e.
Code Exception Number 5 e Components: FW601, FW612 e Function: Main feedwater isolation valve to the steam generator.
II-60 g
4 e Class:
2 e Test Requirements: Quarterly stroking.
\\
Basis for Exception:
Cycling valve during normal e
operation would cause loss of main feedwater to steam generator, which would cause reactor trip.
Alternate Testing:
Valve will be full stroke e
tested at cold shutdown. Valve design precludes partial stroke testing during normal operation.
f.
Code Exception Number 6 e Components:
IA501 e Function:
Instrument air to containment isolation check valve.
e Class:
2 e Test Requirements: Quarterly reverse flow stroking, Basis for Exception: To verify reverse flow closure o
requires entry into the containment. Entry into the containment during power operation is generally precluded by plant operating procedure. Entry during power operation is strictly controlled and i
limited to entry only when absolutely necessary.
(As per Special Order Number 84-4, Revision 4, dated January 8, 1979.)
Alternate Testing: Valve will be full stroke tested e
at cold shutdown.
System operation precludes partial stroke testing during normal operation.
g.
Code Exception Number 7 e Components:
SA502, SA2010 e Function: Breathable air to containment isolation
- valves.
e Class:
2 e
Test Requirements:. Quarterly stroking.
e Basis for Exception: Valve provides breathable air inside containment which must be available during normal operation and cold shutdown for entry into the containment.
Cycling could endanger plant personnel.
II-61 c
4 e Alternate Testing: Valve will be full stroke tested at refueling when the system can be iso-lated without endangering plant personnel.
Valve design (SA2010) and system operation (SA502) preclude partial stroking during normal operation.
h.
Code Exception Number 8 e Components: CV117, CV186, CV187, CVl91, CV209, CV210 e Function: Hydrogen dilution air to containment check valves.
I e Class:
2 and 3 e Test Requirements: Quarterly forward flow stroking.
e Basis for Exception: Cycling can only be performed by injecting air from the hydrogen dilution blowers into the containment.
This air must be purged from the containment to the environment.
'.s air must be purged from the containment to the environment.
Purge time is limited to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year during normal operation. Testing could cause excecsive purging with resulting increase in releases to the environment.
e Alternate Testing: Valve will be cycled at cold shutdown.
No partial stroking is possible during normal operation without injecting air into the containment.
i.
Code Exception Number 9 3
e Components: CV5080 through CV5089 e Function: Containment vacuum breaker valves.
e Class:
2 e Test Requirements: Quarterly forw.rd flow stroking.
e Basis for Exception: Forward flow cycling can only be performed by entering the annular area between the containment and shield building and verifying freedom of valve by hand. Entry to this area during power operation is strictly controlled and limited to entry only when absolutely necessary. '
(As per Special Order No. 84-4, Ret'sion 4, dated January 8, 1979).
II-62 y
e Alternate Testing: Valve will be verified for freedom of valve movement at cold shutdown. Valve design precludes partial stroking during normal operation..
- j. Code Exception Number 10 e Components: CV124, CV125 o Function: Containment gas analyzer isolation check
- valve, e Class:
2 e Test Requirements: Quarterly reverse flow stroking.
e Basis for Exception: To verify reverse flow closure requires entry into the containment. Entry into the containment during norn'l operation is generally pre-cluded by plant operating procedure.
Entry during power operation is strictly controlled and limited to entry only when absolutely necessary. (As per Special Order Number 84-4, Revision 4, dated January 8,1979).
Alternate Testing: Valve will be full stroke tested e
at cold shutdown. System operation precludes partial stroke testing during normal operation.
k.
Code Exception Number 11 l
e Components: RC10 e Function: Pressurizer spray control.
e Class:
1 Basis for Exception: Failure of valve in the closed e
position would result in loss of reactor coolant system pressure control, which is required during normal operation.
e Alternate Testing: Valve will be full stroke tested during cold shutuown. Valve design precludes partial stroke testing during normal operation.
II-63
1.
Code Exception Niunber 12 o Components: RC2A e Function: Pressurizer pressure control valve e Class: 1 Test Requirements: Quarterly stroking and timing.
e e Basis for Exception:
Valve is in normal operation to automatically control the pressurizer pressure.
Valve is interlocked to the pressurizer which auto-matically controls valve position. Valve design and operating modes preclude valve timing.
Alternate Testing: Valve is effectively part e
stroked during normal operation in response to pressurizer conditions. Valve will be full stroked at refueling during performance of plant procedure PT5164.02 which also verifies pressure set point.
m.
Code Exception Number 13
~
e Components: MU33 e Function: Normal makeup water to the Reactor Coolant System o Class:
2 o Test Requirements: Quarterly stroking Basis for Exception: Failure of valve in the closed e
position during test would result in total loss of normal makeup to the reactor coolant system. Makeup is required during normal operation and cold shutdown.
l e Alternate Testing: Valve will be cycled at refueling 1
when makeup water is not required. Valve design pre-cludes partial stroking during normal operation.
II-64 e
n.
Code Exception Number 14 o Components:
MU242," MU243, MU244, MU245 o Function: Reactor coolant pump seal water check valve.
e Class:
2 Test Requirements: Quarterly reverse flow stroking o
Basis for Exception:
Reverse flow cycling during e
normal operation or cold shutdown would require stopping reactor coolant pump seal cooling water flow. This would damage reactor coolant pump _
seals and is not permitted by plant proced rc.
e Alternate Testing:
Reverse flow stroking will be cycled at refueling.
System operation precludes partial stroke testing during normal operation.
~
o.
Code Exception'!Iumber 15 e Components: MU66A, MU66B, MU66C, MU66D, MU59A, MU59D, MU38 e Function: Reactor coolant pump seal water isola-tion valve e Class: 2 Test Requirements: Quarterly stroking e
e Basis for Exception: Cycling valve during normal operation would stop reactor coolant pump seal cooling water flow. This would damage reactor coolant pump seals and is not permitted by plant operating procedure.
e Alternate Testing: Valve will be cycled at re-fueling. Valve design precludes partial stroke testing during normal operation.
f s
II-65 C
4 p.
Code Exception Number 16 e Components:
DH9A, DH9B e Function: Containment emergency sump isolation valve.
i e Class:
2 Test Requirements: Quarterly stroking e
Basis for Exception: Cycling valve would introduce e
borated water from the borated water storage tank directly into the containment emergency sump. Valve is interlocked with DH7A (DH7B) and can only be tested when the borated water storage tank can be isolated.
e Alternate Testing: Valve will be cycled at refueling when the borated water storage tank can be isolated.
valve can not be partial stroke tested during normal operation without injecting borated water into the containment emergency sump.
q.
Code Exception Number 17 e Components:
CF28, CF29 e Function: Core flood tank isolation check valve e Class:
1 e Test Requirements: Quarterly forward flow stroking e Basis for Exception: Forward flow cycling can not be performed during normal operation or cold shutdown when the reactor coolant system is filled and pres-surized to pressure greater than that of the core flood tank.
e Alternate Testing: Valve will be tested at refueling when the contents of the core flood tank can be partially dumped into the reactor coolant system while monitoring core flood tank level.
II-66 9
l r.
Code Exception Number 18 e Components: CF30, CF31, DII76, DH77 e Function:
Low pressure injection check valve e class:
1 e Test Requirements: Quarterly forward stroking Basis for Exception:
Forward flow cycling can only
> e be performed by injecting water from the decay heat system into the reactor coolant system. This can only be done at cold shutdown when reactor coolant system pressure is low enough to permit injection.
e e Alternate Testing: Valve will be forward flow cycled at cold shutdown. System operation pra-cludes partial stroke testing during normal operation when reactor coolant system pressure
~
is greater than the decay heat system design pressure.
s.
Code Exception Number 19 e Components: IIP 48, HP49, HP50, HP51, HP56, IIP 57 HP58, HP59 e Function:
High pressure injection check valve.
e Class:
1 Test Requirements: Quarterly forward flaw stroking e
e Basis for Exception: Valve can only be cycled by high pressure injection flow.
High pressure injec-tion during normal operation or cold shutdown could introduce cold water into the significantly hotter reactor coolant system. This would thermal shock the high pressure injection nozzle. Additionally high pressure injection during cold shutdown could subject the reactor coolant system to pressures higher than allowed in the cold shutdown mode, e Alternate Testing: Valve will be forward flow cycled at refueling. System operation precludes partial stroke testing during normal operation.
II-67 c
t.
Code Exception Number 20 Co,mponents:
C.F15, CF16, RC113 e
e Function: Nitrogen supply to core flood tank isolation check valve e Class:
2 Test Requirements: Quarterly reverse flow e
stroking Basis for Exception:
Verification of reverse flow
]
e stroking venting line downstream of valve. Venting line has the potential for release of airborne radionuclides, which could cause local inhalation dose problems.
- Alternate Testing: Valve will be reverse flow cycled at refueling.
System operation precludes stroke testing during normal operation.
u.
Code Exception Number 21 e Components: CCl411A, CCl411B, CCl407A, CC1407B e Function: Components cooling water isolation valve e Class:
2 e Test Requirements: Quarterly stroking e Basis for Exception:
Cycling valve during normal operation or cold shutdown requires shutting off cooling water to the reactor coolant pumps, which would cause extensive damage to the pumps.
Cooling water to the reactor coolant pumps is re-quired except at refueling.
e Alternate Testing:
Valve will be full stroke tested at refueling. Valve design precludes partial stroke testing during normal operation.
II-68
v.
Code Exception Number 22 e Components: CC1460 o Function: Component cooling water isolation valve e Class:
3 e Test Requirements: Quarterly stroking e Basis for Exception: Cycling valve during normal operation or cold shutdown requires shutting off cooling water to the makeup pump coolers which could cause damage to the pumps. -Cooling water to the pumps can only be shut off during cold shutdown.
e Alternate Testing: Valve will be full stroke tested at cold shutdown. Valve design precludes partial stroke testing' during normal operation.
~
w.
Code Exception Number 23 e Components: CC1567A, CC1567B e Function: Component cooling water isolation valve e Class:
2 e Test Requirements: Quarterly stroking e Basis for Exception: Cycling valve would require shutting off cooling water to the control rod drives which can only be done when electrical power is re-moved from the control rod drives at refueling, e Alternate Testing: Valve will be full stroke tested at refueling. Valve design precludes partial stroke testing during normal operation.
II-69
.=
x.
Code Exception Number 24 e Components:
SW57 e Function:
Service water isolation check valve
?
e Class:
3 e Test Requirements: Quarterly. reverse flow stroking Basis for Exception:
Reverse flow cycling requires e
stopping cooling water flow through the turbine plant cooling water heat exchangers which could result in extensive equipment damage.
e Alternate Testing: Valve will be reverse flow cycled at refueling when cooling water is not required.
System operation precludes partial stroke testing during normal operation.
h
[
II-70
VALVE TYPE ACTUATOR TYPE TEST FREQUENCY Code D,efinition Code Definition Code Definition AN Angle Valve AO Air Operator Q
Quarterly BF Butterfly MA Manual Operator C
Cold Shutdown BL Ball MO Motor Operator R
Refueling CK Check SA Self Actuated DA Diaphragm SO Solenoid Operator GA Gate HO Hydraulic Operator GL Globe ND Needle PG Plug RD Rupture Disk RG Regulating RL Relief SC Stop Check SK Spring Check TW Three Way NORMAL POSITION Co'dh-Definition OP Open CL Closed LO Locked Open Ir Locked Closed LT Locked Throttled TH Throttled Valve position determined by other system parameters as in the case of check valves.
TEST REQUIREMENT Code Definition S
Valve shall be exercised to the position required to fulfill its function.
F Valve with fail-safe actuator to be tested by observing the operation upon loss of actuator power.
T Valve stroke time to be measured.
~
R Safety and relief valves set points to be tested in accordance with ASME PT 25.2 - 1976.
D Exposive actuated valves or rupture disk tested in accordance with IWV-3610 or IWV-3620.
L Valve whose position is controlled by the use of physical constraints such as padlocks or seals.
P Valve whose position is controlled by the use of administrative l
procedures only.
Figure 1.
Valve Test Program Codes t
ra-m
SECTION III WELD, SUPPORT, COMPONENT AND BOLTING INSPECTION PROGRAMS TABLE OF CONTENTS Page A.
PROGRAM
SUMMARY
III-l B.
WELD, SUPPORT AND BOLTING INSPECTION PROGRAM TABLES FORMAT III-2 C.
WELD, SUPPORT AND BOLTING INSPECTION PROGRAM TABLES III-6 l
1.
Weld and Support Inspection Program Tables. III-7 2.
Component Nondestructive Examination Tables'.
III-35 3.
Bolting Nondestructive Examination Tables.
III-57 1
D.
CODE EXCEPTIONS III-66 I
III.
WELD, SUPPORT AND BOLTING INSPECTION PROGRAM A.
PROGRAM
SUMMARY
The Weld, Support and Bolting Inspection Program identifies the nondestructive examination (tmE) requirements for all piping and component welds, supports and bolting within the boundaries of safety related systems, both thcae welds, supports and bolting examined in accordance with the requirements of Subsection IWE, IWC, or IWD, as appropriate, of the ASME Boiler and Pressure vessel Code, 1977 Edition and Addenda through Summer 1978 Addenda and those welds, supports and bolting for which the Code require-ments have been found to be impractical. The Weld, Support and 1olting Inspection Program will be applicable for the remainder of the 120-month interval, which started on June 27, 1977 after which the Program will be reviewed and updated, as appropriate, with the Edition of the Code and Addenda in effect not more than 12 months prior to the start of the next 120-month interval. All examinations shall be conducted in accordance with Inspection Program B of Section XI.
The Weld, Support and Bolting NDE requirements are presented in Section
'C' by coded Weld and Suppo? t Inspection Program Tables, Component Nondestructive Examinatior. Tables and Bolting Nonde-structive Examination Tables. The codes used for these Tables are defined in Section 'B'. The Weld and Support Inspection Program Tables of Section
'C' are arranged by system. Component Nondestructive Examination Tables and Bolting Nondestructive Examination Tables are arranged by Class and System.
Section
'D' provides justificat'.u.' for exceptions take.3 to Code examination requirements as prtvF A for in 10 CFR 50.55a(g) (iii).
All Class 3 welds and a vports will be inspected to the require-ments of Table IWD-2500-1 of the Code.
The examination will be conducted to the extent practicable within the limitations of the component, or system portion, design and geometry.
l III-l d
t
4 B.
WELD, SUPPORT AND BOLTING INSPECTION PROGRAM TABLE FORMATS 1.
The Weld and Support Inspection Tables are coded as follows:
a.
Subsystem / Description. A brief description of the line segment under consideration.
b.
Item Number. A unique, sequential number assigned to each line segment.
c.
Line Number. A non-unique number used to icentify the line.
The first set of numbers show the nominal piping diameter in inches.
The second letter shows the material of con-struction as follows:
e B - carbon steel e C - stainless steel e D - copper e R - carbon steel radwaste o S - stainless steel radwaste d.
ISID.
The Inservice Inspection Drawing on which the line segment is located, c.
Coordinates. The location on the ISID where one end of the line segment is found.
f.
Normal Operating Pressure.
The normal operating pressure in
- psig, g.
Normal Operating Temperature.
The normal operating temperature in "F.
h.
Material in <4 Inches. A
'CS' indicates that the line segment is exempted from NDE per IWC-1220(c), <4 inches nominal pipe size. This exemption is used for ferritic material only.
Austenitic naterial is exempted based upon <2-1/2 inches nominal pipo size. This exemption is applied to class 2 piping only. Other Code Exemption used in developing the Program were:
IWB-1223 (b) - Class 1 piping <1 inch nominal pipe size e
e IWC-1220 (a) - Class 2 piping maintained under static co adi-tions of at least 80 percent normal operating pressure.
I III-2
B.
WELD, SUPPORT AND BOLTING INSPECTION PROGRAM TABLE FORMATS (continued) 1.
Thickness. The nominal pipe wall thickness in inches.
j.
Weld Inspection.
The numbers in each column indicate the number of welds in the line segment which will be inspected by that method.
VOL & SUR/VOL - The welds will be inspected by either e
volumetric and surface examination (nominal pipe thickness
<1/2 inch) or by volumetric examination only (nominal pipe thickness >3/8 inch but <1/2 inch).
SUR - The welds will be inspected by surface examination, e
PRT - Pressure Test per IWB-5000 or IWC-5000, as appli--
o cable. This is only used when no other weld examination is applied.
F/T - Flow Test at 100 percent mi imum rated flow. This e
is only used when no other weld exam *..;' ion is applied.
A/T - Air Test of open ended, normally dry pipe. This is e
only used when no other weld examination is applied.
k.
Support Inspection. The numbers in each column indicate the number of supports which will be inspected by that method.
e SUR & VT The integral attachment weld will receive a surface examination and the complete support will receive a VT-3 visual examination.
e SUR & VT The integral attachment weld will receive a surface examination and the complete support will receive a VT-4 visual examination.
VT The support which has no integral attachment weld and will receive a VT-3 visual examination.
l VT The support which has no integral attachment weld e
and will receive a VT-4 visual examination.
m.
Remarks. This column is provided for pertinent information as appropriate.
ITI-3
B.
WELD, SUPPORT AND BOLTING INSPECTION PROGRAM TABLE FORMATS (continued) 2.
The Component Nondestructive Examination Tables are coded as follows:
a.
Component Information. Consists oft e Name - The name of the component Number - The unique number assigned to the component e
e Drawing Coord. - The location on the ISID where the component is located Design Operating F essure - The design maximum operating e
pressure in psig.
DesignOperatingTemperature-Thedesignmaximumoperating e
temperature in F.
b.
W/S.
A 'W' indicates that the line refers to a teld. An
'S' indicates that the line refers to a support.
c.
No,.
Indicates the number of identical items referred to.
d.
Component Dra_ wing Number. The number of the drawing showing the component.
e.
Coord. The location of the wold or support on the component drawing.
f.
Section XI Item No./ Cat.
The item number and category as given in Table IWB-2500-1 or Table IWC-2500-1.
g.
Section/ Base Material Thickness. The thickness of the welded section or the support base material in inches, h.
Inspection.
The inspection applied to the weld or support.
e VOL - volumetric examination e SUR - surface examination e VT VT-2 visual examination 1.
Note No.
The number of any applicable note. Notes art-shown at the bottom of the page.
III-4
B.
WELD, SUPPORT AND BOLTING INSPECTION PROGRAM TABLE FORMATS (continued) 3.
The Bolting Nondestructive Examination Tables are coded as follows:
a.
Description. A brief description of the item.
b.
Section XI Item No./ Cat..The item number and category as given in Table IWB-2500-1 or Table IWC-2500-1.
c.
Size. The nominal bolt size in inches.
d.
No.
The number of identical items referred to.
e.
Component Drawing Number.
The number of the drawing of the overall component.
l f.
Inspection. The inspection applied to the item.
e VOL - volumetric examination e SUR - surface examination
' ~~
e VT VT-1 visual examination g.
Note Number. The number of any applicable note.
Notes are shown at the bottom of the page.
III-5
,-.... - ~
C.
WELD, SUPPORT AND BOLTING INSPECTION PROGRAM TABLES i
a j
1, weld and Support Inspection Program Tables.
F This section provides a summary of all piping welds and supports within the boundaries 'of the safety related systems, examined i
in accordance with subsection IWB or IWC, as appropriate, of the l
ASME Boiler and Pressure vessel Code, 1977 Edition, and Addenda through Summer 1978 Addenda.
The Tables are arranged by System.
1 III-6
WELD AtlD SUPP0E SYSTEll: AUXILIARY FEEDWATER SYSTEM FIRST SEISMIC SUPPORT PAST H
e C 2)
BOUNDARY IS I!;CLUDED IN COUNT.
N U
UN s
des ge$
ITEM LIflE E
5$$
e$S I
SUBSYSTEM /DESCRIPT10fl flUMBER flUMBER ISID 8
8S$
8SU FROM VALVE AF599 TilRU PEN. 35 TO 35-0 6" EBB-4 007 F-2 990 90 STEAM GENEPATOR 1-2 FROM VALVE AF608 TIIRU PEN. 36 TO 36-0 6" EBB-4 007 F-12 990 90 STEAM GENERATOF. 1-1 e
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T lllSPECT!0fl PROGRN1 W
CLASS 2
PAGE i 0F 1 WELD IflSPECTI0ff SUPPORT iflSPECTI0fl A
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0.280 1
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'I!;SPECT MIllIMUM OF 10% OF WELDS AND 25% OF SUPPORTS PER CODE.
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III-7
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WELD Af!D SUPPORT SYSTEll:
CoxPor!EliT COOLI!1G SYSTE!!
O Y
FIRST SEISMIC SUPPORT PAST Tile g
g gg pg pg DOUllDARY IS It!CLUDED Ill THE COUtiT.
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ITEM LIf1E O
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SUBSYSTEM /DESCRIPTIOft fiUMBER flUMBER ISID 8
8SE ESI E
FROM VALVE CC1411B TilRU PEtt 3 s 3-0 12"IIBB-1 036 F-2 60 95 VALVE CCl411A
~
3-1 10"IIBB-1 036 G-3 60 95 3-2 12"11BB-1 036 G-3 60 95 FROM VALVE CC1407A TliRU PEli. 4&
4-0 12"IIBB-12 036 C-6 30 175 VALVE CC1407B 4-1 10"lIBB-12 036 C-9 30 175 4-2 12"11BB-12 036 C-9 30 175 J.
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IllSPECTI0fl PROGRN1 I
CLASS 2
PAGE 1 0F L WELD IftSPECT10fl SUPPORT lilSPECTI0fl W
On 5
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55 t
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Ti bb N$
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$N
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N REMARKS INSPECT ALL WELDS AND 1
1 0.375 ALL SEISMIC SUPPORTS DURING PRESSURE TEST.
INSPECT 0.365 ALL MINIMUM OF 25% OF SUPPORTS PER CODE.
0.375 ALL 0.375 ALL 1.
1 INSPECT ALL WELDS AND SEISMIC SUPPORTS DURING 0.365 ALL PRESSURE TEST.
INSPECT MINIMUM OF 25% OF SUPPORTS PER CODE.
0.375 ALL 1
INSPECT MINIMUM OF 25% OF 2
1 SUPPORTS PER CODE.
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III-8
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CONTAINMENT AND PENETRATION ROOMS O
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ESE ES" FROM NRV(1) TilRU PENETRATION 8 8A-0 8"HBB-19 029B B-6 ATM 120 (8A-8J) TO CONTAINMD3T VESSEL 8B-0 8"IIBB-19 029B B-6 ATM 120 8C-O 8"IIBB-19 029B B-6 ATM 120 BD-0 8"ItBB-19 029B B-6 ATM 120 8E-0 8"!!BB-19 029B B-6 ATM 120 8F-0 8"IIBB-19 029B B-6 ATM 120 8G-0 8"IIBB-19 029B B-6 ATM 120 8 11 - 0 8"IIBB-19 029B B-6 ATM 120 8I-O 8"IIBB-*19 029B B-6 ATM 120
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FROM BLIND FLANGE Tl!RU VALVE 17-0 8"IICB-44 029B G-5 ATM 120 CV343 MID PENETRATION 17 TO 8"HCB-49 029B G-5 ATM 120 DLIND FLANGE 8"IIBB-20 029B G-5 ATM 120 l
FROM REDUCER DOWNSTREAM OF AND 51-0 4"IIBB-16 029A 11 - 5 18 150 TIIRU PENETRATION 51 TO SUPPOIU 29-IIBB-16-II5 STEAM GENERATOR CIIEMICAL CLEANING 59-0 8"IICD-43 007 E-13 ATM
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LINE - PENETRATION 59 l'.
FROM SUPPORT 29-IIBC-73-II10 Ti!RU 69-0 4"HBB-15 029A 11-11 18 150 PENETRATION 69 TO SUPPORT f
29-IIBB-15-Il2 1
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CLASS 2 PAGE 1 0F 2-WELD IflSPECTI0ff SUPPORT IflSPECTI0fl 0
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10 ItiSPECT MIt3IMUM OF 25% OF WELDS PER CODE. NO SEISMIC SUPPORTS ON TIIESE LINES.
1 0.148 1
0.148 1
1 0.322 2
4 1
INSPECT MI!3IMUM OF 25% OF WELDS AND SUPPORTS PER CODE WELDS EXEMPT PER IWC-1220(c CS 0.237 1
INSPECT MINIMUM OF 25% OF SUPPORTS PER CODE.
INSPECT MINIMUM OF 25% OF 1
0.148 2
WELDS AND SUPPORTS PER CODE 1
1 CS 0.237 INSPECT MINIMUM OF 25% OF SUPPORTS PER CODE.
N III-10
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120 STREAM FROM VALVE CV5007 Ti!RU FDIETRATION 34 TO FIRST SEISMIC SUPPORT DOWNSTREAM OF VALVE CV5008 FROM SUPPORT 29-IIBC-73-II6 Ti!RU 67-0 4"IIBB-15 029A 11 - 1 1 18 150 CS
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35, Y, AND 2 25-2 8"GCB-5 034 D-9 220 120 25-3 8"IICD-8 034 C-3 60 120 25-4 8"IICB-8 034 C-3 60 120 TEST RETURN LINE FROM 8"GCB-5 LINE 25-1A 8"IICC-38 034 D-6 5
120 L
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FROM CONTAINMENT SPRAY PUMP 26-0 6"GCB-5 034 D-9 220 120 P56-1 DISCIIARGE TIIRU CONTAINMENT 26-1 8"GCB-5 034 D-9 220 120 SPRAY HEADER 26-2 8"HCB-4 034 D-6 150 120 26-3 8"IICB-8 034 D-3 60 120 26-4 8"IICB-8 034 D-3 60 120 TEST RETURN LINE FROM 8"GCB-5 26-1A 8"GCB-5 034 D-6 220 120 LINE TIIRU VALVE CS36 TO SUPPORP 34-IICC-38-II27 INCLUDING WELD FWl6B l
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NOTE 10.
SYSTEM EXEMPTED FROM MDE DUE TO SiSTEM BEING 80% STATIC i
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.FROM DECAY IIEAT PUMP P42-2 DIS-27-2 10"CCB-6 033 B-6 ATM 200 OIARGE TIIRU PDIETRATION 27 TO 27-3 10"CCB-6 033 B-3 ATM 200 REACTOR VESSEL 10"CCA-6 033 B-3 2155 280 27-4 14"CCA-6 033 B-3 2155 280 FROM VALVE DH830 TO 10"GCB-10 LINE 27-1A 8"GCB-10 033 F-10 410 200
'FROM VALVE Dill 26 TO 8"GCD-10 LINE 27-1A1 8"GCB-10 033 F-10 410 200
/
y FROM BWST TO CAP ST-0 24"l!CB-2 033 B-12 25 120 1
FROM 24"HCB-2 LINE THRU VALVES DII7A ST-1 14"IICB-2 033 C-12 25 120 AND DI!82 TO REDUCER INCLUDING WELD EMl FROM 24"HCB-2 LINE THRU VALVES ST-2 14"IICD-2 033 C-12 25 120 l
DlI78 AND Dil81 TO REDUCER FROM REDUCER UPSTREAM OF VALVE 30-3 18"HCB-1 033 K-9 ATM 120 Dl!82 TO' TEE FROM 18"IICB-1 TEE THRU VALVE 30-6 18"HCB-1 033 K-9 ATM 120 DH2734 TO DECAY llEAT PUMP P42-2 30-7 18"HCB-8 033 K-9 45 260 30-8 12"GCD-8
.033 G-9 45 260 FROM DECAY !! EAT PUMP P42-2 DIS-27-0 10"GCB-1 033 G-10 410 280 OIARGE TIIRU PENETRATION 27 TO 27-1 10"GCB-10 033 G-ll 410 280 REACI'OR VESSEL HEAT EXCIIANGER BYPASS 27-0A 6"GCB-10 033 G-ll 410 200 6"GCB 033 G-11 410 280
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6 INSPECT MINIMUM OF 25% OF 9
6 WELDS AND SUPPORfS PER CODE.
ALL 0.375 0.188 ALL 0.188 ALL 0.375 ALL 0.375 ALL 0.375 ALL 0.375 ALL 1
0.250 ALL 0.250 ALL 0.134 ALL
.r-0.134 ALL ALL INSPECT ALL WELDS AND SEIS-MIC SUPPORTS DURING FLOW TEST.
i III-15
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l WELD AND SUPPORT SYSTEM: DECAY IIEAT REMOVAL SYSTEM (CONTINUED)
C U
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8SE ES" FROM 10"GCB-10 LINE TIIRU VALVE 27-lF 8"GCD-10 033 B-9 410 200 DII65 TO ANCi!OR 83 8"IfCB-9 033 B-9 100 120 FROM DECAY HEAT PUMP P42-1 DIS-28-2 10"CCB-6 033 E-5 ATM 200 q
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IIEAT EXCIIANGER BYPASS 28-0A 6"GCB-10 033 G-8 410 200 FROM VALVE DII831 TO 10"GCB-10 LINE 28-1A 8"GCB-10 033 F-9 410 200 I
FROM VALVE Dill 28 TO 8"GCB-10 LINE 28-1A1 8"GCB-10 033 F-9 410 200 d
FROM 10"GCB-1O LINE TO VALVE DII66 28-lE 8"GCD-10 033 E-7 410 200 1
FROM REDUCER UPSTREAM OF VALVE 31-3 18"IICB-1 033 J-6 ATM 120
-=
DH81 'IO TEE FROM 18"!!CB-1 TEE THRU VALVE 31-6 18"HCB-1 033 J-6 ATM 120
-c DI!2733 TO DECAY IIEAT :? UMP P42-1 31-7 18"GCB-8 033 J-6 45 260 31-8 12"GCB-8 033 H-6 45 260 FROM DECAY IIEAT PUMP P42-1 DIS-28-0 10"GCB-1 033 11 - 8 410 280
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1 4
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INSPECT MINIMUM OF 25% OF 12 6
WELDS AND SUPPORTS PER CODE.
0.375 ALL 0.375 ALL 0.375 ALL 0.250 ALL 0.250 ALL 0.250 ALL INSPECT ALL WELDS AND SEIS-ALL MIC SUPPORTS DURING FLOW TEST.
k III-16
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WELD AND SUPP0F SYSTEM: HIGH PRESSURE INJECTION SYSTEM 0
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E-5 2155 582 030 FROM 4"CCB-2 LINE TEE TIIRU PENETRA-50-0 2 "CCB-2 033 E-5 2250 120 E
TION 50 TO REACTOR VESSEL 50-1 2 "CCA-2 033/
E-5 2155 582 E
030 FROM IIIGII PRESSURE INJECTION PUMP 19-0 4"CCB-2 033 C-8 ATM AMB S
P58-2 DISCIIARGE TIIRU PENETRATION 19-1 "CCB-2 033 C-6 2250 120 S
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030 FROM 4"CCB-2 LINE TEE TIIRU PENETRA-20-0 2 "CCD-2 033 C-3 2250 120 S
TION 20 TO REACTOR VESSEL 20-1 2 "CCA-2 033/
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030 PROM 14"IICB-2 LINE TIIRU VALVES ST-3 6"IICB-2 033 J-ll 25 120 IIP 10 AND IIP 12 'IO IIIGII PRESSURE ST-4 6"GCB-4 033 E-11 410 180 INJECTION PUMP P58-1 SUCTION INCLUDING WELD IW32 FROM 14"IICD-2 LINE TIIRU VALVES IIPll ST-5 6"liCB-2 033 K-ll 25 120 AND IIP 13 TO IIIGI! PRESSURE INJECTION ST-6 6"GCD-4 033 D-11 410 180 PUMP P58-2 INCLUDING WELD FW27 FROM 4"CCB-2 LINE TIIRU VALVE IIP 26 TC 22-0B 4"CCB-18 033 D-7 ATM AMB St FIRST SEISMIC SUPPORT 33C-CCD-19-H2 FROM 4"CCB-2 LINE TIIRU VALVE IIP 27 IS-0B 4"CCB-18 033 C-7 ATM AMB SE TO FIRST SEISMIC SUPPORT 33C-CCD-19-ill2 Q
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9 T IflSPECTI0tl PROGRAF 1 CLASS 1 & 2' PAGE 1 0F _1 WELD IflSPECTI0t1 SUPPORT If1SPECTI0tl m
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CLASS 1 9
54 19 INSPECT MINIMUM OF 25% OF WELDS AND SUPPORTS PER CODE.
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0.134 ALL INSPECT ALL WELDS AND SEIS-0.134 ALL MIC SUPPORTS DURING FLOW TEST.
0.438 EXEMPT PER IWC-1220(c).
0.438 EXEMPT PER IWC-1220 (c).
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0.120 EXEMPT PER IWC-1220 (c).
0.120 EXEMPT PER IWC-1220 (c).
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FROM VALVE PW601 THRU PENETRATION 37-0 18" EBB-3 007 H-2 990 461
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PAGE 1
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1 0.937 4
2 0.750 6
3 1
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2 2
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1 32 12 6
5
. INSPECT MINIMUM OF 25% OF WELDS AND SUPPORTS PER CODE.
I 4
I l
a 1
f III-20 i
- a I
WELD AtlD S PPORT SYSTEM:
MAIN STEAM SYSTEM - SECONDARY CIDE
]c m
w es e
g 5e 5~
- g ors arm e
Efs EEE dd ITEM LIf1E o
mww ewr r
SUBSYSTEM /DESCRIPTI0li fiUMBER fiUMBER
'ISID 8
8SE ESW f_*
FROM STEAM GENERATOR l-2 THRU 39-0 26" EBB-1 007 B-2 910 594 PENETRATION 39 AND VALVE MS100 39-1 26" EBB-1 007 B-2 910 594 TO SUPPORT C-283 39-2 36" EBB-1 007/
B-3 910 594 003 FROM 36" EBB-1 LINE TO VALVE 39-2A 8" EBB-1 007 B-5 1155 600 ICSilA FROM 36" EBB-1 LINE TO 12" CAP 39-2B 12" EBB-1 003 B-14 PROM STEAM GENERATOR l-1 THRU 40-0 26" EBB-1 007 B-11 910 594 PENETRATION 40 AND VALVE MS101 40-1 26" EBB-1 007 B-ll 91Q 594 I
TO SUPPORT SR10 40-2 36" EBB-1 007/
B-11 910 594 4
003 i
FROM 36" EBB-1 LINE M VALVE 40-2A 8" EBB-1 007 B-8 910 594 ICSilB FROM 36" EBB-1 LINE TO 12" CAP 40-2B 12" EBB-1 003 A-11 l
O 4
t e
I
a (flSPECTI0ff PROGRN1 CLASS 2 PAGE 1 0F 2 WELD If1SPECTI0fl.
SUPPORT IfiSPECTI0fi m
,s m^
LAJ m J
M 4
M 4
uu s
m n
n e
-.J W W
H H
H M C 0 9 e
e 3* W OD D
E N
N DH DH H
H rl REMARKS r
Hv
>m m
o.
u.
m>
m>
0.798*
6 1
1
- MIN. WALL
' MIN. WALL O.798*
2 1
2 1.055/
6 1
1 2.375 l
0.406 1
0.798*
7 1
2 1
- MIN. WALL 0.798*
5
- MIN. WALL 1.055/
8 3
1 2.375 0.406 1
1 I
36 4
3 4
1 4
INSPECT MINIMUM OF 25% OF WELDS AND SUPPORTS PER CODI:
i i
~
e t
l l
III-21
l",
4
\\
/
6 WELD AtlD SUPPORT SYSTEM: MAIN STEAM SYSTEM - SECOrDARY SIDE a
u Q
Ew ER 5
aps apf e
EnN 25E d
P ITEM LIllE o
eww ewx SUBSYSTEM /DESCRIPTI0ft fiUMBER fiUMBER ISID 8
8$E ES" E
FROM 36" EBB-1 LINE TO VALVE MS107 39-3 6" EBB-2 007/
B-3 910 594 003 FROM 6" EBB-2 LINE TO VALVE MS106A 39-3A 6" EBB-2 003 C-12 910 594 FROM 36" EBB-1 LINE TO VALVE MS106 40-3 6" EBB-2 007/
B-10 910 594 003 FROM 6" EBB-2 LINE TO VALVE MS107A 40-3A 6" EBB-2 003 E-2 910 594
.{
FROM STEAM GENERATOR l-2 THRU 57-0 4" EBB-5 007 E-2 930 536 j'
PENETRATION 57 57-1 4" EBB-5 007 E-2 930 536 I
FROM STEAM GDIERATOR l-1 THRU 58-0 4" EBB-5 007 E-ll 930 536 e
PCIETRATION 58 58-1 4" EBB-5 007 E-ll 930 536 c
i 4
Ir
I IftSPECTI0ft PROGRAff e
CLASS 2 PAGE 2 0F _2 WELD IflSPECTION SUPPORT IftSPECTI0ft M
w ILd Me c
La w
_s
>E U$
g3 I
e e
m e
m e
l.~.
uu s
f
>-* C
_J m F-F-
F-M I M i I
I
[ VI 50 25 a
E D
E S$
M5 REMARKS 1
0.280 5
3 2
2 1
0.280 0.280 G
3, 1
2 o.280 3
0.237 EXEMPT PER IWC-1220(c) l EXEMPT PER IWC-1220(c) 5 9.237 EETT PER IWC-1220 (c) 1 0.237 1
0.237 EXEMPT PER IWC-1220(c) 15 6
2 3
INSPECT MINIMUM OF 10% OF WELDS AND 25% OF SUPPORTS PER CODE.
6 l
e
(
?
i t
III-22
d 9
'i
'l I
WELD AtlD SUPPORT ]
SYSTEM: MAYZUP WATER TREATMENT SYSTEM 10 W
Q Ew ER S
c 5
aps ap5
$2 e
2fE
$3 ITEM
-LINE O
eww mwr r
SUBSYSTEM / DESCRIPTION NUMBER NUMBER ISID 8
8SE ESd'
$5 FIOM ANCllOR 183 TifRU PENETRATION 21-0 4"l!CB-23 010B K-2 35 85 SS 21 TO ANCilOR 121 h
i-t i
l i
e l
dt
oRdS "h2-o n5M u so h
$4S*.
2 AO5=
tPo =5E 5
.- U S
S)
ES L
NE O
KH
&V CC
/
3 4
3 4
l !
LR R
T T
T R -
R -
f HI 0U U
R
/
/
UT UT T
T mE=YM T(
VS S
P F
A SV SV V
A w
i iGU Ds mSMONt Mw
)
n E
8s
- wOi W
\\
{
WELD ATID SUPPORT SYSTE!!:
MAKEUP & PURIFICATION SYSTEM W
W E
ew HE a
5 sps spg 5
,l f$E ITEM LINE o
eww ewz H
SUBSYSTEM /DESCRIPTI0t{
fiUMBER flUMBER ISID 8
8SE ES" I
FROM TIIE REACTOR COOLANT LOOP TO LD-0 2 "CCA-18 031 C-2 2185 580 g
VALVES MUlA & MUlB LD-1 2 "CCA-18 031 C-3 2185 580 S
LD-2 2\\"CCA-18 031 C-3 2185 580 S
1 FROM VALVE MU2A TIIRU PEN. 14 &
14-0 2 "CCB-21 031 C-4 2185 120 S
VALVE MU3
.4' I-I
,I
\\
l P
\\
f
s If1SPECTI0ft PROGRAll PAGE 1 0F 1_
CLASS 1& 2 WELD IfiSPECTI0f4 SUPPORT IflSPECTI0tl
$G a
i EE eg e
e m?
mi
?
?
MM A
u
~
'Ji 50 RS S
E D
2 S$
S$
REMARKS s
0.375 3
1 CU6S 1 3
0.375 3
CLASS 1 3
1 Cues I 3
0.375 FIRST SEISMIC SUPPORT 1'
1 3
li 0.375 PAST TiiE BOUNDARY IS INCLUDED IN COUNT 12 3
1 INSPECT MINIMUM OF 25% OF WELDS AND SUPPORTS PER CODE.
W 6
l l
III-24
i
\\
,l WELD N!D SUPPORT SYSTEM: NOPSI, COOLDOWN SYSTEM C
U e
Ew ER 5
aps aps e
158 25W h
ITEM LItiE o
cr: w w a: w =c SUBSYSTEM / DESCRIPTION t1 UMBER NUMBER ISID 8
88E ESW FROM REACTOR COOLANT LOOP 2( A) TO 29-0 12"CCA-4 030/
D-7 2155 350 18"GCB-8 LINE INCLUDING WELDS 'D' 033 29-1 12"GCB-7 033 11 - 3 220 280 l
D
'B' FROM 12"CCA-4 LINE TO VALVE DH23 29-0A 8"CCA-4 033 11 - 2 2155 350
.FROM VALVE Dil23 TO 12"GCB-7 LINE 29-1A 8"GCB-7 033 H-3 220 280
-e FROM 12"GCB-7 LINE TO VALVE DH4849 29-1B 4"GCB-7 033 H-3 220 280 S2 1
4 FROM 12"GCB-7 LINE TO VALVE DI!31 29-2B 10"GCB-7 033 G-5 220 280 1
.i FROM 12"CCB-7 LINE TO VALVE DH30 29-3B 10"GCB-7 033 H-5 1
FROM REACTOR COOLANT LOOP 2(A) TO 29-2 12"GCB-7 033 G-5 220 280 18"GCD-8 LINE INCLUDING WELDS 'D' 29-3 12"GCB-7 033 II-5 220 280 AND B BYPASS AROUND VALVE Dill 518 29-lD 2 "GCD-7 033
!!-4 220 280 S:
1 FROM 12"GCB-7 LINE TO VALVE Dl!33 29-2C 2\\"GCB-7 033 H-6 220 280 S1 BYPASS AROUND VALVE Dill 517 29-lC 2 "GCB-7 033-H-4 220 280 SS FROM 12"GCB-7 LINE TO VALVE DH29 29-2A 2 "GCB-7 033 H-5 220 280" SE FROM 12"GCD-7 LINE TO VALVE DH28 29-3A 2 "GCB-7 033 11 - 5 S5
\\
FROM 12"GCB-7 LINE TO VALVE DH32 29-3D 2 "GCB-7 033 H-6 SI E
I IflSPECT10fl PROGRAll CLASS 1& 2 PAGE 1 0F _1_
WELD IflSPECT10ft SUPPORT IfiSPECT10f1 m
m w
mn x
wm
_s i
'N.
NN ms a
a m
-r m
e u
. c-uu s
- -* C
_j m N
H H
>-=
M e M 3 8
8 l
ar I-om a
M s
s 2 6-2 6--
t-6--
REMARKS vi e- -
um m
u.
u
=t m>
m>
i 1
1.125 4
2 lCLA49 l
0.250 8
1 CLASS 1 0.812 1
0.250 1
r 0.120 0.250 1
1 2
1 INSPECT MINIMUM OF 25% OF 5
11 WELDS AND SUPPORTS PER CODE ALL 0.250 ALL 0.250 1
0.203 ALL 1
Ii!SPECT ALL WELDS AND SEIS-MIC ddPPORTS DURING FLOW TEST.
)
0.203 1
EXEMPT PER IWC-1220(c). IN-SPECT MINIMUM OF 25% OF SUP l
PORTS PER CODE.
EXEMPT PER IWC-1220(c).'
0.203 EXEMPT PER IWC-1220(c).
O.203 e
EXEMPT PER IWC-1220(c).
l EXEMPT PER IWC-1220(c).
d.
III-25
a
\\
t WELD Afl0 SUPPOR1 SYSTEM:
now.AL MAKEUP m
w w
ce Ew ER O
aDE apM O
EOm NEE b
ITEM Lif1E E
bE EEU-U SUBSYSTEM /DESCRIPTI0ft
- f. UMBER fiUMBER ISID cos x
v
- o n.
FEoM VALVE Mu33 To 2 "CCB-2 LINE 19-1A 2 "CCB-3 031/
C-6 2250 120 t
033 O
f L.
l 8
9 1
I O
\\r Ll
IflSPECTI0fl PROGRAff CLASS 2 PAGE 1 0F l__
WELD If1SPECTI0ft SUPPORT If4SPECTI0fl
- 5 W!0 g
=
xx e
e ME as
'~
u m?
mT
?
Y Il 50 SS S
E D
E S$
S$
REMARKS S
O.
5 4
1 INSPECT MINIMUM OF 25% OF WELDS AND SUPPORTS PER CODE.
0 9
4 j
t III-26
o_
d I
\\
v WELD Afl0 SUPPORT SYSTEM: PEACTOR COOLMIT DRAIN NiD GASEOUS EADWASTE SYSTEM AUXILIARY BUILDING E
e ew Wi2 a
5 aps apf 5
e 558 EME 5
ITEM LIflE o
22 w w ewz e
SUBSYSTEM /DESCRIPT!0rt fiUMBER fiUM9ER ISID 8
8SE ESU' I
FIOM VALVE RC1719A M3D SUI' PORT 16-0 3"11CD-33 040A J-7 15 120 SS IICB-12-I!3 TIIRU PENETRATION 16 MID VALVE RC1719B I
?
6 i
l 1
f
[
C WmmQ5= x8g-o o
P3w u
,Em s g
c$ 2mgnd3
@ nog _5 AO5*
=
s S
t S) h ES L
c NE O
i KH
&V f
3 4
3 4
I CC
/
1 !
LR R
T T
T R -
R -
HU OU U
R
/
/
UT UT T
T AE"G u-T(
VS S
P F
A SV SV V
V i
i i
HZ(A9 mod aEEc3 OM w OM O * ~8 i
- d t"0In DG mGmOkC M=
o 5
OOOt.
1 i
m p
0TS I,
a
1 h
a WELD AflD SUPP0R SYSTEM: REACER COOLNiT SYSTEM
'i 0
Y e
Ew ER 5
aps ops e
65E l
ITEM LINE o
aww e w :c SUBSYSTEM /DESCRIPTI0ft tiUMBER fiUMBER ISID 8
@SE
@ S "-
REACTOR COOLtJ3T I4OP A RCA-0 36"DIA.
030 D-8 2250 650 RCA-1 28"DIA.
030 F-3 2250 590 RCA-2 28"DIA.
030 G-3 2250 390 RCA-3 28"DIA.
030 F-2 2250 590 c
RCA-4 28"DIA.
030 J-3 2250 590 c
i, REACTOR COOLANT LOOP B RCB-0 36"DIA.
030 D-9 2250 650 RCB-1 28"DIA.
030 F-13 2250 590 RCB-2 28"DIA.
030 G-Il 2250 590 RCB-3 28"DIA.
030 F-14 2250 590 RCB-4 28"DIA.
030 J-12 2250 590 I
i, I
FROM 28" COLD LEG % REAC% R RCA-lA 2h"CCA-18 030 G-3 2185 580 SE COOLANT PUMP P36-3 TO VALVE RC33 FROM 28" COLD LEG % REACE R RCA-3A 2 "CCA-18 030 J-2 2185 580 ss COOLANT PUMP P36-4 TO VALVE RC35 FROM 28" COLD LEG W REACM R RCB-1A 2h"CCA-18 030 F-13 2185 580 ss COOLANT PUMP P36-1 TO VALVE RC34 FROM 28" COLD LEG TO REACE R RCB-3A 2 "CCA-18 030 J-12 2185 580 S@
COOLANT PUMP P36-2 % RC41 O
f 1
l
L I1 1
l l
lp1l J!C2
[
% NW:30 I
N S
0 0
0 0
P 2
2 2 2 3
2 2 E
5~UiUG 2
3 3
3 3
3 2 2 2 2 0 2
2 2
2 0
J C
i 7
7 7
7 5 5 5 5 0
5 5 5 5
0 0=UWin T
V 5
5 5
5 0 0 0 0 0 0 0 0 0 0 O
I N
2 4
2 2 2 2 4 3 2 1
2 4 go R
P O
amNg)_
G RN W
1 8
1 3
2 2
3 1
2 am E
L D
I S
N E-P ECT I
D-ON 2-2 1
1 am C
S L
.M U
A P
S P
S am a.
O I
R 1
I T
t.V I
I 2
N 8
S P
s.M E
CT I
O b.e N
AI NN OWI NEN DS LS P
C PT SPT P
I R
TN SCN SI E
TOI M
P M
EDM A
A PU EM M.E U R
G M
R K
E O
S CF O
NF O
O 1
D2 2
E5 S5 U%
0 P
W F
PO E
OF
_4 LD R
E T
I t
]
1 t
WELDAflDSUPPO SYSTEM:
REACTOR cooumT SYSTEM 0
U e
Sw HR J
_, p 3
_, p 3
- 5 <9
=
e M$N E5W
$5 ITEM LINE g
ggg gg5 q,
SUBSYSTEM / DESCRIPTION NUMBER NUMBER
'ISID u
= o n-
=os 2-2 PRESSURIZER SURGE LINE PZ-0 10" DIA.
030 D-5 2250 670 FROM PRESSURIZER TIIRU VALVE PZ-1 3"CCA-8 030 B-4 2155 648 SS RCll TO VALVE RC2A PZ-2 2 "CCA-8 030 B-3 2155 648 SS FROM PRESSURIZER TO VALVE PZ-3 6"CCA-8 030 B-5 2155 648 RC13B PZ-4 4"CCA-8 030 B-5 2155 648 SS 030 B-5 2155 648 FROM PRESSURIZER TO VALVE PZ-5 6"CCA-8 RCl3A PZ-6 4"CCA-8 030 B-6 2155 648 SS J.
i l
l
[.
\\
r
=4
1 P
ll5PECTI0tl PROGRN1 CLASS 1 PAGE 2
0F 1 WELD IflSPECTI0tlr SUPPORT ItiSPECTI0ff m
m-LAJ m
_J GW
-e m
e m
e uu s
MZ J tr rt F-H F--
M B ff e B
e EEC 28 a"
E D
2 SC at-REMARKS i-1.000 4
1 0.438 2
1 1
1 0.375 0.562 6
1 -
0.438 0.562 3
1 0.438 1
16 1
3 1
1 inspect 25% OF WELDS AND SUPPORTS PER CODE.
e l
I III-29
1 i
WELD AtlD SUPPORT SYSTEM: REACTOR CooLA!iT SYSTEM y,
w G
GQ t
n 5e 5~
d!
ars arm e
M5s Ese
$frJ ITEM LINE a
ct w w a: w z SUBSYSTEM / DESCRIPTION NUMBER NUMBER ISID 8
8SE ESW fs PRESSURIZER SPRAY lit 4E PZ-7 2 " DIA.
030 E-8 2250 PZ-7A 2 " DIA.
030 C-8 2250
=,
i PROM 10"GCB-10 lit 1E TilRU VALVE 74C-0 1 "CCA-10 033/
G-ll 2185 580 SS D1127 36, PE!;ETRATIO!I 74C M4D 030 jf_
VALVE RC51 To 2 " PRESSURE SPRAY 74C-1 l\\"CCA-7 033/
D-5 2155 400 SS' LIFIE If;CLUDIIIG WELD
'l' 030 h
l s
e
l
'l flSPECTI0il PROGRAft PAGE 3
0F L CLASS 1
f WELD IflSPECTI0ti SUPPORT IflSPECTI0fl i
03 a
ne
.8 g ' MM e?
eT
?
T e
e F
om m
h EC 88 8
!E D
2 at at b
REMARKS 7
10 0.375 0.375 2
1 12 7
INSPECT 25% OF WELDS AND SUPPORTS PER CODE.
O.281 ALL ALL 0.281 ALL ALL ALL ALL ALL WELDS AND SUPPORTS -
PRESSURE TEST PERFORMED WITH PRIMARY SYSTEM HYDRO.
1 6
O 9
1 1
l III-30
r, 1
{
d WELD AtlD SUPPORT SYSTEM:
E Q
Ew EE a
5 aps ap5 5
e 250?
EME ITEM LINE o
ce w w a: w =c r
SUBSYSTEM / DESCRIPTION NUMBER NUMBER ISID 8
8SE ES&
I FROM SUPPORT 4Q,CCB-16-Jil 32-0 3"IICB-32 040A C-10 5
AMB SS
- TIIRU PENETRATION 32 70 SUPPORT 40-IISC-71-lil FROM SUPPORT 40-IICB-22-II3 48-0 3"HCC-22 040A 11 - 3 25 200 SS
'IIIRU PENETRATION 48 AND VALVE RC229A TO SUPPORT 40-IICC-85-lil
=
1 t I 4
Wt OI i
t b
It1SPECTI0tl PROGRAff l
CLASS 2 PAGE 4
0F 4 WELD ItiSPECTI0tl SUPPORT lilSPECTI0tl 0G h
EM eR a
e e
u?
eY
?
Y b?M ak u
[i
==
ea a
=
2
=
se at t
REMARKS v
INSPECT MI!!IMUM OF 25% OF 0.120 3
1 WELDS AllD SUPPORTS PER CODI' 1
Ir;SPECT MINIMUM OF 25%.OF O.120 4
WELDS A!;D SUPPORTS PER CODE e
e
\\
4 O
i
- i. l III-31
P' 4
WELD AtlD SUPPORT SYSTEM:
REFUELING CANAL SYSTEM
'i C
U Ew EU a
z
-e
\\
8
$US
$U5 E
i ITEM LIf1E E
E$$
&5h U
SUBSYSTEM /DESCRIPTI0ft fiUMBER fiUMBER ISID 8
8SE ESW' I
FROM VALVE Dl!88 TIIRU PEN. 49 TO 49-0 8"!!CB-11 033 F-4 20 100 VALVE DlI87 INCL'JDING FW3 9
F a
l.
il, i
l I
I
\\
r
l\\
I, BilSPECTI0tl PROGRN1 CLASS 2 PAGE 1 0F 1_
WELD INSPECTI0tl SUPPORT IrlSPECTI0tl
'J M-5 un d
xx
.o ::=
.a
.a NN awD x
H H
H x?
mT 9
9 Ji EC BS E
D 2
Sb Sb b
b REMARKS i
INSPECT MINIMUM OF 25% OF 0,148 3
WELDS AND SUPPORTS PER CODE.
h O
TTT-12
WELD AtlD SUPPORT
[
^
SYSTEM:
SERVICE WATER SYSTEM E
FIPST SEISMIC SUPPORT PAST w
BOUNDARY IS INCLUDED IN COUNT.
g g
gg pg pg z
e 65M EME E
ITEM Ot4E o
eww ewx H
SUBSYSTEM /DESCRIPTI0ti tiUMBER tlUMBER ISID 8
8SE OS" FPOM VALVE SW1366 Tl!RU PEN. 5 5-0 8"IIBB-7 041 E-3 70 85 1
FlOM VALVE SW1368 TilRU PEN. 6 6-0 8"IIBB-7 041 E-5 70 85 I
FROM VALVE SW1367 T!!RU PEN. 7 7-0 8"IIBB-7 041 E-6 70 85 5' ROM PEN. 9 TO VALVE SW1356 9-0 8"IIBB-ll 041 C-1 65 100 FROM PEN.10 TO VALVE SW1358 10-0 8"11BB-11 041 C-3 65 100 f
FROM PEN. 11 TO VALVE SW1357 11-0 8"IIBB-11 041 C-5 65 100
{
e 6
3 k
k
P i
IflSPECTI0ff PROGRAft i.
CLASS 2
PAGE 1 0F _1 WELD IflSPECTIOff SUPPORT IflSPECTI0ft m
m La mn tr LAJ M J
t)
Z LAJ o
Mx my
.c en m
ut s
m o
m e
l
~ ;;
_.J cr ce H
H H
cr e a e
$3r 50 BS S
E D
2 8$
5$
h REMARKS 0.322 3
2 0.322 3
I 1
0.322 2
2 0.322 3
1 0.322 2
1 0.322 2
1 INSPECT MINIMUM OF 25% OF
~
~
~
~
0
~
~
~
WELDS AND SUPPORTS PER CODE O
e Y
b III-33 I
i P
C.
WELD, SUPPORT AND BOLTING INSPECTION PROGRAM TABLES (continued) s
+
l 2.
Component Nondestructive Examination Tables.
This section provides a tabulation of all component welds and supports within the boundaries of the safety related systems, both those welds and supports that are tested in accordance with the requirements of Subsection IWB or IWC, as appropriate, i
of the ASME Boiler and Pressure Vessel Code,1977 Edition, and Addenda through Summer 1978 Addenda; and those welds and sup-ports for which the Code requirements have been found to be impractical.
The Tables are arranged by Class and System.
l III-34
PREPARED B M h h f,,
DATE V/ca]B PAGE 1
OF 3
DAVIS-BESSE NUCLEAR POWER STATION REVIEWED BY DATEf/2/fD UNIT NO. 1 ISID NO.
030 CLASS 1
SYSTEM REACTOR COOLANT REV. O, 2-15-80 COMPONENT SECTION XI SECTION i
DRAWING BASE MAT'L d
ITEM THICKNESS
$5 NOTE COMPONENT INFORMATION W/S DESCRIPTION NO.
NUMBER COORD NO.
CAT.
(INCIES)
M$
NO.
NAMES REACTOR VESSEL W
UPPER SHELL FLANGE TO UPPER SHELL 1
154616E E-8 Bl.30 B-A 12.000 MIN VOL I
MK-7 to MK-169 W
UPPER SHELL TO SHELL MK-169 to 1
154625E G-8 Bl.ll B-A 8.438 MIN.
VOL I
NUMBER:Tl MK-170 W
SHELL TO IDWER SHELL MK-170 to 1
154617E E-3 Bl.ll B-A 8.438 MIN VOL s
MK-171 DRAWING COOE: D-8 W
LOWER SHELL TO LOWER HEAD MK-171 TO 1
15'4625E G-10 Bl.ll B-A 5.375 NOM VOL f
MK-181 W
IDWER HEAD WELD M-181 to MK-6 1
154623E D-7 Bl.21 B-A 5.375 NOM VOL DESIGN OPERATING (ACCESSIBLE, PRESSURE 2750 psig i
W Z OUTLET NOZZLE TO SHELL MK-168 TO 1
154619E G-2 B3.90 B-D 12.175 NOM VOL (17)
TEMPERATURE 608 0F MK-169 B3.100 W
X OUTLET NOZZLE TO SHELL MK-168 TO 1
154619E G-2 B3.90 B-D 12.175 NOM VOL (17)
MK-169 B3.100 W
W/Z INLET NOZZLE TO SHELL MK-182 TO 1
154620E G-2 B3.90 B-D 12.175 NOM VOL (17)
MK-169 B3.100 W
Y/Z INLET NOZZLE TO SHELL MK-182 TO 1
154620E G-2
,B3.90 B-D 12.175 NOM VOL (17)
MK-169 B3.100 W
X/Y INLET NOZZLE TO SHELL MK-182 to 1
154620E G-2 B3.90 B-D 12.175 NOM VOL (17)
MK-169 33.100 EXAMINATION PERFORMED FROM VESSEL ID.
e
s PREPARED BYMe,s./-r / MATE g/r,j//W O.T ONENT NONDES E C M N N ION PAGE 2
OF 3
DAVIS-BESSE NUCLEAK POWER STATION p DATEf/2/fd UNIT NO. 1 REVIEWED BY ISID NO.
030 CLASS 1
SYSTEM REACTOR COOLANT REV. O, 2-15-80 COMPONENT SECTION XI SECTION DRAWING BASE MAT'L M
ITEM THICKNESS Si 5 NOTE COMPONENT INFORMATION W/S DESCRIPTION NO.
NUMBER COORD NO.
CAT.
(INCHES) 3E NO.
HAME:
REACTOR VESSEL W
W/X INLET NOZZLE TO SHELL MK-182 TO 1
154620E G-2 B3.90 B-D 12.175 NOM VOL (17)
MK-169 B3.100 W
W CORE FLOODING NOZZLE TO SHELL 1
154618E G-8 B3.90 B-D 12.175 NOM, VOL (17) i NUMBER: Tl MK-176 to MK-169 B3.100 W
Y CORE FLOODING NOZZLE TO SHELL 1
154618E G-8 B3.90 B-D 12.175 NOM VOL (17)
MK-176 TO MK-169 B.100 4
l DRAWING COORD: D-8 W
W CORE FLOODING NOZZLE TO SAFE END 1
15'4618E F-2 B5.10 B-F 3.000 NOM VOL &
g MK-176 to MK-89 SUR I
W Y CORE FIDODING NOZZLE TO SAFE END 1
154618E F-2 B'5.10 B-F 3.000 NOM VOL &
DESIGN OPERATING MK-176 TO MK-89 SUR l
PRESSURE 2750 psig W
INSTRUMENTATION NOZZLES TO LOWER 52 154624E C-7 B4.14 B-E NA VT-2 HEAD MK-92-ll8 to MK-6 (25%)
TEMPERATURE 608 op W
CLOSURE HEAD FLANGE TO CLOSURE 1
154628E B-10 Bl.21 B-A 6.625 MIN VOL HEAD MK-22 TO MK-24 W
CONTROL ROD HOUSING TO CLOSURE 69 154631E E-7 B4.13 B-E NA VT-2 HEAD MK-43-54 to NK-24 (25s)
W CONTROL ROD HOUSING WELD 69 154632E B14.10 B-O 0.649 SUR (O N. 7 PER-IPHERA :,)
S LIFTING LOG TO CLOSURE HEAD MK-34 3
154629E B-ll 38.10 B-H 3.5000 NOM SUR TO MK-24 EXAMINATION PERFORMED FROM VESSEL ID.
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030 CLASS 1
SYSTEM REACTOR COOLANT REV. O, 2-15-80 COMPONENT SECTION XI SECTION DRAWING BASE MAT'L 8
ITEM THICKNESS NOTE COMPONENT INFORMATION W/S DESCRIPTION NO.
NUMBER COORD NO.
CAT.
(INCHES) dE NO.
NAME8 STEAM GENERATO t W INLET NOZZLE TO UPPER HEAD MK-70 1
151916E
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VOL NUMBER: E24-1 TO MK-51 E24-2 W
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W DRAIN TO LOWER HEAD MK-22 TO MK-7 1
151917E G-3 TA B-E 8.000 NOM VT-2 (18)
PRESSURE 2750 psig S
SUPPORT SKIRT TO LOWER HEAD MK-96 1
151917E H-10 38.30 B-H 1.750 NOM VOL (19),
TEMPERATURE 608 0F I
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I NO SECTION XI CATEGORY AND/OR ITEM NUMBER GIVEN IN TABLE IBW-2500-1/IWC-2500-1.
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s, PREPARED d %4_DATEf/74/po COMPONENT NONDESTRUCTIVE EXAMINATION DAVIS-BESSE NUCLEAR POWER STATION p
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SYSTEM REACTOR COOLANT REV. O, 2-15-80 COMPONENT SECTION XI SECTION DRAWING BASE MAT'L 8
ITEM THICKNESS NO'IE COMPONENT INFORMATION W/S DESCRIPTION NO.
NUMBER COORD NO.
CAT.
(INCHES) 3E NO.
f NAME:
PRESSURIZER W
VENT NOZZLE TO UPPER HEAD MK-78 TO 1
154594E D-7 NA B-E NA VI-2 (18)
MK-5 W
MANWAY NOZZLE TO UPPER HEAD MK-122 1
154594E D-10 B3.110 B-D 4.750 MIN VOL NUMBER: T2 TO MK-5 B3.120 W
2 " RELIEF NOZZLE TO UPPER HEAD 1
154594E G-7 B3.110 B-D 4.750 MIN VOL i
MK-31 TO MK-5 B3.120
- C-4 W
SAFE END TO 2 " RELIEF NOZZLE MK-32 1
154594E C-7 B5.20 B-F
.375 NOM VOL &
.j TO MK-31 SUR W
3" RELIEF NOZZLE TO UPPER HEAD 2
154594E F-F B3.110 B-D 4.750 NOM VOL DESIGN OPERATING MK-124 TO MK-5 33.120 PRESSURE 2750 psig W
SAFE END TO 3" RELIEF NOZZLE 2
154608E E-7 35.20 B-F
.938 NOM VOL &
MK-125 TO MK-124 SUR TEMPERATURE 608 Op W
SPRAY NOZZLE TO UPPER HEAD MK-9 TO 1
154594E G-5 33.110 B-D 4.750 MIN VOL MK-5 33.120 W
SAFE END TO SPRAY NOZZLE MK-45 TO 1
154601E C-7 B5.20 B-F
.813 NOM VOL &
j MK-9 SUR l
W LIFT LOG TO UPPER HEAD MK-47 TO 2
154594E H-1 38.20 B-H 3.60,5 MIN SUR f
MK-5 W
UPPER HEAD TO SHELL MK-5 to MK-1 1
154592E D-10 32.10 B-B 4.750 MIN L'OL W
SHELL LONGITUDINAL WELD MK-1 1
154596E F-2 32.12 B-B 6.500 NOM 10L (21)
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PREPARED ua/s b DATE Vdd[fd COMPONENT NONDESTRUCTIVE EXAMINATION DAVIS-BESSE NUCLEAR POWER STATION PAGE 2 op 3
REVIEWED BY I DATE f/%/yp UNIT NO. 1 i
ISID NO. 030 CLASS 1
SYSTEM REACIOR COOLANT REV. O, 2-15-80 COMPONENT SECTION XI SECTION DRAWING BASE MAT'L 8
ITEM THICKNESS NOTE COMPONENT INFORMATION W/S DESCRIPTION NO.
NUMBER COORD NO.
CAT.
(INCHES) 3E NO.
NAME:
PRESSURIZER W-LEVEL SENSING NOZZLE TO SHELL 3
154592E C-8 NA B-E NA VT-2 (18)
MK-132 'IO MK-1 W
SHELL TO SHELL WELD MK-1 TO MK-2 1
154593E H-7 B2.ll B-B 6.500 NOM-VOL W
SHELL LONGITUDINAL WELD MK-2 1
154596E F-2 B2.12 B-B 6.500 NOM VOL (21)
W SUPPORT TO SHELL MK-126 TO MK-3 8
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C-4 W
SHELL TO SHELL WELD MK-2 TO MK-3 1
154593E H-7 B2,11 B-B 6.500 NOM VOL i
W SHELL LONGITUDINAL WELD MK-3 1
154596E F-2 B2.2 B-B 6.500 NOM VOL (21)
W SHELL TO HEATER BELT MK-3 TO MK-4 1
154593E H-7 32,11 B-B 6,500 NOM VOL DESIGN OPERATING AND MK-41 PRESSURE 2750 psig W
HEATER BELT FORGING TO HEATER BELT 4
154599E D-2 B2.12 B-B 7,500 NOM VOL (21)
SHELL LONGITUDINAL MK-4 TO MK-41 TEMPERATURE 608 OF AND MK-4 TO MK-40 W
HEATER BELT FORGING CIRCUMFERENTIAL 1
154599E E-7 B2.ll B-B 13,562 POM 70L HK-41 TO MK-40 W
SAMPLING NOZZLE TO SHELL MK-30 TO 1
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CLASS 1
SYSTEM VARIOUS REV. O, 2-15-80 COMPONENT SECTION XI SECTION DRAWING BASE MAT'L 8
ITEM THICKNESS Oi 5 NOTE COMPONENT INFORMATION W/S DESCRIPTION NO.
NUMBER COORD NO.
CAT.
(INCHES) dE NO.
I NAME: CLASS 1 VALVES VALVES DH-ll, DH-12 2
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REVIEWED BY Jr. -
DATEjI/2/fg UNIT NO. 1 ISID NO.
033 CLASS 2
SYSTEM DECAY HEAT REMOVAL REV. O, 2-15-80 COMPONENT SECTION XI SECTION i
DRAWING BASE MAT'L O
ITEM THICYNESS Oi5 NOTE COMPONENT INFORMATION W/S DESCRIPTION NO.
NUMBER COORD NO.
CAT.
(INCOS) dE NO. j W
HEAD TO SHELl. '4 ELD A 1
D2552-5 NA C1.20 C-A 0.625 NOM VOL (19)ll NAME: DEACAY HEAT COOLER W
SHELL LONGITUL_'AL WELDS B AND H 2
D2552-6 N,.
NA C-A 0.625 NOM VOL (18)
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D2552-6 NA C2.10 C-B 0.365 NOM SUR (19)
W NOZZLE TO FLANGE WELDS D AND F 2
D2552-6 NA C5.ll C-F 0.365 NOM SUR (19)
DMEG ME:
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D2552-6 NA C2.23 C-B 0.625 NOM SUR (19) 5 W
NOZZLE REENFORCING PAD TO SHELL 2
D2552-6 NA NA NA 0.750 NOM SUR.
(18)
DESIGN OPERATING W
SOCKET TO NOZZLE 4
D2552-6 NA C5.30 C-F NA SUR (19)!
PRESSURn 410 psig S
SADDLE TYPE SUPPORT NOT WELDED 2
D2552-6 NA C3.20 C-C NA VT-3 (19)
TEMPERATURE 280
'0F 1
I i
'NO SECTION XI CATEGORY AND/OR ITEM NUMBER GIVEN IN TABLE IWB-2500-1/IWC-2500-1.
EXAMINATION PERFORMED ON ONE COMPONENT ONLY.
EXAMINATION IS ONE FOOT AT INTERSECTION WITH CIRCUMFERENTIAL WELD.
m
N
.I PREPARED 74,, JATE j//fe[3 COMPONENT NONDESTRUCTIVE EXAMINATION 2
DAVIS-BESSE NUCLEAR POWER STATION PAGE 1
OF 1 REVIEWED BY [
ADATE[/2-/70 UNIT NO. 1 ISID NO.
034 CLASS 2
SYSTEM DECAY HEAT REV. O, 2-15-80 I
COMPONENT SECTION XI SECTION i
DRAWING BASE MAT'L M
ITEM THICKNESS Oi 5 NOIE COMPONE%T INFORMATION W/S DESCRIPTION NO.
NUMBER COORD NO.
CAT.
(INCHES) 3E NO. d NAME:
CORE FLOOD TANK W
MANWAY TO TANK WELD A 1
139621E G-5 C2.20 C-B 2.375 MIN VOL &
I (TYPICAL OF 2)
SUR (19).l W
HEAD TO SHELL (UPPER HEAD) WELD B 1
139621E I-3 C1.20 C-A 2.375 MIN -
VOL (19) I NUMBER: T9-1, T9-2 W
HEAD TO SHELL (LOWER HEAD) WELD C 1
139621E I-3 C1.20 C-A 2.375 MIN VOL (19) l DRAWING COORD:
OUTLET NOZZ M M HEAD WED D 1
139621E G-6 C2.20 C-B 2.375 M m m&
p q
H-7, H-3 8
W OUTLET NOZZLE TO SAFE END WELD 1
139621E G-7 C5.10 C-F SUR (19)
DESIGN OPERATING W
N LOADING NOZZLE TO UPPER HEAD WELE 1 139621E G-2 C2.10 C-B 2.375 MIN SUR (19) '
2 PRESSURE 700 psig W
MAKEUP NOZZLE TO SHELL WELD 1
139621E G-2 C2.10 C-B 2.375 MIN SUR (19) 0 TEMPERATURE 150 F W
SAMPLE CONNECTION NOZZLE IO SHELL WELD 1
139621E G-2 C2.10 C-B 2.375 MIN SUR (19) i W
LEVEL SENSING NOZZLE TO SHELL WELD 4
139621E G-2 C2.10 C-B 2.375 MIN 3UR (19)
S VESSEL SUPPORT WELDS E, F, I, J 4
139621E E-6 C3.10 C-C BUR (19)
S VESSEL SUPPORT WELDS G, H, K, L 4
139621E E-7 C3.10 C-C SUR (19)
I EXAMINATION PERFORMED ON ONE COMPONENT ONLY.
8
PREPARED 4YY.&/r E;,,e @ TE_Y/$a /e COMPONENT NONDESTRUCTIVE EXAMINATION DAVIS-BESSE NUCLEAR POWER STATION PAGE 1 OF 1 REVIEWEDBY_[
DATEf/2/fd UNIT NO. 1 CLASS 2
SYSTEM DECAY HEAT REV. 0,.2-15-80 COMPONENT SEC'..
XI SECTION i
DRAWING BASE MAT'L 8
ITEM THICKNESS NOTE COMPONENT INFORMATION W/S DESCRIPTION NO.
NUMBER COORD NO.
CAT.
(INCHES)
$E NO.
NAMEe IIIGH PRESSURE W
PUMP CASING WELD A 1
643066 NA C6.10 C-G COOLANT INJECTION SUR (19)
W PUMP (TYPICAL OF 2)
INLET NOZZLE TO PUMP WELD C 1
643066 NA NA C-B SUR (18)'
NUMBER: P58-1, P58-2 (19)
W OUTLET NOZZLE TO PUMP WELD 1
643066 NA NA C-B
'SUR (18)
(19)
DRAWING COORD: E-9, B, D, E,. F 5
642157 NA C3.70 C-E NA SUR (19)
C-9 DESIGN OPERATING PRESSURE 1650 psig TEMPERATURE 260 OF NO SECTION XI CATEGORY AND/OR ITEM NUMBER GIVEN IN TABLE IW8-2500-1/IWC-2500-1 I19I EXAMINATION PERFORMED.ON ONE COMPONENT ONLY.
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l DAVIS-BESSE NUCLEAR POWER STATION PAGE 1 OP 4 REVIEWED BY [
DATEf/2/fD T NO. 1 ISID NO.
007 CLASS 2
SYSTEM STEAM GENERATOR SECONDARY SYSTEM REV. O, 2-15-80 COMPONENT SECTION XI SECTION i
DRAWING BASE MAT'L 8
ITEM THICKNESS f;j 5 NOTE COMPONENT INFORMATION W/S DESCRIPTION NO.
NUMBER COORD NO.
CAT.
(INCHES).
5E NO.
NAME: STEAM GENERA'IOR
^
^
~
~
SECONDARY SIDE (TYPICAL OF 2)
W TUBE 31EET TO UPPER SHELL MK-51 TO 1
151911E H-5 C1.30 C-A 6.625 NOM VOL (19)
MK-1 NUMBER E24-1, E24-2 W
UPPER SIELL LONGITUDINAL WELD MK-1 2
175138E C-1 NA C-A 6.625 NOM VOL (18)
(19)
DRAWING COORD: C-ll, (21)
W SIELL 'IO SIELL MK-1 TO MK-2 1
151911E D-5 C1.10 C-A 4.188 NOM VOL (19)
C-2 W
SHELL LONGITUDINAL MK-2 1
175138E C-2 NA C-A 4.188 NOM VOL (18)
DESIGN OPERATING (21)
PRESSURE 1155 psig W
SHELL 'IO SHELL MK-2 TO MK-3 1
151911E D-5 C1.10 C-A 4.188 NOM VOL (19)
TEMPERATURE 600 0 W
SHELL LONGITUDINAL 2
175138E C-3 NA C-A 6!625 NOM VOL (18)
F (19)
(21)
W SHELL TO SHELL MK-3 TO MK-2_
1 151911E D-5 Cl.10 C-A 4.188 NOM 10L (19) I W
SIELL LONGITUDINAL MK-2 1
175138E' C-5 NA C-A 4.188 NOM VOL 118)
(19) i (21)
NO SECTION XI CATEGORY AND/OR ITEM NUMBER GIVEN IN TABLE IWB-2500-1/IWC-2500-1.
EXAMINATION PERFORMED ON ONE COMPONENT ONLY.
EXAMINATION IS ONE FOOT AT INTERSECTION WITH CIRCUMFERENTIAL WELD.
.I PREPARED C C /,
-07..,,_ CATE v/r,,4f>
DAVIS-BESSE NUCLEAR POWER STATION PAGE 2
OF 4 REVIEWED BY I
DAC f/2/ft1 UNIT NO. 1 ISID NO. _ 007 CLASS 2
SYSTEM STEAM GENERATOR SECONDARY SYSTEM REV. O, 2-15-80
' COMPONENT SECTION XI SECTION DRAWING BASE MAT'L M
ITEM THICKNESS Oi 5 NOTE COMPONENT INFORMATION W/S DESCRIPTION NO.
NUMBER COORD NO.
CAT.
(INCHES)
ME NO.
W NAME: STEAM GENERATOR SHELL TO SHELL MK-2 TO MK-4 1
151911E E-5 C1.10 C-A 4.188 NOM VOL (19)
SECONDARY SIDE W
SHELL LONGITUDINAL MK-4 1
175138E C-5 NA C-A 4.188 NOM VOL (18)
(. TYPICAL OF 2L (19)
NUMBER: E24-1, E24-2 (21)
W SHELL TO SHELL MK-4 TO MK-5 1
151911E E-5 C1.10 C-A 4.188 NOM NONE.
(22)
W SHELL LONGITUDINAL MK-5 1
175138E C-5 NA C-A' 4.188 NOM VOL (18)
DRAWING COORD: C-ll, C-2 (21)
W SHELL TO SHELL MK-5 TO MK-6 1
151911E D-5 C1.10 C-A
'.188 NOM VOL (19) 4 DESIGN OPERATING W
SHELL LONGITUDINAL MK-6 2
175138E C-6 NA C-A 6.625 NOM VOL (18) 5 PRESSURE 1155 psig (19)
(21)
TEMPERATURE 600 0F (18)NO SECTION XI CATEGORY AND/OR ITEM NUMBER GIVEN ON TABLE IWB 2500 1/
(
00-1.
EXAMINATION PERFORMED ON ONE COMPONENT ONLY.
EXAMINATION IS ONE FOOT AT INTERSECTION WITH CIRCUMFERENTIAL WELD NOT AT A GROSS, STRUCTURAL DISCONTINUITY - NO EXAMINATION.
O
PREPARED B47[2/, r;,,,,, m. DATEv/co/r2, COMPONENT NONDESTRUCTIVE EXAMINATION DAVIS-BESSE NUCLEAR POWER STATION PAGE 3 OF 4 REVIEWED BY DATE f///fD UNIT NO. 1 r
ISID NO.
007 CLASS 2
SYSTEM STEAM GENERATOR SECONDARY SYSTEM REV. O, 2-15-80 COMPONENT SECTION XI SECTION i
DRAWING.
BASE MAT'L M
ITEM THICKNESS Si $
NOTE COMPONENT INFORMATION W/S DESCP'.72* ION NO.
NUMBER COORD NO' CAT.
(INCHES)
$E NO.
W NAME8 STEAM GENERATOR SHELL TO LO'.ER TUBE SHEET MK-6 TO 1
151911E H-10 C1.30 C-A 6.625 NOM VOL (19)
MK-50 SECONDARY SIDE (TYPICAL OF 2)
W AUXILIARY FEEDWATER NOZZLE TO SHELL 1
151902E G-9 C2.10 C-B 6.625 NOM VOL &
NUMBERtE24-1, E24-2 W
AUXILIARY FEEDWATER NOZZLE TO SAFE 1
151902E G-9 C5.ll C-E O.432 NOM VOL END MK-300 TO MK-301 l
DRAWING COORD: C-ll, W
STEAM OUTLET NOZZLE TO SHELL MK-14 2
15'1902E E-5 C2.20 C-B 6.625 VOL &
C-12 TO MK-3 SUR li" DRAIN CONNECTION TO SHELL MK-25 2 151902E C-5 NA NA NA VT-2 (18)
W s
DESIGN OPERATING TO MK-3 PRESSURE _1155 psig 1" LEVEL CONNECTION NOZZLE TO SHELL 2
151.,0 2E E-5 NA NA NA VT-2 (18)
W MK-18 TO MK-3 4
O TEMPERATURE 600 F
W TEMPERATURE SENSING CONNECTION TO 2
151902E E-7 NA NA NA VT-2 (18)
SHELL MKn28 TO MK,2 W
SPARE LEVEL SENSING CONNECTION 2
151902E C-7 NA NA NA VT-2 (18)
SHELL MK-18 TO MK-2 W
LOW LEVEL SENSING CONNECTION TO 2
151902E C-9 NA NA NA VT-2 (18)
SHELL MK-27 TO MK-5 W
SAMPLE AND DRAIN NOZZLE 'IO SHELL 2
151902E E-10 NA NA NA VT-2 (18)
MK-18 TO MK-6 NO SECTION XI CATEGORY AND/OR ITEM NUMBER GIVEN IN TABLE IWB-2500-1/IWC-25bO-1.
EXAMINATION PERFORMED ON ONE COMPONENT ONLY.
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WELD, SUPPORT AND BOLTING INSPECTION PROGRAM TABLES (continued) 3.
Bolting Nondestructive Examination Tables.
This section provides a ' tabulation of all ' bolting within the boundariec of safety related systems, both bolting that -is tested in accordance with the requirements of Subsection IWB or IWC, as applicable, of the ASME Boiler and Pressure Vessel Code, 1977 Edition, and Addenda through Summer 1978 Addenda; and bolting for which the Code requirements have' been found to be impractical. The Tables are arranged by Class and System.
i e m.
1 4
4 4
III-56
PREPARED BY._m api 4
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- sM/
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/ Mo<-
,[8 DAVIS-BESSE NUCLEAR POWER STATION DATE f/f/M UNIT NO. 1 REV. O, 2-15-83 CLASS 1
SYSTEM REACTOR COOLANT PAGE 1
OF 5
SECTION XI g
COMPONENT O
b ITEM dE DRAWING
$0 $f DESCRIPTION NO.
CAT.
5U NUMBER 5E O :s NO.
REACTOR VESSEL CLOSURE STUDS (MK-25)
B6.20 B-G-1 6.50 60 M-503-44-5 VOL (23)
OR B6.30 VOL &
(24) y SUR 7y CLOSURE HEAD NUTS (MK-26)
B6.10 B-G-1 6.50 60 M-503-44-5 SUR LIGAMENTS BE'IWEEN STUD HOLES AND THREADS IN BASE MATERIAL B6.40 B-G-1 NA 60 M-503-44-5 VOL CLOSURE SPHERICAL WASHERS (MK-27)
B6.50 B-G-1 6.50 60 M-503-44-5' VT-1 CONTROL ROD DRIVE NOZZLE FLANG3 BOLTS B7.10 B-G-2 1.125 552 M-503-44-5 VT-1 (26)
CONTROL ROD DRIVE NOZZLE FLANGE NUTS B7.10 B-G-2 1.125 552 M-503-44-5 VT-1 (26)
WHEN BOLTING IS IN PLACE.
WHEN BOLTING IS REMOVED.
SEE CODE EXCEPTION 2.
Nl;z 5
$0 F
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BOLTING NONDESTRUCTIVE EXAMINATION
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~
DATE
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/
UNIT NO. 1 REV. O, 2-15-80 CLASS 1 SYSTEM REACTOR COOLANT pAGE 3 OP 5 SECTION XI g
,E COMPONENT O
ITEM dE DRAWING Nl DESCRIPTION NO.
CAT.
EU NO.
NUMBER ME Oz PRESSURIZER HEATER STUDS (MK-75)
B7.20 B-G-2 2
48 M-507-7-4 VT-1 U
NUTS (MK-76)
B7.20 B-G-2 2
48 M-507-7-4 VT-1 y
E MANWAY STUDS (MK-67)
B6.60 B-G-1 2.750 12 M-507-7-4 VOL (23)
OR B6.70 VOL &
SUR (24)
NUTS (MK-68)
B6.60 B-G-1 2.750 12 M-507-7-4 VOL (23)
OR B6.70 VOL &
SUR (24)
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D.
CODE EXCEPTIONS This section provides justification for the exceptions taken,to Code test requirements as provided for in 10 CFR 50.55a(g) (5) (iii).
Each Code exception is identified by a unique number and identifies the item (s) for which the Code exception is being taken.
The specific Code test requirement found to be impractical is defined and the basis for exclusion from Code requirements is presented.
Any testing performed in lieu of Code requirements is specified.
1.
Code Exception Number 1.
e Components:
Reactor Coolant Pumps P36-1, P36-2, P36-3, P36-4 o Function:
Reactor Coolant Circulation e Class:
1 Test Requirement:
Volumetric and Surface examination of the o
reactor coolant pump casing welds.
e Basis for Exception:
The reactor coolant pump casing welds are too thick for examination by using present state of art ultrasonic techniques. For a baseline, these welds are radiographed. However, for inservice inspection, the back-ground radiation will be too high making radiography impractical.
e Alternate Testing:
Surface examination only.
2.
Code Exception Number 2.
e Components: Control rod drive nozzle flange bolts and nuts.
e Function: Secure control rod drive housing to reactor vessel
- head, e Class:
1 Testing Requirement: Visual examine (VT-1) all bolts and nuts.
e e Basis for Exception:
It is impractical to visually examine the eight flange bolts on each of the 69 CRDM's from the plat-form of the head service structore, approximately 20 feet above the flange surface. Most of the peripheral CRDM bolts can be observed through the twelve (12) inch diameter ports in the service structure cylinder, the other CRDM bolts and are not accessible for examination.
e Alternate Testing:
Examine bolts and nuts on 10 percent of peripheral CRDM's to coincide with category B-0 " Pressure Retaining Welds in CRD Housings".
III-66
)
SECTION IV SYSTEM PRESSURE TEST PROGRILM t
)
IV.
SYSTEM PRESSURE TEST PROGRAM The System Pressure Test Program for all safety related systems will lac conducted in accordance with Table IWB-2500-1, Table ~IWC-2500-1 or Table IWD-2500-1 and will meet the requirements of Subsection IWB-5000, IWC-5000' or IWD-5000, as appropriate, of the ASME Boiler and Pressure Vessel Code,1977 Edition, and Addenda through Summer 1978 Addenda. The System Pressure Test Program will be applicable for the remainder of the 120-month interval, which started June 27, 1977 after which the Program will be reviewed and updated, as appropriate, with the Edition of the Code and Addenda in effect, not more than 12 months prior to the $ start of the next 120-nonth interval. All tests shall be conducted in accordance with the Inspection Program B of Section XI.
In the event that no safety or relief valve is provided within the test boundary, for tests performed under IWC-5000 or IWD-5000, the system's normal operating pressure will be used to determine the System Pressure Test and System Hydrostatic Test pressures to ~
be used.
In no case will the maximum pressure rating (with a 7 percent safety factor) of the lowest rated component be exceeded.
f 0
4 IV-1
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