ML20134J304
| ML20134J304 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/31/1983 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20134J287 | List: |
| References | |
| NUDOCS 8508290240 | |
| Download: ML20134J304 (22) | |
Text
.
SUMMARY
VIRGINIA ELECTRIC & POWER COMPANY NORTH ANNA POWER STATION UNIT #2 2nd OUTAGE /1st PERIOD /1st INTERVAL I.
Introduction An inservice examination of Class 1 and 2 components and piping, including two reactor coolant pump flywheels, reactor vessel veld, nozzle welds, ligaments, vessel interior, and closure head was conducted at North Anna Power Station Unit 2 from April 1, 1983 to May 26, 1983. The examinations were performed in accordance with an approved examination program.
Examination procedures were approved prior to the examination 4, and cdreification documents relative to personnel, equipment, and materials were reviewed and determined to be satisfactory.
1 Inspections, witnessing, and surveillance of the examinations and related activities were conducted by personnel from the Hartford Steam Boiler Inspection and Insurance Company, North Anna Station Quality Assurance Department, and North Anna Station technical staff.
II.
Limitations Some of the arrangements and details of the piping system and components were designed and f abricated before the access and examination require-ments of Section XI of the 1974 Code could be applied; consequently some examinations are limited or not practical due to geometric configuration or accessibility.
Generally these limitations exist at all fitting to fitting joints such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface condition preclude ultrasonic coupling or access for the required scan length, i
't 8508290240 850821 PDR ADOCK 0500 9
G
2 III. Examination
)
Ex==4 nations were conducted to review as much of the examination zones as was practical, within geomatric, metallurgical and physical limitations.
When the required ultrasonic examination volume or area could not be examined 100%, the examination was considered to be partial (PAR) and so noted. Generally PAR's are noted at fitting to fitting assemblies and in areas where integrally welded supports, lugs, or hangers, etc., preclude access to some part of the examination.
IV.
Rasults The reactor vessel examination performed, utilizing the remote operated tool, revealed no indication in the welds. A detailed explanation of the inspection may be found on Summary Report under Reactor Vessel Inservice Inspection Program 2nd Outage /1st Period /ist Interval.
The balance of plant non destructive examinations resulted in a total of 7 recordable indications being noted on the basis of procedure recording criteria, which generally are more critical than specified ASME Section XI acceptance standards.
Seven indications were treated and dispositioned by the North Anna Station Maintenance Department.
A sammary of the indications and dispositions follows:
A.
Three indications were related to boric acid residue or rust on bolting and flange areas due to minor leakage.
The af fected areas were cleaned, re-examined, and accepted.
B.
Two indications were related to nuts not properly engaged on studs.
The areas were tightened, re-examined, and accepted.
C.
Two indications were related to improper thread engagement on studs.
The areas were tightened, re-examined, and accepted.
A compilation of all recorded indications and their disposition by maintenance report is available, should you require more detailed information, the entire Inservice Inspection Program is maintained on file at the facility and the corporate office.
LETTER /ds31
INSERVICE INSPECTION REPORT INTERVAL - 1 PERIOD
-1 OUTAGE
-2 POR THE I
NORTH ANNA UNIT #2 NUCLEAR POWER STATION P.O. BOX 402 MINERAL, VIRGINIA 23117 FOR l
l f
VIRGINIA ELECTRIC AND POWER COMPANY l
P.O. BOX 1194 l
RICHMOND, VIRGINIA 23261 OUTAGE DATE: MAY 1983 l
COMMERCIAL SERVICE DATE: DECEMBER 1980 OPERATING CAPACITY:
907 MWe PREPARED BY:
WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR SERVICES INTEGRATION DIVISION INSPECTION SERVICE P.O. BOX 2728 PITTSBURGH, PENNSYLVANIA 15230
FORM NIS-1 CWNERS' DATA REPORT FCR INSERVICE INSPECTIONS l
As required by the Provisions of the ASME Code Rules
$ f$
- 1. Owne, Virgina Electric and Power Company. Rictenond, Va.
]
(Namne and Addres of Owner) j
- 2. Plant North Anna Power Station. Mineral. Virninfa 4
(Names and Address of Plant)
. Plant Unic 2
- 4. Owner certificate of Authonsanos (if seguned)
- k. Comanercial Seresse Does Dec. 1980s. Nano I soard Nusuber for Unit
- 7. - ; -
-_es tempected i
Manufacturer Cosmposest or Manufacturer or lastaller State or National Appursesasse or lastaller Senal No.
Province No.
Board No.
Reactor Iessel Rotterd==
30662 061445
~N/A teactor Vessel i
Intsmals W Pensacola Division RC ERI N/A N/A Steam Gen.
IZL. 1Z52 68-95, 68-96 4
Looos 1. 2. 3 W T==a= Division 1283 N/A 68-97 RCPCPC-01 R. C. Pumps W EMD op. og Nfa upv_1. p. 3.
{!
R. C. Piping Southwest Fabricating N/A N/A N/A C. L. 1 Piping Southwest Fabricating N/A N/A N/A 1
l C. L. 2 fiping Southwest Fabricating N/A N/A N/A
)
Excess Letd.
it. ExchanQer Atlas 1307 61436 1126 Residual it. Exchanaer Jos. Dat & Sons 1832-5 061417 372 i
5eal Water j
de Frehannse iln e. nat 1 Cane 1 A17 7D OKQAAA MQ Won-Regenerat.
.etdown Mt.Ech, Jos. Oat & Sons J-18303 059687 363 Regenerative 1
450 451 l
4t. Frehanaer Jos. Dat & Sons 1R31-12 106143c;
&4$2 lolume
~
Control Tank Jos. Dat & Sons 2034-1B 059825 501 Accumislator 061422 2823 Tank Delta-Southern 41370-71-1.2 061420 2822 Boron Inisetion Tanir Struthore IJslle N/A ncio7nn 11141 5eal Woter i
Iniect' on Filt, Commercial Fitters Div.
19076-1967 N/A 1465 i
Note: supplemental sheen in form of lists, sketches. or drawings may toe used provided (I) sise is 8% in. a 11 in..
l (2) information in items I through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
- l
,.1 1
This form (E000291 ney he ootained from the oroer Dept., aSME. 345 L 47tn St., New vorn, N.Y.
10C17 l
a.'
.... n FORM NIS 1 OWNERS
- DATA REPORT FOR INSERVICE INSPECTIONS As rosysired by the Provisions of the ASME Code Rules hh8
- 3. ow, Viroinia Electric and Power t'amnanv. Richannd v4 n4a4.
(Nasas and Addne of Owner)
~
~
North Anna Power Station. Mineral. Virainia
- 3. pie.t (Name and Address of Plan't)
- h. Flest Unic 2
- 4. Owner Certificaer of Aushorasanos (if required) l'
$. Cosmsmeresal Sesvise Date DEC. 19806. Nemoeal Board Number for Unit
- 7. PP= laspected I
Manufacturer re or Manufacturer or lastaller State or National Apparessence or Inesaller Serial No.
Province No.
Board No.
tes1 dual Heat temoval Pumps Innersoll - Rand L17024 M/A N/A
- eni;rifugal 46362. 46363 harging Pumps Pacific PumD Co.
46364 N/A N/A
's..
l l
Note: Supplemental sheets in form of lists. sketches. or drawings may be used provuled t 11 size is 8% in. x 11 in.,
l (2) informanon in items 1 through 4 on the data report is included on each sheet. and (3) each sheet is numbered and the number of sheets is verorded at the top of the form.
10C17 TNe' form (E00029) nov be metained frorn ime Creer Dept.. ASME. 345 L 47tn St.. New yors. N.Y.
j 4
REACTOR VESSEL I"TER!!ALS EXA"I:lATIO !
SITE: il0RTil A!!! A L't:IT 82 I!.TEP. VAL: 1 oEP.IOD!.1 DATE: APRIL.1933 OUTACE 2 ir A video taoe recorri was made of the areas identified by the I:!TEP.:tAL DRO*.RA*i.
This tace has been reviewej by MESTI'lCH0!ISE for co"nliance with the required exaaiinations.
Westinghouse:
N 9 ate:
N _3 Recei,t of
/
reel (p4 of viieo tane fron !!estinchouse is ackno'sledneJI Utility:
- ' ate:
- -9p T3 I
k
'y
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n Procedure:
ISI-88 Rev. 1 Examiner (s);_,I-1 for v
j ECLn a t
e l
Date(s): 4-2L 24 - 83 VPPER I N T E R fl A L S i
Tape Ref.
Initial as j,hg i
C 0 il P 0 N E N T Location Location Remarks RI NRI
- E
- Thennocouple and Flow Mixer Device 3ti'Em 2 W 658to787
- Fastenings (As Accessible)
A M #ET j bpper internals - Head Alignment o*
63S i Pin Interface Surfaces.
Examine 2 27o*
StoS I
! Opper Core Plate Fuel Assembly Peripheral W
x MB hr
! Guide Pins (As accessible)
Pins o
- to 2-io" vessel 5
(,5 axis.
i
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Procedure:
151-88 Rev. 1
)
Examiner (s)J._ 4 _ -f rg7 m,-
3 3 L A
_t.
l Date(s):
4-ZL24-83
- LOWER l il T E R N A L S 4
Initial as
)
i Tape Ref.
i C 0 fi P 0 !1 E il T S Location Location Remarks RI MRI jeted l
l I ticad and Vessel Alignment Pin Vessel Mating Surfaces and Attachments.
Axis x,
ws ser
- Examine 4
[.
M
" O 4*7 x
us ser gg A
x6 as r 2 Xf 217.
i Unver Core Plate Guide Key.
Vessel x
>A ger Axis,
M i Examine v
W der l
O*
27oiq 3:2 8
un gar K
ws ner
- Outlet Nozzle Mating 90fface.
Vessel g g,,7 k
Examine Axipeyg.
4cgg,4gg 2(1 05*
A M der Flange to Core Barrel Weld From 210 512.to S45 g
to O
4 Core Barrel Flange Flow Nozzle Welds.
From o
- oas to251 to
%o*
- & *T Core Barrel Mid Plane Weld From 2]O
- 488to S22 to O
Vyn gy u.w
/
.-s
~
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?
I
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Procedure:
151-88 Rev. 1 Ex as..iner(s):
4
_a r%_,
y i
b D Q._
4 g'g Date(s):
14 21.24-83 j
- t t-
^
.._a'4^
linitia'. asi ITape Ref. '
C i,....,. L \\ '-
i i.ocation Location Ri n.arns RI NRI !Exara. is i
i
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Completed !
- )
i Jua8 derj X
e t
....,3...... y in. e..e s i from 40 ' 384 to448 !
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l to IBo
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.Jf.c ? ai.e.
2xas;r.e T0,1 2 formers a 3"O84f X
... :.- Ce.e F. te doiting From O* 3aoto384 to 3roo
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5'
( 4-I l
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1 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 REACTOR VESSEL INSERVICE INSPECTION PROGRAM 2ND OUTAGE /1ST PERIOD /IST INTERVAL 1983 The areas listed below were examined as required by the Plant Technical
, Specification, the 1974 Edition of Section XI of the ASME Boiler and Pres-sure Vessel Code with Addenda through Sunner,1975, and the NRC Regulatory (Guide 1.150, utilizing the Westinghouse remotely operated reactor vessel r inservice inspection tool.
VESSEL-TOOL INTERFACE PARAMETERS (Dwg. 2222D24 (5 Sheets))
(a) Vessel head alignment pins located at 0, 90, 180 and 270 degrees vessel axis.
(b) Closure head guide studs located in stud holes #5, #21 and #37 on 171.25 inch bolt circle diameter. Guide stud #5 removed.
(c) Tool aligned on pin at 90 degrees and other two legs at 210 degrees and 330 degrees.
EXAMINATION REQUIREMENTS IWB-2600 Item Bl.3 VESSEL TO FLANGE WELD (Dwg. 2222024 Sheet 5)
W VGB 1-1100 Weld #1 Thirty-three percent of the total length of the weld to be examined.
Examine from centerline between stud hole #58 and #1 at 356.90' vessel axis, clockwise to centerline between stud hole #12 and #13 at 71.38' vessel axis and from centerline between #44 and #45 at 270* vessel axis clockwise to centerline between stud hole #51 and #52 at 313.44' vessel axis.
(117.9degreestotal)
l eq4,,
IW8-2600 Item Bl.4 OUTLET N0ZZLE TO VESSEL SHELL WELDS
(
W VG8-1-1100 (Dwg.2222024 Sheet 4) i Loop 1 - Weld #14 Examine the nozzle to shell weld and nozzle protrusion of Loop 1. Loop 2 and Loop 3 Loop 3 - Weld #10 outlet nozzles.
Centerline of nozzles Loop 3 - Weld #12 located 82.94 inches from top: surface of flange. Outlet nozzle located at 24.9 3
degrees vessel axis for Loop 2,145.1 I
degrees for Loop 1 and 265.1 degrees for f
Loop 3.
IWB-2600 Item Bl.6 0UTLET N0ZZLE TO SAFE-ENO WELDS W VGB-1-1100 (Dwg. 2222024 Sheet 4)
W VGB-1-4100 Examine nozzle to safe-end welds on Loops 1, Ioop 1 - Weld #1(DM) 2 and 3 at locations given under Item Bl.4.
Centerline of nozzle to safe-end weld is at 8~l~4(d#1(DM) 122.53 inches from centerline of vessel.
W VGB-1-4300 foop 3 - Weld #1(DM)
IWB-2600 Item Bl.9 LIGAMENTS BETWEEN THREADED STUD HOLES 024 S W t 2)
W VGB~1-1100 Examine thirty-three percent of the vessel flange ligaments.
Examine ligaments around stud holes #1 through #12 and a45 through #51 (19 total).
Stud holes are threaded 6"-8N-38, are 11 inches deep and are located on 171.25 inches Bolt circle diameter.
Flange top surface is 0.5 inches above flange seal surface.
EXAMINATION The above listed areas were examined utilizing the remotely operated reactor vessel inservice inspection tool in accordance with the requirements of Procedure 151-154 Rev. 1.
The examinations were performed using search unit sizes, frequencies and refracted angles as defined below.
Detailed param-eters for the examination of each individual weld or area, including the
- 1,ocation of each scan with reference to the vessel axis and datums, the number of scans, the incremental distances between scans are defined in the inspection program input data prepared in accordance with Procedure RV-ISI-01 Rev. 1.
The requirements of NRC Regulatory Guide 1.150 as defined in Westing-house Recomended Position" dated March 22, 1983 were applied to the examin-ation of the Vessel to Flange Weld and the Outlet Nozzle to Ves.el Shell Welds.
20
SEARCH
- 5. U.
FREQUENCY INCIDENT REFRACTED LOCATION UNIT SIZE MHz ANGLE ANGLE I
Outlet Nozzle to Shell Welds TRS 1.5 2.25 0*
O' and Nozzle Protrusions TR7 1.5 2.25 23.5*
60's TR8 1.5 2.25 23.5' 60's i
ObietNozzleSafeEndWelds TRO
.750 2.25 0'
0' TR1
.750 2.25 9 1/2*
41*L TR2
.750 2.25 9 1/2' 41*L TR3
.750 2.25 91/2' 41*L TR4
.750 2.25 9 1/2' 41*L Vessel to Flange Weld TR5 1.5 2.25 0'
0' TR9 1.5 2.25 1.5*
6*L TRLO 1.5 2.25 3*
12*L Flange Ligaments TRIO 1X.5 5.0 0'
0' CALIBRATION All search units were calibrated utilizing the information given in Appendix A in accordance with 151-154 Rev. 1.
l 1
Al l
I
s.e APPENDIX A CALIBRATION REQUIREENTS AREA TO BE INCIDENT REFRACTED CAL. BLOCK WATER PATH MANIPULATOR EXAMINED ANGLE ANGLE IDENTITY DISTANCE CALIBRATION REFLECTOR IDENTITIES ORIENTATION Outlet Nozzle 0*
0*
VRA-020 TRS:ll" Hole A Hole D Hole F**
Vertical to Vessel Welds Nozzle Inside 23.5*
60*S VRA-021 TR7:12" Hole D Hole E N/A Vertical Radius (Protrusion)
& TR8 Vessel to Flange O'
0*
VRA-020 TRS:12" Hole D Hole C Hole B Horizontal Weld 1.5*
6*L VRA-020 TR9:12" Hole D Hole C Hole B Horizontal 3*
12*L VRA-020 TR10:12" Hole D Hole C Hole B Horizontal 1
Ligaments O'
0*
VRA-020 TRLO:9 1/2" N/A Hole B Hole C Horizontal Safe-End Welds 0*
O' VRA-022 TRO:5" Hole A Hole B Hole C Vertical 9 1/2*
41*L VRA-022 TRl:5.1" Hole A Hole B Hole C Vertical i
9 1/2*
41*L VRA-022 TR2:5.1" Hole A Hole B Hole C Vertical i
9 1/2" 41*L VRA-022 TR3:4.7" Hole A Hole B Hole C Vertical j
9 1/2*
41.*L VRA-022 TR4:4.7" Hole A Hole B Hole C Vertical 1
- Manipulator Orientation - Horizontal 1
i 8
~
NORTH ANNA UNIT 2 - 1983 8
Transducers TRO,TR1, TR2, TR3, TR4 are 3/4" diameter Transducers TRS. TR7, TR8 TR9 TRIO are 1 1/2" diameter Transducer TRLO is 1" x 1/2" i
mo 00 N m OO O O O LD r
~
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O OMN 5 d ma 8
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ii ii m e in w 8.000 6.500 4
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-2.500 d- - -
TR 5 t
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-3.500 TR' 7 g i
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+
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f -6.353 i--
-5.750 l
(R 9 Jo- -l /) L -6.554
-6.05I
-8.000 O OO OO O O OO OO O q in, q m, m, O,
-m e emIi t
40 MONTH TRANSDUCER PLATE AS
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA PC'iER STATION UNIT 2 4
INSERVICE INSPECTION PROGRAM i'
2ND OUTAGE /1ST PERIOD /1ST INTERVAL 1983 All items listed below wara examined, as indicated, in accordance with the re-quirenients of the Plant Technical Specification, Section 4.2 and the 1974 Edition of Sedtion XI of the ASME Boiler and Pressure Vessel Code up to and including Sumner",1975 Addenda to the extent practical with the access provided and the limitations of component geometry.
PROGRAM IWB-2600 EXAMINATION SKETCH ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE U/T SURF V/T VGB REACTOR VESSEL 1-1100 1.
Bl.3 Weld #1 - 120*
154' 1-1300 2.
Bl.3 Weld #1 - 0* thru 120' 47 1-1100 3.
B1.4 Welds #10, #12 and #14 154 1-4100 4.
Bl.6 Weld #1(DM) 154 1-4100 5.
Bl.6 Weld #1(DM) 205 11 1-4200 6.
Bl.6 Weld #1(DM) 154 1-4200 7.
Bl.6 Weld #1(DM) 205 11 1-4300 8.
Bl.6 Weld #1(DM) 154 1-1100 9.
Bl.9 Closure Ligaments - Examine 154
- 1 thru #12 and #45 thru
- 51 8
1-1300 10.
Bl.11 Conoseal Bolting - Area #1 88 1-1200 11.
81.15 Vessel Interior STEAM GENERATORS 12.'
B3.1 Welds 1-1, 2-1, and 3-1 47 1-3100 from 0" thru 7.5" PIPING 1-4109 11 13.
B4.8 Weld #19 e
r i
ll
EXAMINATION SKETCH PROGRAM IWB-2600 ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE
~
U/T SIRF V/T g
PtMPS 1-5100 14.
55.1 Flange Bolting 3-B1 thru 3-824 15 15.l B5.3 Flange Bolting 3-B1 thru 3-824
'8 1-5100
- 16. E B5.2 Seal House Bolting 2-81 thru 15 70 8
1-5100 2-812 8
1-5100 17.
85.5 Pump Supports 1-15C 1-2SC and 1-35C VALVES 8
1-6300 18.
B6.9 Items:
6,9,12,13,15,16,18 and 59 FLYWHEEL
~
Flywheel 2-1 and 3-1 41 11 8
1-5100 19.
PROGRAM IWC-2600 EXAMINATION SKETCH ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE U/T SURF V/T VGB EXCESS LET00WN HEAT EXCHANGER 2-1110 20.
C1.1 Wald #1 from 0" thru 1" 205 8
2-1110 21.
C1.4 Bolting 81 thru B12 15 RESIOUAL HEAT EXCHANGERS 2-1120 22.
C1.1 Weld 1-1 from 71.0" thru 73.5" 205 2-1120 23.
C1.1 Weld 2-2 from 71.0" thru 73.5" 205 2-1120 11 24.
C1.3 Welded Supports 1-2WS and 2-1WS 8
2-1120 25.'. C1.4 Bolting 1-B1 thru 1-B48 15 SEAL WATER HEAT EXCHANGER 26.
C1.1 Welds #1 and #2 from 0" thru 2" 205 2-1130 2-1130 11 27.
C1.3 Welded Supports 1WS and 2WS t
)
/b
PROGRAM IWC-2600 EXAMINAT!0N SKETCH ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDLRE REFERENCE U/T SURF V/T vgg IGN-REGENERATIVE LET00WN HEAT EXCHANGER
- 28.,
C1.1 Welds #1 and #2 from 0" thra 4.5" 205 2-1140 2g. i 11 2-1140 C1.3 Welded Supports 1WS and 2WS r
30.
C1.,4 Solting B1 thru B36 15 8
2-1140 REGENERATIVE E AT EXCHANGER l
31.
C1.1 Welds fl. #3. #5 and #11 205 11 2-1150 V0LLME CONTROL TANK 2-1200 32.
C1.1 Wald #1 from 6" to 11" 205 2-1200 33.
C1.1 Wald #2 from 0" to 5" 205 2-1200 11 34.
C1 3 Welded Supports IWS and 2W5 8
2-1200 35.
'C1.4 Bolting 51 thru 816 15 ACCUMULATOR TANKS 2-1210 i
36.
C1.1 Weld #1-1 from 0" thru 10" 205 2-1210 37.
C1.1 Wald #1-4 from 0" thru 10" 205 2-1210 i
38.
C1.1 Wald #2-3 from 0" thru 10" 205 2-1210 39.
C1.2 Wald #1-6 205 2-1210 11 40.
C1.3 Welded Support 1-5 from 0" thru 10" 8
2-1210 41.
C1.4 Bolting 1-B1 thru 1-820 15 BORON INJECTION TANK 2-1220 42.
C1.1 Wald 1 from 0" thru 5" 205 2-1220
- 43. '
C1.2 Weld #3 205 2-1220 11 44.
C1.3 Weld Support WS-1 8
2-1220 f
45.
C1.4 Bolting 81 thru 816 15 40 I
L Cy4MINAT!0N SXETCH t
PROGRAM IWC-2600
(
ITEM REFERENCE AREA AND EXTENT OF EXAMIN.*. TION PROCEDWE REFERENCE U/T SURF V/T g
(
P! PING
- 44.
- C2.1 Wald #8 205 2-2525 r
l f
RE5100AL HEAT REMOVAL PLMPS f
8 2-3100 i
47.
C3.2 Bolting 1-81 thru 1-824 15 8
2-3100 48.
C3.4 Supports 1-15C.1-25C and 1-35C CENTRIFUGAL CHARGING PUMPS 8
2-3110 49.
C3.2 Bolting 1-81 thru l-816 15 11 8
2-3110 50.
C3.3 Welded Supports 1-1WS. 1-4W5 2-2W5 and 3-4WS 8
2-3110,
51.
C3.4 Supports 1001 Punp 1 REACTOR COOLANT PUMP _
52.
C1.4 Seal House Bolts 2-81 thru 2-812 15 70 8
2-3120 VALVES 8
2-4100 53.
C4.2 Items 6. 7 and 8 15 W
1
AU WENTED PROGRAM AND MISC. ITEMS I
SKETCH ITEM CATEGORY EXAMINATION OR.
NO.
NO.
AREA AND EXTENT OF EXAMINATION PERFORMANCE NDT - R#
System Leakage Test VT ',
54 f
55 B3.10 Bolts 1-81 thru 1-532, 2-51 thru
.MT/VT 1-1300 2-B32 and 3-81 thru 3-B32 P! PING 56 54.5 Welds 1.2.3.4,6,7 and 10 UT 1-4103 57 B4.5 Weld 18(82)
UT 1-4201 58 54.5 Welds 6.7.8,9 and 10 UT 1-4203 59 54.5 Welds 10(82) and 11(82)
UT -
1-4206 60 B4.5 Weld 17(82)
UT 1-4302 61 84.5 Welds 1.2.3.6,7 and 10 UT 1-4304 62 B4.5 Welds 44(82) and 45(82)
UT 1-4306 63 B4.5 Welds 8,9 and 18 UT 1-4500 64 B4.5 Welds 14,22.30,31 and 35 UT 1-4502 65 B4.10 Support Components VT 66 B4.12 Items 16 and 17 VT 1-4700 REACTOR COOLANT PUMP 67 B5.2 Seal House Bolting 3-B1 thru 3-812 MT/UT 1-5100 68 B5.3 Seal House Bolting 3-B1 thru 3-B12 VT I-5100 VALVES 69 56.7 Item 32 VT 1-6200 70 86.9 Items 9,28.40.52.53 and 54 MT/VT 1-6300 l
,.;4.;O.. L. -
SIETCH EXMINATION -
OR...
ITEM CATtdY No.
NO.
AREA MD EXTENT OF EXMINATION PERFORMANCE NOT - Rf r
STEM GENERATORS 3
71f C1.1 72 C1.4 Rolts 2-31 thru 2-540 UT/YT 2-1100 f
I SEAL WATER INJECTION FILTERS 73 C1.1 Welds 1-1 and 2-2 from 1" thru 2" UT 2-1300 l
74 C1.3 Welded Supports 1-1WS,1-3WS PT/VT 2-1300 and 2-2W5 75 C1.4 Bolting 1-81 thru 1-316 UT/VT 2-1300 REACTOR C0OLANT PUMPS 76 C1.4 seal House Bolts 3-81 thru 3-812 MT/UT/VT 2-3120 YT 77 C2.6 Support Components VALVE 5 78 C4.2 Items 6,7,8 and 28 VT 2-4100 NOT - R#
MISC. ITEMS WGE.
Wald 23 VT/PT 83-073 79 Weld 23 VT/PT 83-073 80 VALVES VT 83 225 Valve 2-51-21 81 VT 83-157 Valve 2-51-1 82 STEM GENERATOR $
(
Hand Hole Bolts - $ team Generators #2 VT 83 172 83 I
t AUGENTED PROGRAM AND N!5C. ITEMS _
ITEM CATEGORY EXAMINATION SKETCH E
NO.
AREA ANO EXTENT OF EXAMINATION PERFORMANCE OR NOT R0 t
M B4.5 Welds 28 and 30 lli 1-4504 h
e i
l l
1