ML20088A550
| ML20088A550 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/29/1975 |
| From: | Ginstein, Kasky R, Scott V ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML20087N425 | List: |
| References | |
| TR-ESS-031, TR-ESS-31, NUDOCS 8404120200 | |
| Download: ML20088A550 (136) | |
Text
._
e SHOP PRE-SERVICE INSPECTION PROGRAM for LOUISIANA POWER & LIGHT Waterford 3 Steam Electric Station OOCUMENT No.
TR ESS - 031 L.. D THIS IS >
VOLUME 1 SHOP PRE SERVICE INSPECTION PROGRAM PROGRAM PLAN VOLUME 2 SHOP PRE SERVICE INSPECTION PROGRAM PROCEDURES VOLUME 3 SHOP PRE SERVICE INSPECTION PROGRAM REPORT VOLUME 4 SHOP PRE SERVICE INSPECTION PROGRAM EXAMINATION DATA VOLUME 5 SHOP PRE SERVICE INSPECTION PROGRAM EXAMINATION DATA l
l AO O
O 2
g PDR Prepared By:
l-*
SYSTEMS INTEGRITY SERVICES l
POWER SYSTEMS GROUP POWER I
COMBUSTION ENGINEERING wind.o,. Conn.cucm SYSTEMS i
l
Date:
7/28/75
~
Revision: 0 By:
-O I
PRESERVICE INSPECTION PROGRAM FOR LOUISIANA POWER AND LIGHT WATERFORD III STEAM ELECTRIC STATION i
O erePered By:
SYSTEMS INTEGRITY SERVICES GROUP DEVELOPMENT DEPARTMENT NUCLEAR POWER SYSTEMS COMBUSTION ENGINEERING WINDSOR, CONNECTICUT
,of Date:
2[2/ 2,5~
Prepared By:
om Senior Development Engineer Approved By:
el Date:
((
[
Manager Inservice pection O
Approved By:
Date:
7 89 Manager, Systems'integr'ty Services
Date:
7/28/75 Revision:
O O
PRESERVICE INSPECTION 9.f.
_ NUCLEAR POWER PLANT COMPONENTS Date February 7. 1984 Owner Louisiana Pover and Licht Plant Waterford III S. E. S.
142 Delaronde Street Taft, Louisiana New Orleans. Louisiana 70174 o
Commercial Service Date (later)
Capacity 3410 MWt 1165 MWe Reactor Vessel No.
(later)
National Board No. Vessel Cla';er?
(State)
Head L la1;er?
Approved:
- a Mfg. By: Combustion Engineerina. Inc.
i ISI coordinator Part No. Vessel 171-201 Title Vessel Head 101-501 A8STRACT The prociram presented within details the examination requirements necessary to comp'y with the 1974 Edition of the ASME Boiler and Pressure Vessel Code,Section XI through the Summer of 1974 Addenda, for the preservice examination of reactor power plant components. This work will be performed in Combustion Engineering's manufacturing facilities in Chattanooga, Tennessee.
Section V
-]
of this-program implements the requirements of Section XI on the reactor pressure vessel, closure head, steam generators and pressurizer.
Date:
3/29/76 Revision:
I By:
IIG O
INTRODUCTION This manual has been prepared to fulfill the Preservice Examination require-ments for the nuclear reactor coolant system pressure boundary of the Waterford III Steam Electric Station nuclear power station.
The require-ments are outlined in the ASME Boiler and Pressure Vessel Code, Section XI:
Rules for Inservice Inspection of Nuclear Power Plants Components (1974 Edition 4
and Summer 1974 Addenda). This program is limited to application of those requirements to the reactor pressure vessel, closure head, steam generators and pressurizer.
This program manual is self-contained; included are drawings which show nozzle weld and other inspection area locations in the principal components, i.e., reactor vessel, steam generators and pressurizer.
In an accompanying volume, appropriate examination procedures and associated data sheets are provided for use by qualified examiners.
Subsections are provided which include definitions of the examination areas, exclusions and exceptions, quality control / quality assurance documents, Q/
report submission guidelines, descriptions of the various UT calibration standards, remote equipment descriptions, examination procedure philosophy, and a copy of Section XI of the ASME Boiler and Pressure Vessel Code including the applicable addenda.
The Preservice Examination Program and Report is presented in five volumes.
Volume 1 - Program Plan Book Volume 2 - Procedures Volume 3 - Report i
Volume 4 - Data Volume 5 - Data This volume, Volume 1, contains the program which describes the examina-tion areas.
O v
I-1
Date:
7/28/75 Revision:
0 TABLE OF CONTENTS I.
Introduction Title Page Certificate of Compliance Introduction II.
Table of Contents III.
Revision Record List of Effective Pages Record of Revision Pages IV.
Program Description V.
Examination Areas Program Sheets Examination Area Designation Codes V-1:. Zone 1
()
~
Plan and Schedule Sheets.
4 Reactor-Pressure Vessel Drawing No. E-LOU-112-001 V-2:
Zone 2 Plan and Schedule Sheets Reactor Vessel Closure Head Drawing No. E-LOU-ll2-002 V-3:
Zone 3 Plan and Schedule Sheets Steam Generator Number 1 Drawing No. E-LOU-112-003 V-4:
Zone 4 Plan and Schedule Sheets Steam Generator Number 2 Drawing No. E-LOU-ll2-004 V-5:
Zone 5 Plan and Schedule Sheets Pressurizer Drawing No. E-LOU-112-005 VI.
Exclusions and Exceptions
.p d VII.
Quality Assurance
-Quality Assurance Manual Program'Contrdis Procedure'for Inservice Inspection II-l
Date:
7/28/75 Revision:
0 By:
({}
TABLE OF CONTENTS (Cont'd.)
VIII.
Report Submissions Report Information IX.
UT Calibration Standards
^
List of UT Calibration Standards Drawings of.UT Calibration Standards
,X.
Remote Equipment Photographs of Remote Equipment XI.
Procedures Procedure Philosophy n
UT Procedure Outline U
List of F>ocedures XII.
Evaluation Criter'ia 6
l i
l l
C:)
,m
.-,w--,
Date:
2-013 Revision:
_ _1, LIST OF EFFECTIVE PAGES The following pages are those that are in effect on date above.
Superseded paces should be removed and replaced by those that are in effect.
Refer to the Record of Revision for changes and notations.
Missing pages may be obtained from:
Combustion Engineering, Inc.
Engineering Development and Services Manager, Field Inspection Services 1000 Prospect Hill Road Windsor, Connecticut 06095 Date Section age Rev.
Section Date Section age Date u
i 1
2/01/77 001 004 l Introduction 1
1 2/01/77 Sh.2 1
1/22/75 Sh.1 1
1/21/75:
004 Table of Con-1 0
7/28/75 Zone 2 1
0 7/28/75 Sh.2 1
1/21/75, tents 2
0 7/28/75 2
0 7/28/75 3
l 0 7/28/75 Zone 5 1
1 2/01/77 Revision 1
1 2/01/77 4
0 7/28/75 2
1 2/01/77 Record 2
1 2/01/77 5
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0 7/28/75 3
1-2/01/77 6
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0 7/28/75 P-9am 4
1 2/01/77 7
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1 2/01/77 8
0 7/28/75 e cription 2
1 2/01/77 9
0 7/28/75 005 0
12/18/74 10 0
7/28/75 Examination 1
0 7/28/75 11 0
7/28/75 Exclusions 1
1 2/01/77l; Area Program 2
1 2/01/77
,12 0 l7/28/75 and 2
1 2/01/77 Sheets 13
'0 7/28/75 Exceptions 3
1 2/01/77-l14
'0 l7/28/75 Zonc 1 1
1 2/01/77
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l 2
1 2/01/77 16 0
7/28/75 t
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3 1
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6 0
7/28/75
'002, 1 7/19/76 Assurance 1
1 2/01/77 l
7 0
7/28/75 Program l
8 0
7/28/75 l
Zone 3 1
1 2/01/77 Controls 8
9 1
2/01/77' 2
1 2/01/77 Procedure l
10 1
2/01/77 3
0 7/28/75 for Inser-11 1
2/01/77 4-0 7/28/75 vice Inspec-12 1
' 2/01/77 5
1 2/01/77 tion All 1
4/9/75 l
13 1
2/01/77 l
14 1
'2/01/77
- 003 Report 15 1
2/01/77
'Sh.l '1 1/22/75 Submissions 1
1 2/01/77 16 1
2/01/77 17 0
7/28/75 003 Calibration 1
1 2/01/77l C
18 0
7/28/75
- Sh.2 1
Ll/22/75 l Standards 2
1 2/01/77 l
19 0
17/28/75 20 0
'7/28/75 Zone 4 1
1 2/01/77 Calibration 2'
1 2/01//7 Standard 001 3
0 7/28/75 Drawings see Page 2 above Sh.1 1
I/22/75 4
0 7/28/75l 5
1 2/01/77
Date:
?.,/JL1j77 Revision:
1 O
LIST OF EFFECTIVE PAGES V
(Continued)
Page Rev.
Page Rev.
Page Rev.
l Section No.
No.
Date Section No.
No.
Date Section No.
Nn.
Date Remote 1
1 2/01/77 Eq ipa nt 2
1 2/01/77 3
1 2/01/77 Fi g.1 1
2/01/77 Fi g. 2 1
2/01/77 Fi g. 3 1
2/01/77 Fi g.4 1
2/01/77 Fig.5 1
2/01/77 Fi g.6 1
2/01/77 Fig.7 1
2/01/77 Procedures 1
1 2/01/77 2
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1 2/01/77 7
1 2/01/77 0
E kjtion Ci. ceria
~l i
2/01/77
. ASME Section XI 1974 Edi-All
~ 7/1/74 tion / Summer 1974 Addenda All 6/30/74 4
END OF !.IST ( F EFFECTI"E PA(!ES
(
)
oU
Section:
III Page:
1 of 2 RECORD OF REVISIONS Revision:
1 Effective Date: 2-01-77 Approved:
Approved:
Rev.
Section/
Page Date Description Paragraph 01 Abstract 11 2-01 Editorial - to reflect examinations as completed.
~
Introduction I-l
' Editorial - to reflect examinations as completed.
Addition of Volume 5 to list of volumes List of effec III-l Address change - Departmental Reorgani-tive pages.
zation.
Editor'al - to reflect examinations
- Program Des-IV-1, 2 i
cription as completed.
Examination V-2 Primary side manway bolting not exa-Area Desig-mined.
II nation Code Program Plan V-1.1 Procedures added to items01-009 and Schedule V-1.2 through 01-013.
V-1.3 Circunferential" deleted from item 01-020.
Procedure NIP-230 added to item 01-020.
'urface examinations not performed.
V-1.9 -
S V-1.16 Drawing E-LOV-112
- hange clad ~ patch location to conform l
-002 to as-builts.
V-3.1 -
JT-2 was UT-3 on items03-002 through V-3.2 33-016.
l 33-022 and 03-023 not examined in shop.
V-3.5
)3-057 and 03-058 not examined in shop.
V-4.1 -
JT-2 was UT-3 on items04-002 through V-4.2
)4-016.
)4-022 and 04-023 not examined in shop.
V-4.5
)4-057 and 04-058 not examined in shop.
I V-5.1 JT-4 was UT-5.
V-5.2 I)S-020 Not examined in shop.
Exclusions and VI-1,2,3 Editorial-to reflect examinations as Exceptions completed, including deletior, of irrele-vant paragraphs.
Section:
III Page:
2 of 2 RECORD OF REVISIO.NS Revision:
1 Effective Date:
2-01-77 Approved:
Approved-Rev.
Section/
Page Date Description Paragraph Quality Assur-2-01' 77 '
Nuclear Laboratories Quality Assurance i
ance
. Manual deleted; Introduction added.
Report Sub-VIII-l Editorial-Reflect examinations as com-missions pleted.
Addition of supplemental vol-ume numbers.
UT Calibratior IX-1 Editorial-Reflect examinations as com-Standards pleted.
IX-2 Final revisions of drawings listed.
Remote Equip-Sect. X; General editorial revision.
ment All 1
4 g 01 Procedures XI-l Editorial - to reflect examinations a's completed.
XI-5, 6, 7 Revision numbers of procedures added.
Evaluation XII-1 Editorial - to reflect examinations as Criteria completed.
Date:
2-01-77 6
Revision:
1 By:
IIG
,Q PROGRAM DESCRIPTION This program has been prepared for the preservice (baseline) examination of the major components of the Waterford III Steam Electric Station nuclear power station. With exceptions noted below, all volumetric examinations on_the components (pressure vessel, steam generators, and pressurizer) have been done by ultrasonics in the fabrication shop soon after the component hydrostatic test. Some visual and surface examinations have been done in the shop. The remainder of'the examinations on these components will be performed after field erection by the examination contractor selected to perforn the complete field preservice examination.
The Program Plan and Schedule Sheets in Section V of this volume list the examinations done in
-the shop.
The components have been divided into smaller areas of interest called zones.
Each zone is depicted on a drawing which locates all the welds and other examination areas for that component. The applicable Plan and Schedule Sheets accompany each zone drawing and provide all the informa-l tion necessary for qualified examiners to perform the various required ex-aminations.
The information includes the zone' drawing number, procedure to be used in performing the examination, method of examination, calibra-O ~ tion standard (for UT examinations), and a brief suninary of the examina-tion requirements as defined by the ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuc1' ar Power Plant Compo-e nents.-
l Each' weld or other area of interest has been given a unique designation number.
For most examination areas the number consists of two parts:
(1) a two-digit number which identifies a' specific component and is iden-tical with the zone number for the component; (2) a sequence number which identifies the area individually. The numbering system is more fully described in Section V of this volume.
A description of the program for each component follows:
The longitudinal seam welds, the upper shell to middle shell circumferen-tial weld, the middle shell to lower shell circumferential weld, the upper portion of the lower shell to bottom head weld, the shell side of the flange to shell weld, the nozzle to shell welds, and the nozzle inner radii were examined from the inside (ID) surface, using remote equipment (described
.later). The lower shell to bottom head circumferential weld, the longi-tudinal seam welds in the tapered part of the lower shell, and the bottom head welds were examined manually from the outside (00) surface. The liga-ment areas between the bolt holes on the flange and the flange to upper Q.
shell.circumferential weld were examined with remote equipment (described later) from the upper flange surface.
The closure studs and nuts were exanined manually. The cladding, snubber lugs, and core stop lugs were l
I examined visually using television. equipment mounted on the same remote equip-ment used to perform the ultrasonic examinations of the vessel shell welds.
L m
Date:
2-01-77 Revision:
1 By: IIG Reactor Pressure Vessel Closure Head All ultrasonic examinations were done manually, The flange weld was done from the ID and the OD, and the dome weld from the ID.
The accessible portions of the longtiudinal (Peel Segment) welds were done from both the OD and the ID. The instrument nozzle welds were done from the ID.
CEDM nozzle housing and extension welds have been included in this program for identification purposes. They were not a part of this preservice program.
Steam Generators All~ shop examinations on both the primary and secondary sides were performed manually, and these examinations were carried out from the OD surface.
The one exception to this statement is the stay cylinder welds, which are in high radiation areas with difficult access.
The inservice examinations of those welds will be done with remote equipment, and, accordingly, the preservice exa-mination must use the.same equipment.. Certain of the equipment is permanently attached to the steam generator assembly in the field, and the stay cylinder examination must be done in the field by the field baseline examination con-
.(-
tractor. The stay cylinder welds have been included in this. program for iden-tification purposes; the examination of these welds was. not a part of this shop preservice program.
m Pressurizer All examinations were performed manually from the OD surface.
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Date:
7/28/75 Revision:
0 By:
o EXAMINATION AREA DESIGNATION CODE Identification of the inspection areas becomes important to implement record keeping and to permit rapid location of the inspection areas.
To achieve this, all primary system component welds and other inspection areas have been assigned a unique numerical identification. For most examination areas the number consists of two parts:
(1) a two-digit number which identifies a specific component and is identical with the zone number for the component; and (2) a sequence number which identifies the area individually.
The weld or other examination area is referenced to a specific component by the following numerical designation:
01 -- Reactor Vessel 02 -- Reactor Vessel Closure Head 03 -- St'eam Generator #1 04 -- Steam Generator #2 05 -- Pressurizer Q
t Those components or areas which have been assig~ned sequential number in the design of the NSSS are referenced by the following designation:
01-L-nn -- Reactor Pressure Vessel Flange Ligament Area Around Stud Hole #nn 01-S-nn -- Reactor Vessel Closure Stud #nn 01-N-nn -- Reactor Vessel Closure Nut #nn l
01-W-nn -- Reactor Vessel Closure Washer #nn 02-T-nn -- Closure Head Instrument Nozzle #nn Tube to Flange Weld 02-U-nn -- Closure Head Instrument Nozzle #nn to Head Weld 02-V-nn. -- Closure Head CEDM Nozzle #nn to Head Weld 02-W-nn -- Closure Head CEDM Motor Housing Lower Weld at Location
- nn (peripheral housings only)
-0 02-v-aa -- ciosure sead ceDM upper Mousias 'ower Weld et Locatioa I
~
- nn (peripheral housings only)
V-1
Date: 2-01-77 Revision: 1 By: IIG
(
The pressurizer heater penetrations have been assigned sequential numbers for the purposes of this program.
The manways on the secondary sides of the steam generators received a visual examination. The description of any indication found would have included a reference to the nearest stud hole (s), with the numbering proceeding clock-wise from the uppermost point on the bolt circle of the manway.
. There are a large number of areas which are listed as receiving visual exam-inations.
In reality, there are two separate classes of visual examinations.
Certain areas, such as bolting, some component supports, and vessel interiors and cladding, are required by Tables IWB-2500 and IWC-2600 for the Class 2 areas. The other areas which receive visual examinations are the Class 1
. partial penetration welds (Category B-E) and the Clas:,1 (Category B-P) and Class 2 areas exempted by Paragraph IWB-1220 (Class 1) and Paragraph IWC-1220 (Class 2) from the requirements of the more exacting examinations.
These areas receive the visual examinations for evidence of leakage required by Paragraph IWA-5000 during the system hydrotests of Paragraphs IWB-5000 and IWC-5000.
In the " Examination Method" column of the following tables, the first class of areas has its method listed as "Vis." and the second. class is listed with "Vis.-H".
O fV Examinations for those. areas whose method is listed as "Vis.-H" will be per-
\\
formed in the field by the e'xaminatfori contractor selected to perform the Field Preservice Examinations. The only other examinations listed in the following tables which were not done in the fabrication shop are the ultra-sonic examinatiens of the stay cylinder welds of the steam generators and of the CEDM housing welds.
In the following tables, all Class 2 areas may be identified as those with a category whose first letter is "C".
These areas are governed by Paragraphs IWC-2500 and IWC-2600.-
In all cases,: attempts were.made to examine 100% of all welds and other exam-ination areas listed.. Where design considerations preclude 100% examinations, the applicable procedures list the extent of examination possible. Any further
- restrictions found during the course of the examinations are described in the
~
issued report of the examinations.
f J
t
.o
-V-2
~
PROGRAM PLAN AND SCHEDULE Z0'NE 1 REACTOR PRESSURE VESSEL R:ference Drawing No.:
E-LOU-ll2-001 i
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Bloc k -No.
Examination IWB-2500 IWB-2600 01-0'01' Bottom Head Dome to Peel Segment Torus B-B Vol.
NIP-232 UT-4 1/2T beyond edge of weld 01-002 Peel Segment to Peel Segment at 30* Orienta-tion 01-003 Peel Segment to Peer Segment at 90* Orienta-tion 01:004 Peel Segment to Peel Segment at 150* Orienta-tion 01-005 Peel Segment to Peel Segment at 210* Orienta-tion-01-006 Peel Segment to Peel Segment at 270* Orienta-tion 01-007 Peel Segment to Peel Segment at 330* Orienta-tion V
V 01-008 Bottom Head Assembly to Lower Shell Circum-ferential Weld
~
y NIP-230 UT-2 NIP-232 01-009 Lower Shell Course Longitudinal Weld at 90*
B-A NIP-230 y
y Orientation y
NIP-231 NIP-232 Date:
2-01-77 V-1.1 Revision:
1 j
i m
~
O O
O PROGRAM PLAN AND SCHEDULE ZONE 1 REACTOR PRESSURE VESSEL Reference Drawing No.:
E-LOU-ll2-001
\\
Weld Examination Examination Procedure Calibration Extent of Designation Weld ' Description Category Method Number Block No.
Examination IWB-2500 IWB-2600 01-010 Lower Shell Course Longitudinal Weld at 210
, B-A Vol.-
NIP-230 UT-2 1/2T b'eyond Orientation NIP-232 edge of weld f
01-011 Lower Shell Course Longitudinal Weld at 330*
Orientation 7
01-012 Lower Shell Course to Middle Shell Course -
NIP-230 Circumferential NIP-231 y
01-013 Middle Shell Course Longitudinal Weld at 90*
B-B Orientation
$/
01-014 Middle Shell Course Longitudinal Weld at NIP-230 210 Orientation 01-015 Middle Shell Course Longitudinal Weld at 330* Orientation 01-016 Middle Shell Course to Upper Shell Course -
Circumferential if 01-017 Upper Shell Course Longitudinal Weld at 90*
UT-1 Orientation 01-018 Upper Shell Course Longitudinal Weld at 210*
Orientation 01-019 Upper Shell Course Longitudinal Weld at 330*
I Orientation Il
'I if V
3 Date:
9 -n1_.77 V-1.2 Revision:
1
.Jx O
'o
~
d PROGRAM PLAN AND SCHEDULE ZONE 1 REACTOR PRESSURE VESSEL j
Reference Drawing No.:
E-LOU-112-001 I
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IWB-2600
.01-020.
Upper Shell Course to Flange B-C Vol.
. NIP-233 UT-8 100% of weld NIP-230 UT-1 volume above, I
UT-9 or 10 100% of weld 1/2T below 01-021 Outlet Nozzle to Shell at 0* Orientation B-D NIP-235 NIP-230 UT-1 from bore',01-022 Inlet Nozzle to Shell at 60* Orientation 1/2T beyond edge'of weld 01-023 Inlet Nozzle to Shell at 120* Orientation from shell 01-024 Outlet Nozzle to Shell at 180* Orientation 01-025 Inlet Nozzle to Shell at 240* Orientation 01-026 Inlet Nozzle to Shell at 300* Orientation y
01:027 Outlet Nozzle Inner Radius at 0 Orientation NIP-236 100% of radius01-028 Inlet Nozzle Inner Radius at 60* Orientation 01529 Inlet Nozzle Inner Radius at 120* Orientation
~
I 01-030 Outlet Nozzle Inner Radius at 180* Orienta-tion 01-031 Inlet Nozzle Inner Radius at 240* Orientation i
].01-032 Inlet Nozzle Inner Radius at 300* Orientation V
y y
y y
i Date:
2-01-77 a
l V-1.3 Revision:
1
O O
O PROGRAM PLAN AND SCHEDULE ZONE 1 REACTOR PRESSURE VESSEL R:ference Drawing No.:
E-LOU-112-001 Weld Examination Examination Procedure Cal'.bration Extent of Designation Weld Description Category Method Number B'ock No.
Examination
'IWB-2500 IWB-2600 l
01-033 Vessel Cladding at 150* Orientation and 133" B-I-1 Vis.
00000-36 sq. in.
Below Flange Surface ESS-002 patch-01-034 Vessel Cladding at 150* Orientatien and 244" Below Flange Surface',01-03d vessel Cladding at 150* Orientation and 355" Below Flange Surface
~~
4 j
01-036 Vessel Cladding at 300* Orientation and 133" Below Flange Surface a
1 01.037 Vessel Claddin'g at 300* Orientation and 244" Below Flange Surface 01-D38 Vessel Cladding at 300* Orientation and 355" Below Flange Surface
~ V V
/
5 01-039 Snubber Lug at 0* Axis B-N-2 All of snub-ber 01-040 Snubber Lug at 60* Axis01-041 Snubber Lug at 120* Axis01-042 Snubber Lug at 180* Axis V
v 01-043 Snubber Luo at 240* Axis i
Date:
7/28/75 V-1.4 Revision:
n i
O O
O PROGRAM PLAN AND SCHEDULE-ZONE 1 REACTOR PRESSURE VESSEL Reference Drawing No.:
E-L00-112-001 Weld Examination Examination Procedure Calibration Extent of Designation Weld Descripcion Category Method Number Block No.
Examination IWB-2500 IWB-2600 01-044 Snubber Lug at 300* Axis B-N-2 Vis.
00000-All of.
ESS-002 snubber 01-045 Core Stop Lug at 10' Location All of lug 01-046 Core Stop Lug at 40' Location 01-047 Core Stop Lug at 85* Location 01-048 Core Stop Lug at 130' Location I
i 01-049 Core Stop Lug at 160* Location 51-0,5,0 Core Stop Lug.at 205* Location t
01-051 +,
Core Stop Lug at 250* Location 01-052 Core Stop Lug at 280* Location i
01-053 Core Stop Lug at 325' Location y
y i
i.
Date:
U28m V-1'5 j
Revision:
0
_~
l O
1 PROGRAM PLAN *AND SCHEDULE ZONE 1 f
REACTOR PRESSURE VESSEL Reference Drawing No.:
E-LOU-ll2-001 f
i I
l Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IWB-2600 i'
01-L-1 Flange Ligament Area Around Stud Hole il B-G-1 Vol.
NIP-234 UT-8 Complete Area and volume to 01-L-2 Flange Ligament Area Around Stud Hole #2 depth of l
stud hole 01-L-3 Flange Ligament Area Around Stud Hole #3 01-L-4 Flange Ligament Area Around Stud Hole #4 01-L-5 Flange Ligament Area Around Stud Hole #5 01 -L-6 Flange Ligament Area Around Stud Hole #6 01-L-7 Flange Ligamerit Area Around Stud Hole #7
}
01-L-8 Flange Ligament Area Around. Stud Hole #8 l
01-L-9 Flange Ligament Area Around Stud Hole #9 01-L-10 Flange Ligament Area Around Stud Hole #10 4
01-L-11 Flange Ligament Area Around Stud Hole ill i
l 01-L-12 Flange Ligament Area Around Stud Hole #12 01-L-13 Flange Ligament Area Around Stud Hole #13
]
if i f if h/
hl Date:
7/20/75 i
i V-l.6 Revision:
0
y i'._
}
PROGRAM PLAN AND-SCHEDULE ZONE 1 REACTOR PRESSURE VESSEL Reference Drawing No.: E-LOU-112-001 Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category
. Method Number Block No.
Examination IWB-2500 IWB-2600 014L-14 Flange Ligament Area Around Stud Hole #14 B-G-1 Vol.
NIP-234 UT-8 Complete Area and l
01-L-15 Flange Ligament Area Around Stud Hole #15 j,
of 0
stud hold
'01-L-16 Flange Ligament Area Around Stud Hole #16 j
01-L-17 Flange. Ligament Are'a.Around Stud Hole #17 01-L-18 Flange Ligament Area Around Stud Hole #18 Ol-L-19 Flange Ligament Area Around Stud Hole fl9 i
i 01-L-20 Flange Ligament Area Around Stud Hole #20 Ol=L-21 Flange Ligament Area Around Stud Hole #21 l
j 01-L-22 Flange Ligament Area Around Stud Hole #22 01-L'-23 Flange Ligament Area Around Stud Hole #23 01-L-24 Flange Ligament Area Around Stud Hole #24 I
01-L-25 Flange Ligament Area Around Stud Hole #25 01-L-26 Flange Ligament Area Around Stud Hole #26 01-L-27 Flange Ligament Area Around Stud Hole #27 01-L-28 Flange Ligament Area Around Stud Hole #28 y
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i Date:
7/28/75 V-1.7 Revision:
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. PROGRAM PLAN AND SCllEDULE ZONE 1 R3ference Drawing No.:
E-LOU-ll2-001.
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No~
Examination IWB-2500 IWB-2600 01-t-29 Flange Ligament Area Around Stud Hole #29 B-G-1 Vol.
NIP-234 UT-8 Complete Area and 01-L-30 Flange Ligament Area Around Stud Hole #30 volume to depth of, 01-L-31 Flange Ligament Area Around Stud Hole #31 stud hole 01-L-32 Flange Ligament Area Around Stud Hole #32
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01-L-33 Flange Ligament Area Around Stud Hole #33 01-L-34 Flange Ligament Area Around Stud Hole #34 1
01-L-35 Flange Ligament Area Around Stud Hole #35 4
Ol_-L-36 Flange.L'igament Area'Around Stud Hole #36 01-L-37 Flange Ligament Area Around Stud Hole #37 01-L-38 Flange Ligament Area Around Stud Hole #38 01-L-39 Flange Ligament Area Around Stud Hole f39 01-L-40 Flange Ligament Area Around Stud Hole #40 01-L-41 Flange Ligament Area Around Stud Hole #41 01-L-42 Flange Ligament Area Around Stud Hole #42 01-L-43 Flange Ligament Area Around Stud Hole #43 V
V V
V V
Date:
7/28/75 4
V-1.8 Revision:
0
O
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PROGRAM PLAN AND SCHEDULE ZONE 1 R:ference Drawing No.:
E-LOU-112-001
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IWB-2600 01-L-44 Flange Ligament Area dround Stud Hole #44 B-G-1 Vol.
NIP-234 UT-8 Complete Area and 01-L-45 Flange Ligament Area Around Stud Hole #45 volume to depth of 01-L-46 Flange Ligament Area Around Stud Hole #46 stud hoTe 01-L-47 Flange Ligament Area Around Stud Hole #47 01-L-48 Flange Ligament Area Around Stud Hole #48 1
01-L-49 Flange Ligament Area Around Stud Hole #49 01-L-50 Flange Ligament Area Around Stud Hole #50 i
01-L-51 FlangeL{gamentAreaAroundStudHole#51-01-L-52 Flange Ligament' Area Around' Stud Hole #52 01-L-53 Flange Ligament Area Around Stud Hole #53
.01-L-54 Flange Ligament Area Around Stud Hole #54 y
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NIP-241 UT-20 Total Volume 01-S-2 Stud #2 01-S-3 Stud #3 01-S-4 Stud #4 V
V V
V V
Date:
2-01-77 l
V-1.9 Revision:
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PROGRAM PLAN AND SCHEDULE ZONE 1 R ference Drawing No.:
NONE REACTOR PRESSURE VESSEL i
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IWB-2600 01-S~5-Stud #5 B-G-1 Vol.
NIP-241 UT-20 Total Volume 01-S-6 Stud #6 01-S-7 Stud #7 01-S-8 Stud #8 4
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01-S-11 Stud #11 01-S-12 Stud #12' 01-S-13 Stud #13 i
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01-S-15 Stud #15 01-S-16 Stud.#16 01-S-17 Stud #17 01-S-18 Stud #18 01-S-19 Stud #19 y
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V-1.10 Revision:
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NONE 4
i Weld Examination Examination Procedure Calibration Extent of
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Designatian Held Description Category Method Number i
IWB-2500 IWB-2600 Block No.
Examination 01-S-3S Stud #35 B-G-1 Vol NIP-241 UT-20 Total Volume 01-S-36 Stud #36 01-S-37 Stud #37 01-S-38 Stud #38 01-S-39 Stud #39 i
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_Z_01-77 j
V-1.12 Revision:
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Examination IWB-2500 IWB-2600 014S-50 Stud #50 B-G-1 Vol.
NIP-241 UT-20 Total Volume 01-S-51 Stud #51 01-S-52 Stud #52 01-S-53
. Stud #53 01-S-54 Stud #54 V
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I Date:
2-01_77 V-1.13 Revision:
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Examination IWB-2500 IWB-2600 Ol*-N-26 Nut #26 B-3-1 Vol.
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I Volume 01-N-27 Nut #27
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V V
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i Date:
2-01-77 V-1.15 Revision:
1 i-4
C 3
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Refcrence Drawing No.:
NONE REACTOR PRESSURE VESSEL i
Weld Examination Examination Procedure Calibration Extent of L
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Examination IWB-2500 IWB-2600 012N-41 Nut #41 B-G-1 Vo'l.
NIP-241 UT-21 Total Volume 01-N-42 Nut #42
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2-01-77 1
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Examination
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7/28/75 i
V-1.19 Revision:
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NONE i
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IW8-2500 IWB-2600-01'-W-46 Washer #46 B-G-1 Vis.
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Examination IWB-2500 IWB-2600 02-001 Flange to Peel Segment Torus B-C Vol.
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02-003 Peel Segment to Peel Segment at 90' Orienta-tion - from OD Surface 02-004 Peel Segment to Peel Segment at-180' Orienta-J tion - from 00 Surface 02-005 Peel Segment to Peel Segment at 270' Orienta-tion - from 00 Surface
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02-006 Peel Segment to Peel Segment at O' Orienta-tion - from ID Surface 02-007 Peel Segment to' Peel Segment at 90' Orienta-tion.- from ID Surface 02-008 Peel Segment to Peel Segment. at 180 Orienta-tion - from ID Surface 02-009 Peel Segment to Peel Segment at 270* Orienta-i tion - from ID Surface 02-010 Dome to Peel Segment Torus y
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1 Date:
7/28/75 V-2.1 Revision:
0
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E-LOU-ll2-002 Weld Examination Examination Procedure Calibration Extent of Designation
. Weld ~ Description Category Method Number Block No.
Exa:nination IWB-2500 IWB-2600 02-011 Clad Patch Counterclockwise of 0* Weld, Below B-I-l Vis., surf.
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Examination IWB-5 IWB-2600 4-02-V-1 CEDM Nozzle il to Head B-E Vis.-H 00000-Surrounding
.ESS-029 area 02-V-2 CEDM Nozzle #2 to Head i
r 02-V-3 CEDM Nozzle #3 to Head 02-V-4 CEDM Nozzle #4 to Head
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02-V-5 CEDM Nozzle #5 to Head i
02-V-6 CEDM Nozzle #6 to' Head 1
02-V-7 CEDM Nozzle #7 to Head 02-V-8 CEDM Nozzle #8'to Head 02-V-9 CEDM Nozzle #9 to Head i
i 02-V-10 CEDM Nozzle #10 to Head I
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02-V-12 CEDM Nozzle #12 to Head j
02-V-13 CEDM Nozzle #13 to Head 02-V-14 CEDM Nozzle #14 to Head y
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7/28/75 4
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uc r,.3 n acw m.: c aer rcgru. mci.d ad Revision:
0
O O-O PROGRAM PLAN AND SCHEDULE ZONF 2 REACTOR VESSEL CLOSURE HEAD Reference Drawing No.: E-LOU-112-002 Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IWB-2600 02-V-15 CEDM Nozzle #15 to Head B-E Vis.-H 00000 Surrounding ESS-029 area 1
02-V-16 CEDM Nozzle #16 to Head
+
02-V-17 CEDM Nozzle #17 to Head l
02-V-18 CEDM Nozzle #18 to Head 02-V-19 CEDM Nozzle fl9 to Head 02-V-20 CEDM Nozzle #20 t6 Head j
1 02-V-21 CEDM Nozzle #21 to Head
.i 02-V-22 CEDM Nozzle l'22 to Head 02-V-23' CEDM Nozzle #23 to Head I
02-V-24 CEDM Nozzle #24 to Head i
j 02-V-25 CEDM Nozzle #25 to Head 02-V-26 CEDM Nozzle #26 to Head j
02-V-27 CEDM Nozzle #27 to Head l
02-V-28 CEDM Nozzle #28 to Head if i/
V V
1 i
Date:
7/28/75 V-2*5 Revision:
0
_ - _ _ ~
o
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PROGRAM PLAN AND SCHEDULE ZONE 2 REACTOR VESSEL CLOSURE HEAD Reference Drawing No.:
E-LOU-112-002 i
i Weld Examination Examination Procedure Calibration Extent of Designation Weld ~ Description Category Method Number Block No.
Examination i
t IWB-25m)
IWBe2600 02-V-29 CEDM Nozzle #29 to Head B-E Vis.-H 00000-Surround.ing ESS-029 area
]
02-V-30 CEDM Nozzle #30 to Head i
02-V-31 CEDM Nozzle #31 to Head 02-V-32 CEDM Nozzle #32 to-Head 4
02-V-33 CEDM Nozzle #33 to Head l
02-V-34 CEDM Nozzle #34 to Head 02.-V-35 CEDM Nozzle #35 to Head 02-V-36 CEDM Nozzle #36-to Head l
0?-V-37 CEDM Nozzle #37 to Head l
02-V-38 CEDM Nozzle #38 to Head
}
02-V-39 CEDM Rzzle #39 to Head i
02-V-40 CEDM Nozzle #40 to Head i
02-V-41 CEDM Nozzle #41 to Head 02-V-42 CEDM Nozzle #42 to Head i
i 02-V-43 CEDM Nozzle #43 to Head
-\\/
T/
h/
V i
i Date:
7/28/75 l
i V-2.6 Revision:
o j
~
O O-O PROGRAM PLAN AND SCllEDULE ZONE 2 REACTOR VESSEL CLOSURE HEAD Reference Drawing No.:
E-LOU-112-002 i
Weld Examination Examination Procedure Calibration Exteat of Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IWB-2600 02-V-44 CEDM Nozzle #44 to Head.
B-E Vi s.-H 00000-Surrounding ESS-029 area 02-V-45 CEDM Nozzle #45 to Head 02-V-46 CEDM Nozzle #46 to' Head 02-V-47 CEDM Nozzle #47'to Head 02-V-48 CEDM Nozzle #48 to Head j
02-V-49 CEDM Nozzle #49 td Head 02-V-50 C,EDM Nozzle #50 to Head 02-V-51 CEDM Nozzle #81 to Head 02-V-52' CEDM Nozzle #52 to Head 02-V-53 CEDM Nozzle #53 to Head l
02-V-54 CEDM Nozzle #54 to Head 02-V-55 CEDM Nozzle #55 to Head j
02-V-56 CEDM Nozzle #56 to Head 02-V-57 CEDM Nozzle #57 to Head y
y y
y i
Date:
7/28/75 V-2.7 Revision:.
O
{
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PROGRAM PLAN AND SCHEDULE ZME 2 V
L CLO W E H W Reference Drawing No.:
E-LOU-112-002 Weld Examination Examination Procedure Calibration Extent of j.
Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IW8-2600 02-V-58 CEDM Nozzle #58 to Head B-E Vis.-H 00000 Surrounding i
ESS-029 area I
02-V-59 CEDM Nozzle #59 to Head I
j 02-V-60 CEDM Nozzle #60 to Head 02-V-61 CEDM Nozzle #61 to Head 02-V-62 CEDM Nozzle #62 to Head t'
02-V-63 CEDM Nozzle #63 to Head l
4 l
02-V-64 CEDM Nozzle #64 to Head l
j 02-V-65 CEDM Nozzle #65 to Head 02-V-66 CEDM Nozzle #66 to Head i
i l
02-V-67 CEDM Nozzle #67,to Head 1
}
02-V-68 CEDM Nozzle #68 to Head 02-V-69 CEDM Nozzle #69 to Head i
j 02-V-70 CEDM Nozzle #70 to Head i
~
02-V-71 CEDM Nozzle #71 to Head j
02-V-72 CEDM Nozzle #72 to Head if i f V
II l
i
~
l Date:
7/28/75 V-2.8 Revision:
0
,s Q
O O
PROGRAM PLAN AND SCHEDULE ZONE 2 REACTOR VESSEL CLOSURE HEAD Reference Drawing No.:
E-LOU-112-002 i
Weld Examination Examination Procedure Calibration Extent of Designation Wald' Description Category Method Number Block No.
Examination IW8-2500 IW8-2600 02-V-73 CEDM Nozzle #73 to Head 8-E Vis.-H 00000-Surrounding ESS-029 area 02-V-74 CEDM Nozzle #74 to Head 02-V-75 CEDM Nozzle #75 to Head 02-V-76 CEDM Nozzle #76 to Head
~
02-V-77 CEDM Nozzle #77 to Head 02-V-78 CEDM Nozzle #78 to, Head 02-V-79 CEDM Nozzle #79 to Head 02-V-80 CEDM Nozzle #80 to Head 02-V-81.
CEDM Nozzle #81, to Head 02-V-82 CEDM Nozzle #82 to Head s-02-V-83 CEDM Nozzle #83 to Head 02-V-84 CEDM Nozzle #84 to Head 02-V-85 CEDM Nozzle #85 to Head 02-V-86 CEDM Nozzle #86 to Head 02-V-87 CEDN Nozzle #87 to Head V
V V
V Date:
7/28/75 V-23 Revision:
0
O O
O i
g i
PROGRM PLAN AND SCEDULE 20NE 2 REACTOR VESSEL CLOSURE HEAD i
Reference Drawing No.:
E-LOU-112-002 l
I Weld Examination Examination Procedure Calibration Extent of j
Designation Weld Description Category Method Number Block No.
Examination IWB-2500 1 6 2600 02-V-88 CEDM Nozzle #88 to Head bee Vis.-H 00000-Surrounding area l
1 ESS-029 02-V-89 CEDM Nozzle #89 to Head 02-V-90 CEDM Nozzle #90 to Head t
i 02-V-91 CEDM Nozzle #91 to Head
.i f V
if if EXAMINATIONS LISTED BELOW~ BONE IN THE FIELD I
L i.e-02-W-60 CEDM Motor Housing Lower Weld at Location #60 0-0 Vol.
NIP-239 UT-1/2T beyond
)
edge of weld l
02-W-61 CEDM Motor Housing Lower Weld at Location #61 1
i 02-W-62 CIDM Motor Housing Lower Weld at Location #62 l
02-W-63 CEDM Motor Housing Lower Weld at Location J63 i
l 02-W-64.
CEDM. Motor Housing Lower Weld at Location #64 l
l 02-W-65 CEDM Motor Housing Lower Weld at Location #65 f
i l
02-W-66 CEDM Motor Housing Lower Weld at Location #66 l
32-W-67 CEDM Motor Housing Lower Weld at Location #67 l
02-W-68 CEDM Motor Housing Lower Weld at Location #68 j
02-W-69 CEDM Motor Housing Lower Weld at Location #69 V
V hl V
,i wwdm twuwwrnd w oevnuf>
O rea rnesc waas sas Psz xtsww ny.wr Date:
7/28/75
[
gJ(sa-,S.-g3 V-2.10 Revision:
0 i
O O-O PROGRM PLAN MD SCHEDULE 20NE 2 REACTOR VESSEL CLOSURE HEAD Reference Drawing No.:
E-LOU-il2-002 Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWE-2500 In-2600 02-W-70 CEBM Motor Housing Lower Weld at Location #70 B-0 Vol.
NIP-239 UT-1/2T beyond edge of weld 02-U-71 CEDM Motor Housing Lower Weld at Location #71 02-W-72 CEIM Motor Housing Lower Weld at Location #72 02-W-73 CEDM Motor Housing Lower Weld at Location #73 02-W-74 CEDM Motor Housing Lower Weld at Location #74 02-W-75 CEDM Motor Housing Lower Weld at Location #75 02-W-76 CEDM Motor Housing Lower Weld at Location #76 02-W-77 CEDM Motor Housing Lower Weld at Location #77 02-W-78 CEDM Motor Housing Lower Weld at Location #78 02-W-79 CEDM Motor Housing Lower Weld at Location #79 02-W-80 CEDM Motor Housing Lower Weld at Location #80 02-W-81 CEDM Motor Housing Lower Weld at Location #81 02-W-82 CEIM Motor Housing Lower Weld at Location #82 02-W-83 CEDM Motor Housing Lower Weld at Location #83 02-W-84 CEDM Motor Housing Lower Weld at Location #84 V
V V
V U
~
Date:
7/28/75 V-2.1.1 Revision:
0 t
O O'
O PROGRAM PLAN AND SCHEDULE ZONE 2 REACTOR VESSEL CLOSURE HEAD
[
Refcrence Drawing No.:
E-L00-112-002 I
Weld Examination Examination Procedure Calibration Extent of i
l Designation Wald Description Category Method Number Block No.
Examination i
IW8-2500 IWB-2600 4
j 02-W-85 CEDM Motor Housing Lower Weld at Location #85
- 5. v Vol.
NIP-239 UT-1/2T beyond edge of weld 02-W-86 CEDM Motor Housing Lower Weld at Location #86 02-W-87 CEDM Motor Housing Lower Weld at Location #87 i
j 02-W-88 CEDM Motor Housing Lower Weld at Location #88 l
02-W-89 CEDM Motor Housing Lower Weld at Location #89 02-W-90 CEDM Motor Housing Lower Weld at Location #90 02 W-91 CEDM Motor Housing Lower Weld at Location !91 1
j 02-X-60 CEDM Motor Housing Upper Weld at Location #60 UT-2 02-X-61 CEDM Motor Housing Upper Weld at Location #61 t
02-X-62 CEDM Motor Housing Upper Wt.id n Location #62 f
02-X-63 CEDM M'otor Housing Upper Weld.t Location #63 l
j 02-X-64 CEDM Motor Housing Upper Weld at Location #64 l
1 t
02-X-65 CEDM Motor Housing Upper Weld at Location #65 j
i l
02-X-66 CEDM Motor Housing Upper Weld at Location #66
[
02-X-67 CEDM Motor Housing Upper Weld at Location #67 U
V V
U i
l Date:
7/28/75 i
j V-2.12 Revision:
0 i
O
-Q o
t PROGRAM PLAN AND SCHEDULE 20ME 2 REACTM VESSEL CLME HEM Reference Drawing No.:
E-LOU-112-002 t
t Weld Examination Examination Procedure Calibration Extent of 3'
Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IW8e2600 02-if68-CEDM Motor Housing Upper Weld at Location #68 Be0 Vol.
NIPe239 UT-1/2Tbeyond i
edge of weld t
02-X-69 CEDM Motor Housing Upper Weld at Location #69 02-X-70 CEDM Motor Housing Upper Weld at Location #70 l
l 02-X-71 CEDM Motor Housing Upper Weld at Location- #71 02-X-72 CEDM Motor Housing Upper Weld at Location #72 02-X-73 CEDM Motor Housing Upper Weld at Location #73 1
l 02-X-74 CEDM Motor Housing upper Weld at Location #74 1
l 02-1275 CEDM Motor Housing Upper Weld at Location ~f75 1
j 02-X.-76 CEDM Motor Housing Upper Weld at Loca' tion #76 02-X-77 CEDM Motor Housing Upper Weld at Location #77
~
I 02-X-78 CEDM Motor Housing Upper Weld at Location #78 l
02-X-79 CEDM Motor Housing' Upper Weld at Location #79 l
02-X-80 CEDM Motor Housing Upper Weld at Location #80 i
02-X-81 CEDM Motor Housing Upper Weld at Location #81 l
02-X-82 CEDM Motor Housing Upper Weld at Location #82
,V if if if if Date:
7/28/75 I
y-2.13 Revisicn:
0 1
a m
O O
Q PROGRAM PLAN AND SCHEDULE ZONE 2 REACTOR VESSEL CLOSURE HEAD Reference Drawing No.: E-LOU-112-002 Designation Weld Description Category Method '
Procedure Calibration Extent of Weld Examination Examination Number Block No.
Examination IW8-2500 IW8-2600 02-X CEDM Motor Housing Upper Weld at Location #83 8-0 Vol.
N!P-239 UT-1/2T beyond Wge of weld 02-X-84 CEDM Motor Housing Upper Weld at Location #84 02 X-85 CEDM Motor Housing Upper Weld at Location #85 7
02-X-86 CEDM Motor Housing Upper Weld at Location #86 02-X'-87 CEDM Motor Housing Upper Weld at Location #87 02-X-88 CEDM Motor Housing Upper Weld at Location #88 02-X-89 CEDM Motor Housing Upper Weld at Location #89 02-X_-90 CEDM Motor. Houiing Upper Weld at Location #90 02-X-91 CEDM Motor Housing Upper Weld at Location #91 if 1f 02-Y-60 CEDM Upper Housing Lower Weld at Location #60 MIP-240 UT-02-Y-61 CEDM Upper Housing Lower Weld at Location #61 02-Y-62 CEDM Upper Housing Lower Weld at Location #62 02-Y-63 CEDM Upper Housing Lower Weld at Location #63 02-Y-64 CEDM Upper Housing Lower Weld at Location #64 02-Y-65 CEDM Upper Housing Lower Weld at Location #65 if if if if If Date:
7/28/75 V-2.14 Revision:
0
O O
o PROGRAM PLAN AND SCHEDULE ZONE 2 REACTOR VESSEL CLOSURE HEAD Reference Drawing No.: E-LOU-ll2-002 t.
~
Examination Examination Procedure Calibration Extent of Designation Weld Description Gategory Method Number Block No~
Exainination 1 6 2500 I h 2600 4 -
i 02-146 CEDM Upper Housing Lower Weld at Location #66 84 Vol.
NIre240 UTe 1/2Tbeyond Wge of weld 02-Y-67 CEDM Upper Housing Lower Weld at Location #67 4
i 02-Y-68 CEDM Upper Housing Lower Weld at Location #68 l
)
02-Y-69 CEDM Upper Housing Later Weld at Location #69
{
02-Y-70 CEDM Upper Housing Lower Weld at Location #70 1
l 02-Y-71 CEDM Upper Housing Lower Weld at Location #71
~
02-Y-72 CEDM Upper Housing Lower Weld at Location #72 l
02-1 73 CEDM Uppec Housiing Lower. Weld at Location #73' 02-Y-74 CEDM Upper Housing Lower Weld at Location #74 l
02-Y-75 CEDM Upper Housing Lower Weld at Location #75 i
02-Y-76 CEDM Upper Housing Lower Weld at Location #76 j
02-Y-77 CEDM Upper Housing Lower Weld at Location #77 1 '
)
02-Y-78 CEDM Upper Housing Lower Weld at Location #78' i
l 02-Y-79 CEDM Upper Housing Lower Weld at Location #79 02-Y-80 CEDM Upper Housing Lower Weld at Location #80 V
V il
'l V
,I l
~
Date:
7/28/75 V-2.15 Revision:
0
O O
a PROGRAM PLAN AND SCHEDULE ZONE 2 REACTOR VESSEL CLOSURE HEAD Reference Drawing No.:
E-LOU-ll2-002 l
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number 81ock No.
Examination
-2500 IW8-2600 IW8 02h-81 CEDM Upper. Housing Lower Weld at Location #81 Be0 Vol.
NTPe240.
UTe 1/2Tbeyond 02-Y-82 CEDM Upper Housing Lower Weld at Location #82 02-Y-83 CEDM Upper Housing Lower Weld at Location #83 02-Y-84 CEDM Upper Housing Lower Weld at Location #84 02-Y-85 CEDM Upper Housing Lower Weld at Location #85 02-Y-86 CEDM Upper Housing Lower Weld at Location #86 02-Y-87 CEDM Upper Housing Lower Weld at Location #87
~
02-Y-88 CEDM Upper Housing Lower Weld at Location #88 02-Y-89 CEDM Upper Housing Lower Weld at Location #89 02-Y-90 CEDM Upper Housing Lower Weld at Location #90 02-Y-91 CEDM Upper Housing Lower Weld at Location #91
+A 02-Z-60 CE0M ' Upper Housing Upper Weld at Location #60 02-Z-61 CEDM Upper Housing Upper Weld at Location #61 02-Z-62 CEDM Upper Housing Upper Weld at Location #62
/
V if if V
02-Z-63 CEDM Upper Housing Upper Weld at Location #63 yn u-z-40 gen 91 - raese wzas ac nor cakt uMLcss A LEnx 'neJcLets 7)' ' 5 Date-7/28/75 MRMO N
B asezs M y ]f '3a R e s& so d is a swes s.
fs 7-su Nu PS2 y
Revision:
0 n,s-u
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. PROGRAM PLAN AND SCHEDULE ZONE 2 Reference Drawing No.: E-LOU-112-002
~ REACTOR VES$EL CLOSURE HEAD 4
i Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IWB-2600
NIP 240 UT-1/2T beyond edge of weld 02-Z-65 CEM Upper Housing Upper Weld at Location #65 02,-Z-66 CEDM Upper Housing Upper Weld at Location #66 1
02-2-67 CEDM Upper Housing Opper Wald at Location #67 02-Z-68 CEDM Upper Housing Upper Weld at Location #68 02-Z-69 CEDM Upper Housing Upper Weld at Lt. cation'#69 l
02-Z-70 CEDM Upper Housing Upper Weld at Location #70
~
02-2-71 CEDM Upper Housing Upper Weld at Location #71 02-Z-72 CEDM Upper Housing Upper Weld at Location #72 i
02-Z-73 CEDM Upper Housing upper Weld at Location #73 02-Z-74 CEDM Upper Housing Upper Weld at Location #74
'02-Z-75 CEDM Upper Housing Upper Weld at Location #75
}-
02-Z-76 CEDM Upper Housing Upper Weld at Location #76 4
l 02-Z-77 CEDM Upper Housing Upper Weld at Location #77' 1
l 02-Z-78 CEDM Upper Housing Upper Weld at Location #78 if i f I I I I II
~
Date:
7/28/75 V-237 Revision:
0 7
1
O O
O PROGRAM PLAN AND SCHEDULE ZONE 2 REACTOR VESSEL CLOSURE HEAD Reference Drawing No.:
E-LOU-ll 2-002-Designation Weld Description Category Method
~
Procedure Calibration Extent of Weld Examination Examination Number Block No.
Examination IWB 2500 IWB-2600 02-if '
CEDM Upper Housing Upper Weld at Location #79 8-0 Vol.
NIP-240 UT-1/2T beyond 79 edge of weld 02-Z-80 CEDM Upper Housing Upper Weld at Location #80 02-Z-81 CEDM Upper Housing Upper Weld at Location #81 02-Z-82 CEDM Upper Housing U'pper Weld at Location #82 02-Z-85 CEDM Upper Housing Upper Weld at Location #83 02-Z-84 CEDM Upper Housing Upper Weld at Location 184 02-Z-85 CEDM Upper Housing Upper Weld at Location #85 02-Z-86 CEDM Upper Housing Upper Weld at Location #86 02-Z-87 CEDM Upper Housing Upper Weld at Location #87 02-2-88 CEDM Upper Housing Upper Weld at Location #88 02-Z-89 CEDM Upper Housing Upper Weld at Location #89 02-Z-90 CEDM Upper Housing ' Upper Weld at Location #90 02-Z-91 CEDM Upper Housing Upper Weld at Location #91 V
V V
V V
Date:
7/28/75 V-2.18 Revision:
0
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O PROGRAM PLAN. AND SCHEDULE ZONE 3 STEAM GENERATOR UNIT #1 Reference Drawing No.:
E-LOU-ll2-003 1
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description
' Category Method Number Block No.
Examination IWB-2500 IWB-2600 03-001 Support Skirt to Steam Generator B-H Vol.
NIPr248 UT-7 2T along support 03-002 Stay Cylinder Base to Hemisphere B-B NIP-248 UT-2 1/2T beyond
]
edge of weld 03-003 Peel Segment to Peel Sepent at 56' 15' Axis03-004 Peel Segment to Peel Segment at 128* 15 Axis 4
1 03-005 Peel Segment to Peel Segment at 200* 15' Axis l
l 03-006 Peel Segment to Peel Sepent at 272* 15' Axis03-007 Peel Segment to Peel Segment at 344' 15' Axis l
if 03-008 Hemisphere to. Tube Sheet Extension NIP-247 03-009 Tube Sheet Extension to Tube Sheet y
03-010 42" Hot Leg Nozzle to Hemisphere
~
B-E NIP-248 1/2T beyond shell side 03-011 30" Cold Leg Nozzle to Hemisphere at 45' Axis of weld l
03-012 30" Cold Leg Nozzle to Hemisphere at 315*
I AKIS if if if.03-013 Extension Ring Segment to Segment at O' Axis B-B
)/
NIP-247 3r M2e gpgeqd V-3.1 Date:
2-01-77 j
Revision:
1 1
3 n
0 0'
- Q e
PROGRAM PLAN AND SCHEDULE ZONE.3 STEAM GENERATOR UNIT #1 Reference Drawing No.: E-LOU-112-003 i
Weld Examination Examination Procedure Calibration Extent of Designation Wald Description Category Method Number Block No.
Examination IWB-2500 IWB-2500 03-014 Extension Ring Segment to Segment at 90*
B-B Vol.
NIP-247 UT-2 1/2 T beyond Axis edge of weld i
03-015 Extension Ring Segment to Segment at 180*
t Axis03-016 Extension Ring Segment to Segment at 270*
i f y
y if V
03-01T Hot Side Clad Patch B-I-2 Vis.
00000-36 sq. in.
l l
ESS-029 patch 03-018 Cold Side Clad Patch l
y y
l 03-019 42" Hot Leg Nozzle Inner Radius Section B-D Vol.
NIP-251 UT-ll 100%
t l
03-020 30" Cold Leg Nozzle Inner Radius Section at
- 45* Axis l
03-021 30" Cold Leg Nozzle Inner Radius Section at 315* Axis i f i r 1r V
y n
THE FOLLOWING TWO EXAMINATIONS TO BE PERFORMEl> In THE FIEL )03-022 Manway Bolting at 0* Orientation 3-G-2 Vis.
00000-Entire Area
~
ESS-029 03-023 Manway Bolting at 112* - 30' Orientation
'/
V if 1/
)sv ucencs due.no ess vssisot Mowi M -63 '
Date:
2-01-77 QM/3-U~-83 V-3.2 Revision:
i
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L)
PROGRAM PLAN AND SCHEDULE ZONE 3 Ref rence Drawing No.: E-LOU-ll2-003 Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination
[W(B,C)-2500 [W(B,C)-2600 03-024 Upper Extension Ring to Tube Sheet C-A Vol.
NIP-264 UT-38 1/2 T beyond edge of weld 03-025 Upper Extension Ring to Lower Shell y
03-026 Intermediate Shell to Conical Section UT-37, UT-38 1
03-027 Conical Section to Upper Shell y
03-028' Upper Shell to Top Head Torus UT-38 03-029 Top Head Torus to Top Head Dome V
V 03-030 Steam Nozzle to Top Head Dome C-B 1/2T beyond shell side 03-031 Feedwater Nozzle to Upper Shell y
y y
of weld y
FOUR EXAMINATIONS BELOW DONE IN FIELD
~
03-032 Stay Cylinder t'o Stay Cylinder Base B-B NIP-249 UT-3 1/2 T beyond edge of weld 03-033 Stay Cylinder to Stay Cylinder Extension 03-034 Stay Cylinder Extension to Tube Sheet V
V V
03-035 Tube Sheet to Stay Cylinder Cap C-A y
UT-7 y
(
sc c P1rsuhv Y r.v Tan s'sR Gid w coRPod a n o d W A' W A ]}i Q'n 83 gggg; yjggjy5 V-3.3 Revision:
0
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O-O i
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I PROGit4M PLM AND SCHEDULE ZONE 3
[
STEAM GENEMTOR tillk #1 c
4
.- f Reference Drawing No.:
'E-LOU-112-003
')
y 1
l i
e
-s!
/
Erimination Examination Procedure Calibration Extent of i
\\ i i
Weld Designation Weld Lascription Catagory Method Number Block No.
Examination IW(8,C)-2500 IW(8,C)-2600 l
g, i
03-036 Primary Head Instrument Nozzle at 21' B-P Vis.-H 00000-Surrodnding
'*'4 ESS-029 Area j.
J,.
Primary (Hed6' Instrument,Puzzleat33*
3 f
i;03-03T. 'f t
t s.
l.
'f 03-038,,
Rrimary Heq I'nstrament Nozz'.e,at 327*
b
-l
,03-03I Primary Hea'd !r.strament Noz'zle' at _239*.
I~
6
.\\j.
4 x
303-4 % '
Primar)dManway at c' s t
e 6 i.
y.-
,s a
p g
s03-041 Primar>,' MaMay at 112*30'-
1 3
.If i
03'-C42 -
Conical Shell Level Nozzle at 22*30' IWC-2510 l
~
03,043 '
Conical Shell L5 vel Nozzle at 45*
l
)'03-044 Conical Shell Level Nozzle at 315" t
03-045 Conical Shell Level Nozzle ~at 337*30' 5
03-046 Bottom Blowdown Nozzle 1
i 03-047-Upper Shell Level Nozzle at 22*30' i
i 03-048 Upper Shell Level Nozzle at 45*
03-049 Upper Shell Level Nozzle at 315*
l j
03-050 Upper Shell-Level Nozzle at 337*30' i f if If I I i
I Date:
7/28/75 V-3 4 Revision:
0
,n.
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O-O PROGRAM PLAN AND SCHEDULE ZONE 3
- I Reference Drawing No.:
E-LOU-112-003 l
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category ~
Method Number Block No.
Examination IWC-2500 IWC-2600 03-051 Secondary Manway at 90*
IWC-2510 Vis.-H 00000-Surrounding ESS-029 Area 03 052 Secondary Manway at 270*
03-053 Sampling Nozzle 03-M 4 Handhole at O'03-055 Handhole at 90*
03-056 Surface Blowdown Nozzle V
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3g THE FOLLOWING TWO EXAMINATIONS TO BE PERFORMED IN THE FIEL0 03-057 Secondary Manway Bolting at 90*'
C-D Vis., surf.
00000-Visual: all ESS-029 areas03-058 Secondary Manway Bolting at 270*
if if 00000 Surface:
~
ESS-028 bolts03-059 Key lug at 0* axis C-C Surf.
00000-Entire weld ESS-028 03-060 Key lug at 180* axis03-061 Snubber lug at 90* axis03-062 Snubber lug at 270* axis V
V
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2-01-77 V-3.5 Revision:
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. PROGRAM PLAN AND SCHEDULE ZONE 4 STEAM GENERATOR UNIT #2 i
Reference Drawing No.:
E-LOU-112-004 i
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IWB-2600 04-001 Support Skirt to Steam Generator B-H Vol.
NIP-248 UT-7 2T along support 04-002 Stay Cylinder Base to Hemisphere B-B NIP-248 UT-2 1/2T beyond edge of weld 04-003 Peel. Segment to Peel', Segment at 56* 15' Axis04-004 Peel Segment to Peel Segment at 128* 15' Axis04-005 Peel Segment to Peel Segment at 200* 15' Axis04-006 Peel Segment to Peel Segment at 272" 15' Axis j
,04-007 Peel Segment'to Peel Segment at 344* 15' Axis04-008 Hemisphere to Tube Sheet Extension
~
NIP-247 04.009 Tube Sheet Extension to Tube Sheet V
V V
04-010 42" Hot Leg Nozzle to Hemisphere B-E NIP-248 1/2T beyond shell side 04-011 30" Cold Leg Nozzle to Hemisphere at 45' Axis of weld 04-012 30" Cold Leg Nozzle to Hemisphere at 315*
Axis V
V V
04-013 Extension Ring Segment to Segment at,0* Axis B-B NIP-247 1/2T beyond
~
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edge of weld Date:
2-01-77 i
V-4*1 Revision:
1
{
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PROGRAM PLAN AND SCHEDULE ZONE 4 STEAM GENERATOR UNIT #2.
Reference Drawing No.:
E-LOU-ll2-004 l
l Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IWB-2500 04-014 Extension Ring Segment to Segment at 90*
B-B Vol.
NIP-247 UT 2 1/2T bey.ond Axis edge of weld 04-015 Extension Ring Segment to Segment at 180 Axis O.4-016 Extension Ring Segment to Segment at 270*
Axis N/
V V
V 04-017 Hot Side Clad Patch B-I-2 Vis.
00000-V 36 sq. in.
ESS-029 aatch 04-018 Cold Side Clad Patch sf V
N/
V 04-019 42" Hot Leg Nozzle Inner Radius Section B-D Vol.
NIP-251 UT-ll 100%
04-020 30" Cold Leg Nozzle Inner Radius Section at 45* Axis04-021 30" Cold Leg Nozzle Inner Radius Section at 315* Axis Y
y y
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THE FOLLOWING TWO EXAMINATIONS TO BE PERFORMED IN THE FIELD 04-022 Manway Bolting at 0* Orientation B-G-2 Vis.
00000-Entire Area ESS-029 04-023 Manway Bolting at 112 - 30' Orientation
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2-01-77 V-4.2 q Al 10 -15'-93 Revision:
1
O O
O PROGRAM PLAN AND SCHEDULE ZONE 4 STEAM GENERATOR UNIT #2 Reference Drawing No.:
E-LOU-112-004 I
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IW(B,Cs-2500 IW(B,C)-2600 04-024-Upper Extension Ring to Tube Sheet C-A Vol.
NIP-264 UT-38 1/2T beyond edge of weld 04-025
. Upper Extension Ring to Lower Shell q
04-026 Intermediate Shell to Conical Section UT-37, UT-38 i
04-027 Conical Section to Upl er Shell y
04:028.
Upper Shell to Top Head Torus UT-38 l
04-029 Top Head Torus to Top Head Dome y
y 04-030 Steam Nozzle t.o Top Head Dome
', C-B 1/2T beyond 04-031 Feedwater Nozzle.to Upper Shell gr shell side FOUR EXAMINATIONS BELOW DONE IN FIELD V
~
04-032 Stay Cylin. der to Stay Cylinder Base B-B NIP-249 UT-3 1/2T beyond edge of weld j
04-033 Stay Cylinder to Stay Cylinder Extension 04-034 Stay' Cylinder Extension to Tube Sheet y
y 1
04-035 Tube Sheet to Stay Cylinder Cap C-A UT-7 V
y
% sea ps.c secpa,w,1y mc voacuu'n carwnw r>sd or /veanodb y 92.,5.g3 Date:
7/28/75 V-4.3 Revision:
0
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PROGRAM PLAN AND SCHEDULE ZONE 4 STEAM GENERATOR UNIT #2 Reference Drawing No.:
E-L00-112-004 l
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Catep ry Method Number Block No.
Examination IW(B,C)-2500 IW(B,C)-2600 04'-036 Primary Head Instrument Nozzle at 21 B-P Vis.-H 00000-Surrounding ESS-029 Area 04-037 Primary Head Instrument Nozzle at 33*
0~4-038 Primary Head Instrument Nozzle at 327*
04-039 Primary' Head Instrument Nozzle at 339*
04-040 Primary Manway at 0*
04-041 Primary Manway at 112*30'
\\/
04-042 Conical Shell, Level Nozzle at 22*30' IWC-2510
'04'-043 Conical S' hell Level Nozzle at 45 04-044 Conical Shell Level Nozzle at 315*
04-045 Conical Shell Level Nozzle at 337*30'04-046 Bottom Blowdown Nozzle 04-047 Upper Shell Level Nozzle at 22 30'04-048 Upper Shell Level Nozzle at 45*
04-049 Upper Shell Level Nozzle at 315 yf p
f f
04-050 Upper Shell Level Nozzle at 337*30' Date:
7/28/75 V-4.4 Revision:
0
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. PROGRAM PLAN AND SCHEDUL ZONE 4 STEAM GENERATOR UNIT #2 Reference Drawing No.: _
E-LOU-112-004.
t Wald Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWC-2500 IWC-2600 0'4'-051.
Secondary Manway at 90*
IWC-2510 Vis.-H 00000-Surrounding ESS-029 Area
,04-052 Secondary Manway at 270*
'04-053 Sampling Nozzle 04-054 Handhole at 0*
04-055 Handhole at 90*
04-056 Surface Blowdown Nozzle
\\[
Y THE FOLLOWING TWO EXAMINATIONS TO BE PERFORME1 IN THE FIEL )
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C-D Vis., surf.
00000-Visuhl: all ESS-029 areas04-058 Secondary Manway Bolting at 270*
S/
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00000-Surface:
ESS-028 bolts04-059 Key lug at 0* axis C-C Surf.
00000-Entire weld ESS-028 04-060 Key lug at 180* axis04-061 Snubber lug at 90* axis04-062 Snubber lug at 270* axis V
V V
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2-01-77
/ 9 '// d snr secr. x < a a c q fa i.r-8 3 V-4.5
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D PROGRAM PLAN AND SCHEDULE ZONE 5-PRESSUR,IZER Reference Drawing.No.:
E-LOU-112-005 l
Wald Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IWB-2600 05-db1' Support Skirt to Vessel Weld B-H Vol.
NIP-243 UT-7 2T along support 05-002 Bottom Head to Shell Circumferential Weld B-B NIP-242 UT-4 1/2T beyond l
edge of weld 05-003 Lower,Shell Longitudinal Weld at 90*
l 05.004 Lower Shell-Longitudinal Weld at 270*
05-005 Lower Shell to Upper Shell Circumferential Weld i
l 05-006 Upper Shell Longitudinal Weld at 0
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i 05-bO8 Upper Shell to Top Head Circumferential Weld y
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05-009 Surge Nozzle to Bottom Head Weld B-D NIP-242 1/2T beyond
- shell side 05-010 Spray Nozzle to Top Head Weld of weld i
j 05-011' Safety Valve Nozzle to Top Head Weld at 45*
i 05-012 Safety Valve Nozzle to Top Head Weld at 135'05-013 Safety Valve Nozzle to Top Head Weld at 225*
y y
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'l V-5.1 Date: 2-01-77 1
l Revision:
1
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. PROGRAM PLAN AND SCHEDULE
~
ZONE 5 Reference Drawing No.:
E-LOU-112-005 l
Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination
~
IWD-2500 IWB-2600 05-0'i4~
Surge Nozzle Inner Radius B-D Vol.
NIP-245 UT-12 Radius Areas 05-015-Spray Nozzle Inner Radius UT-13 t
05.-016 Safety Nozzle Inner Radius at 45*
UT-14 05-017 Safety Nozzle Inner ~ Radius at 135*
05-018 Safety Nozzle Inner Radius at 225* -
V V
V V
V 05-019 Cladding Patch (36 sq. in.) Located 18" B-I-2 Vis.
00000-36 sq. in.
Above Top Head.to Shell Weld ESS-029 patch THE FOLLOWING EXAMINATION TO BE PERFORMED IN
'HE FIELD 4
05-020 Manway Bolting:. 20 1-1/2"~ studs and nuts B-G-2 Entire Area 05-021 Lower Level Nozzle on Bottom Head at 171*
B-P Vis.-H Surrounding
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Orientation Area 05-022 Lower Level Nozzle on Bottom Head at 189*
Orientation 05-023 Temperature Nozzle on 0* Centerline 34-13/16" Above Bottom Head Weld V
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Date:
2-01-77
% fo-/&s3 V-5.2 Revision:
1
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O PROGRAM PLAN AHD SCHEDULE ZONE 5 PRESSURIZER Reference Drawing No.:
E-LOU-ll2-005 Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination IWB-2500 IWB-2600 05-0I54*
Instrument Nozzle at 165 Orientation on Top B-P Vis.-H 00000-Surrounding Head ESS-029 Area 05-025 Instrumer.t Nozzle at 195 Orient.ation on Top Head 05-026 Instrument Nozzle at 270 Orientation on Top Head '
1 05-027 Instrument Nozzle at 315* Orientation on Top Head i
05-028 Manway 37 B-E 05-H-1 Heater Penetration A-1 05-H-2 Heater Penetration A-2 05-H~3 lleater. Penetration B-1 05-H-4 Heater Penetration B-2 Heater Penetration'B-3
]
05-H-5 05-H-6 Heater Penetration B-4 05-H-7 Heater Penetration C-1 Il il I
05-H-8 Heater Penetration C-2 Date:
7/28/75 V-5*3 Revision:
0 1
O O
O PROGRAM PLAN AND SCllEDULE ZONE 5 Rsference. Drawing No.:
E-L00-ll2-005 Weld Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method-Number Block No.
Examination IWB-?S00 IWR-2600 05-H'-9' Heater Penetration C-3 B-E Vis.-H 00000-Surrounding ESS-029 Area 05-H-10 Heater Penetration C-4
'05.-H-l l Heater Penetration D-1 05-H-12 Heater Penetration D-2 05-H-13 Heater Penetration D-3 05-H-14 Heater Penetration D-4 05-H-15 Heater Penetration E-1 05-H-16 Heater Penetration E-2 05-H-17 Heater Penetration F-1 l
05-HJ18 Heater Penetration F-2 05-H-19 Heater Penetration F-3 05-H-20 Heater Penetration F-4 05-H-21 Heater Penetration G-1 05-11-2 2 Heater Penetration G-2 05-H-2 3 Heater Penetration G-3 if if il-II Date:
7/28/75 V-5.4 Revision:
0
O.
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I PROGRAM PLAN AND SCllEDULE ZONE 5 PRESSURIZER R2ference Drawing No.:
E-LOU-ll2-005 i
Wald Examination Examination Procedure Calibration Extent of Designation Weld Description Category Method Number Block No.
Examination 05-H-24 Heater Penetration G-4 B-E Vis.-H 00000-Surrounding ESS-029 Area t
05-H-25 Heater Penetration H-1 05-H-26 Heater Penetration H-2 05-H-27 Heater Penetration H-3 05-H-28 Heater Penetration H-4 05-H-29 Heater Penetration I-l 05-H-30 Heater Penetration I-2 y
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f Date:
7/28/75 V-5.5 Revision:
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x Date: 2-01-77 Revision: 1 By:IIG i
<D EXCLUSIONS AND EXCEPTIONS I
I The following items identify those areas where strict compliance with the preservice examination reouirements of the 1974 Edition of Section XI of the l
ASME Boiler and Pressure Vessel Code and Summer 1974 Addenda is limited.
All areas are delineated below. The general reasons for limited compliance are lack of access, availability of material for calibration standards i
and lack of code requirements.
Technically sound, reasonable alternatives have been imposed in these areas.
Application of the rules of the 1974 Edition of Section XI of the ASME Code and Sumer 1974 Addenda was selected with the intent of meeting these. requirements to the maximum extent practi-cal.
1 1.
Paragraph I-3121 requires calibration standard material to be from the j
- component to be examined. Nozzle dropouts and/or prolongations from all components were not available; consequently, carbon steel calibration standards numbered UT-1 through UT-5 and UT-7 through UT-14, which were utilized for examinations on the reactor pressure vessel and closure head, the steam generators and the pressurizer, were manufactured from reactor vessel nozzle cutouts.
Steam generators and the pressurizer are made i
from materials-'of the same specifications.
The calibration standards are
. O the property of the utility and will be retained on site for use in all future inservice examinations.
2.
Portions of the 270 longitudinal weld in the middle shell, the 270 longitudinal weld in the lower shell, and the: middle to lower shell girth weldareadjacenttothematerialsurveillancebrackegs. fheegamination techniques used on other shell welds of the vessel (0, 45, 60 half-vee) cannot be used fully in these areas during inservice examinations.
ine preservice (baseline) examinations were performed prior to installation of these brackets; consequently, the preservice examinations consisted of.
l~
examinations using the required Section XI half-vee techniques supplemented i
by other angles and full-vee techniques to establish a fingerprint for subsequent inservice examinations.
In addition, the perpendicular scan of short portions of the girth weld was performed from an angle slightly off the perpendicular.
3.
Paragraph I-5220 of Section XI requires verification of penetration by obtaining an observable back reflection. The geometry of component areas with non-parallel back surfaces prevents total compliance with this requirement.of Section XI.
4.
Paragraph I-6230 of Section XI requires a permanent weld marking scheme to be implemented. The Waterford III S.E.S.. component welds have been marked with low stress steel stamping in accordance with Section XI requirements; i
however -the locational aspects.of the marking scheme actually used are
~
l Q-
- an effective marking system.
The details of the marking system are as not in strict compliance with Section XI, but meet the Code's intent for follows:
S
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Revision:
1 By: IIG EXCLUSIONS AND EXCEPTIONS (continued) 1 t
A.
Circumferential and Longitudinal Welds-1 i
The weld centerlines are marked as the Code states, with twelve (12) inch spacing on the reference points.
In addition, two reference lines, located 2-1/2 T (T= wall thickness) from weld centerline on each side of the weld are marked using a twelve (12) inch spacing. The reactor vessel is marked on the ID as well as the OD surface.
B.
Nozzle-to-Component Welds-The weld centerlines are marked as the Code states, with twelve (12) inch spacing on the reference points.
In addition, a circular reference line is marked on the component using a six (6) inch spacing for noz-z1es greater than twelve (12) inches in diameter.
For smaller nozzles which are greater than one (1) inch nominal size, spacing less than six (6) inches, suitable to define the weld centerline, shall be used.
This circle shall be marked on nozzles greater than one (1) inch nomi-nal size with diameter equal to the weld centerline diameter plus five (5) times the shell thickness.
Azimuthal markings are as the Code i
states, except that five (5) degree increments are marked on nozzle welds greater than twenty (20) inches diameter, rather than the twenty-four (24) inches diameter of the Code.
(
C.
Safe-End and Transition Piece Welds-l' Two (2) reference lines are provided. One parallel lind is marked on each side of the weld centerline, one inch from the weld centerline.
No scribe line is directly on the weld, as the weld receives a penetrant examination and a scribe line could give a non-relevant indication 1
which might mask a true indication.. Spacing and azimuth marking is as specified for nozzles of the same diameter.
f D.
Calibration Pads and Location Markers-Two sets of positional markers have been provided on the reactor vessel.
These markers are not required by the Code but have been provided to enhance the speed and accuracy with which the examinations are carried out.
1.
Calibration Pads 4
Calibration pads have been provided to locate reactor vessel weld seams accurately when performing ultrasonic examinations from the vessel interior using remote equipment. The increased metal path for ultrasonic beams was readily apparent on equipment readouts, and exa.nination datum points can be quickly established. These pads consist of nine. (9) weld build-ups on the-vessel 0.D.
These
.are three-inch square pads approximately one inch high. The pads have been machined such that the corners are essentially square, while the intersection with the shell is contoured to avoid stress risers.- -The pads are located near the intersection of each longi-
.tudinal and girth weld at a distance of 3T from each weld. Spect-r fically the edge of. the pad is 3T from the edge of the weld ~and is
Date: 2-01-77 j
Revision: 1 By: IIG EXCLUSIONS AND EXCEPTIONS (continued) 3
, (
located above and to the left of the intersection of the welds.
The exact location of all calibration pads is shown on a suitable drawing.
- 11. Location Markers Location markers consist of weld beads rpproximately one inch long located on the 00 surface of the bottom head adjacent to the meri-dional and dome welds.
These markers assist in the rapid location of the weld seams and will thereby minimize radiation exposure to examination personnel.
Each meridional weld is located by a single one-inch long bead running parallel and 3T to the side of the weld at the shell end and by two intersecting beads at the lower end, one parallel to the meridional weld and one parallel to the dome weld at a distance of 3T from each weld.
Location of the weld beads has been accurately recorded on a suitable drawing.
()
i l
I l
VI-3
Date:
2-01-77 Revision: 1 By:
IIG r0 QUALITY ASSURANCE All engineering services and examinations conducted on the Waterford III Steam Electric Station components meet the applicable quality assurance criteria of
Specifically, C-E Procedure 00000-NLE-056, Program Controls Procedure for Inservice Inspection, has been followed. A copy of 00000-NLE-056 is provided in this section of volume 1.
It should be noted that, because of a recent reorganization within Combustion Engineering regarding Quality Assurance functions, the following changes shall apply to this procedure:
1.
All references to " Development Depar'iment Quality Assurance Mahual" shall mean " Power Systems Group Nuclear Quality Assur-ance Manual, Revision 3, dated June 21, 1974."
2.
All references to " Development Department Quality Assurance Group" shall mean " Power Systems Group Quality Assurance."
3.
All references to " Development Department Quality Assurance Engineer" shall mean " Group Quality Assurance QA Engineer."
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i 7 0 PROGRAM CONTROLS PROCEDURE l
FOR INSERVICE INSPECTION
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00000-NLE-056
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SYSTEMS INTEGRITY SERVICES NUCLEAR POWER SYSTEMS DIVISION COMBUSTIO!! ENGIllEERING, INC.
-V WINDSOR, CONNECTICUT o
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Date:
l
' Approved by:
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/
Manager, Systems Integrity Services l
f!/4/7.$
[:
u.l Date:
Approved by:
,e Manager Inservip Inspection Revision Number:
1 Original Issue Date:
Acril 9. 1975 Date:
April 10,1974
-g Page 1 of 23 s. %
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INDEX Section Title Pace C,. Q t
4 1.0 Purpose t
4 2.0 Scope 3.0 References 4
4.0 Definitions 4
t 6
5.0 Applicability 6.0 Administrative Requirements 7
7.0 Contractual Requirements 8
8.0 Quality Assurance Program 9
' 9.0 Quality Assurance Audits 9
10 10.0 Organization 11.0 Design Control 11 12.0 Procurement Document Control 11 4
,(
13.0 Procedures and Drawings 12 14.0 Document Control 12
~15.0 Control of Purchased Material, Equipment and Services 15 16.0 Identification and Control of Materials, Parts and Components 16 2
I 17.0 Control of Nondestructive Examinations 17 18.0 Control of Inservice Inspection Examinations 18 19.0.
Control of Examination Equipment 19 l
20.0 Examination Material 19 21.0 Vendor Qualification 20
[
l 22.0 Qualification of Personnel 20 i
21 23.0 Control of Records 22 APPENDIX I -- Organization Chart 23 l
l APPENDIX II - Engineering Notice Procedure No. 00000-;tLE-056 Revision io.
i l
Date f,prii v.
..e_q Page 2_of S j-
Procedure flo. 00000-NLE-056 Revision f*o.
1 O
oate A r41 9. 1975 f
3 of_23 Page RECORD OF REVISIONS Acorovals Rav.
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Date
. Description
, Reason Originator C-E-l[il 1
4/9/75
- a. Changed Title on Editorial cover sheet and made editorial f-to-7f 4/^/7f
/3)]/ f changes on Pages 4, 5, 6, 7, 9, 15, 7
18, 19, 20 & 21 q[/6/
- b. Reflected organiza-Department re-tion changes on organization Pages 1, 5, 6, 7, 8, 9, 10, 11, 12, 18, 19, 20, 21 &
22
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- c. Section 9 - ex-To add. clarity panded scope and 1%)
added definition
- d. Section 12 - added To add clarity definition
- e. Section 14 - ex-To add clarity panded scope and added definition f Section 16 - ex-To add clarity 1
panded scope and added definition
- g. Added Appendix II To provide form l.
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PROGRAM CON' plS PROCEDURE FOR INSERVICE INSPECTION l
{b 1.0 PURPOSE This document defines the manner in which work will be performed on i
Inservice Inspection contracts which must meet the intent of 10CFR50, Appendix B.
Where a conflict exists between this document and the con-tract, the contract shall take precedence.
2.0 SCOPE 2.1 This document pertains to all aspects of an Inservice Inspection Program, as required by contract and may include any or all of the 4
following:
2.1.1 Engineering Services
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2.1.2 Component Preparation 2.1.3 Preservice Examinations 2.1.4 Inservice Examinations 2.2 Applicable sections of this document shall apply as required by con-(0 tract.
3.0 REFERENCES
3.1 ASME Boiler and Pressure Vessel Code,Section XI, " Rules for Inser-vice Inspection of Nuclear Reactor Coolant Systems," and Addenda as referenced in the contract.
i 3.2 NRC,10CFP.50, Appendix B, " Quality Assurance Requirements for Nuclear Power Plants" 3.3 ANSI N45.2 - 1971, " Quality Assurance Program Requirements for Nuclear f
Power P1 ants" 3.4 SNT-TC-1A, " Recommended Practice for Nondestructive Testing Personnel Qualification and Certification," published by the American Society for Nondestructive Testing 3.5 Development Department " Quality Assurance Manual"
^4.0 DEFINITIONS-4.1 Baseline Examination -- A term comonly used interchangeably with Preservice Examination.
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-Q 4.2 Certification _ -- A formal statement executed by a responsible employee
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of a supplier or an approved technical outside source which certifies that supplies or services, represented on an invoice or delivery document, are in all respects in accordance with contract agreements i
and/or technical requirements.
4.3 Cognizan't Enoineer -- That individual appointed by the Manager, Inservice Inspection, who is responsible for implementation and per-formance of the scope of work of an Inservice Inspection contract.
4.4 Component preoaration -- That scope of work performed on individual
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. components to ennance preservice and/or inservice examinations. The work may be in addition to that supplied under the terms of the ftSSS contract.
Component preparation may include but not be limited to:
- 4. 5.1 Procurement of ultrasonic calibration standards 4.5.2 Preparation of examination surfaces 4.5.3 Drawings, locating examination areas 4.5.4 Permanent identification of examination areas, by methods such as vibra' tooling or stamping
- 4. 5 Engineerina Services -- Engineering Services pertain to any of a number n
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, of activities related to an Inservice Inspection program that are per-
. !. s, formed prior to actual conduct of the required examinations.
Engi-V neering Services may include but not be limited to:
4.6.1 Review of component, piping and construction drawings to deter-mine if sufficient access is availabic for the performance of the examinations.
4.6.2 Preparatiori of examination boundary drawings i
4.6.3 Examination area identification and preparation of suitable drawings 4.6.4 Preparation of nondestructive examination procedures 4.6.5 Preparation of preservice and/or inservice examination program plans 4.6.6 ' Consultation services in all matters pertaining to Inservice Inspection 4.6 Examination -- The nondestructive examinations (fl0E) such as visual, radiograpny, ultrasonic, liquid penetrant and magnetic particle methods performed on component parts of the (155S.
Procedure flo. 00000-t:LE'-056 m
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4.7 Inservice Examinations -- Those examinations performed on a periodic
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basis for tne life of the plant commencing after the plant has become operational.
4.8 Inservice Inscection -- A general term used to describe any or all reuqirements of Section XI of the ASME Eoiler and Pressure Vessel
.i Code.
4.9 Inspection -- The witnessing of performance of examinations by an Inspector representing a State or Municipality of the United States, or other enforcement authorities having jurisdiction over the nuclear
, power components at the plant site.
4.10 Inspector -- All references to " Inspector" shall mean an " Authorized Inspector" having been first qualified by written examination pursuant to the legislation or rules of a State or Municipality of the United States or the rules of another authority having jurisdiction over a nuclear power plant at the installation location and which has adopted i
Section XI of the Code.
The Inspector shall not be an employee of the Owner or the Manufacturer.
4.11 Preservice Examinations -- Those examinations performed prior to I-the initial operation of the facility and in compliance with the requirements of Section XI of the Code.
The results of subsequent examinations can then be compared to the original condition to deter-mine if changes have occurred.
The intent is that the preservice examinations be as closely representative of *the exaninations to be l <ig )
perforned later as is practicable.
4.12 Qualification. Personal / Process -- Documented verification that person-p nel or processes are capaole of performing to requirements.
4.13 The Code -- Refers to the ASME Boiler and Pressure Vessel Code.
5.0 APPLICABILITY 5.1 This document applies to all' contractual Inservice Inspection acti-vities conducted by the Engineering Development and Services Depart-ment of the Nuclear Power Systems Division of Combustion Engineering, Inc.
5.2 The Inservice Inspection Group is responsible specifically for, but
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not limited to:.
'5.2.1 Administering all Inservice Inspection contracts whether directly with the Inservice Inspection Group or as a part of an existing NSSS contract.
Procedure No. 00000-NLE-056
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5.2.2 Review of.de specifications and regulations in areas of Inservice inspection.
Review of components and piping supplied by C-E and/or others 5.2.3 for accessibility and suitability of design to perform Code required examinations.
5.2.4 Selection of subcontractors to support activities related to Inservice Inspection when required.
5.2.5 Participate in the auditing and approval of subcontractors.
5.2.6 Performance of Engineering Services and/or studies for utility customers.
l 5.2.7 Preparation of Preservice and/or Inservice Examination Plans.
Conduct of Preservice and/or Inservice examinations and all l
5.2.8 associated functions.
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5.2.9 Preparation of Final Reports resulting from the conduct of actual examinations.
6.0 ADMINISTRATIVE REQUIREMENTS The Manager, Insenvice Inspection or the Manager. Syste,ms Integrity,
O 6.1 Services, is responsible for determining and assigning qualified engineers (Cognizant Engineer) or technicians to specific tasks, studies
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.Q He shall consider the individuals' education, and/or programs.
experience and job classification in making the determinations.
I The Manager, Inservice Inspection, shall determine that the terms 6.2 of the contract or request are in accordance with Section XI of the Code prior to assigning the task. Where conflicts exist, he shall be responsible for resolving these conflicts.
The Cognizant Engineer shall be responsible for performing or having 6.3 When a task performed all requirements of the contract or request.
is performed by an individual other than the Cognizant Engineer, the Cognizant Engineer shall be responsible for determining that the assigned individual is qualified to perform the task.
The Cognizant Engineer shall be responsible for reviewing and determining the i
completeness and accuracy.of work performed by others under his direction.
L The Manager, Inservice Inspection, shall be responsible for the 6.4 review and approval of all assignments completed by the Cognizant Engineer.
Procedure No. 00000-NLE-055 Revision No.
1 Date April 9. 1975
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_s 6.4.1 Apprv'ai f internal mem randa, letters r interim rep rts shall
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. be acknowledged by initialing.
6.4.2 Approval of final reports, procedures, program plans or certi-fication shall be approved by full signature and date on the s
3 Title Page.
,s 6.5 The Manager, Inservice Inspection, or his designated alternate shall I
participate with a Quality Control Engineer in the qualification and
. periodic audit of vendors and subcontractors.
I 6,6,The Dire?. tor, Engineering Development and Services, shall be responsible for certification of individuals to Level III qualification in accor-dance with the requirements of ASftT-TC-1 A.
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I 6.7 The Manager, Inservice Inspection, shall be responsible for the selection, training and ' approval of technicians to operate remote handling equipment required for the conduct of non-destructive t
examinations.
6.7.1 When technicians are provided by. vendors or subcontractors, the selection and training may be performed by the vendor orsubcontractor with the approval of the Manager, Inservice Inspection.
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6.8 The sanager, Inservice Inspection, shaii be responsib e for estab-lishing, maintaining and retaining records as requirad by Section XI i %,.)
of the Code and the contract.
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6.9 The Manager, Inservice Inspection, and/or the Crgnizant Engineer shall be responsible for verifying that the u signed tDE examiners are qualified to the appropriate level of SitT-TC-1A and that certi-
- l' fying documents are available prior to the start of any examination.
7.0 CONTRACTUAL REQUIREMEilTS 7.1 Inservice Inspection programs with utility customers will be performed l
on a contractual basis. The contract will define the scope of work by referencing the appropriate specification and/or proposal.
7.2 Combustion Engineering'shall be responsible for all planning, examina-tion, reporting' and all other F.atters pertaining to the execution of the contract.
At the discretion of the Manager, Inservice Inspection, i
or Manager, Systems Integrity Services,- a portion of the work may be
' delegated tosother-departments-and/or divisions of C-E or subcontracted to a qualified vendor.' 'In:a11' cases,' reports and all other correspon-k dence with the customer shall be prepared and/or approved by Combustion e
1 Engineering.
w Procedure t!o. 00000-ftLE-056 Revision tio.
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7.2.1 When a cc: ract is part of the NSSS contract, correspondence
. b O-shall be i adled through the C-E project Manager's office or directly am the Inservice Inspection Group at the discretion i
of the Prc.ect Manager.
The Manager, Inservice Inspection, or I
his designated alternate, shall be responsible for reviewing all correspondence between C-E and the customer as it pertains to Inservice Inspection.
7.2.2 After the award of a contract the Manager, Inservice Inspec-l, tion, C-E Project Manager and a responsible customer represen-tative shall mutually agree upon a distribution list for all correspondence between C-E and the customer.
8.0 QUALITY ASSURANCE PROGRAM 8.1 The requirements of this document are in accordance with the Develop-ment Department Quality Assurance Manual and 10CFR50, Appendix B, 4
where applicable.
9.0 QUALITY ASSURANCE AUDITS 9.1 Quality assurance audits of the Inservice Inspection Group activities shall be performed by the Development Department Quality Assurance Group in accordance with the following procedure:
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9.1.1. Audit Preparation Eg,)'
9'. l.1.1 The Manager, Inservice Inspection, or the Cogni-zant Engineer shall notify.the Quality Assurance Engineer when shop or field examinations are scheduled for a particular Inservice Inspection contract.
9.1.1.2 The Quality Assurance Engineer shall prepare a general format or series of checklists to serve as a guide for conducting the audit and for per-forming future audits in the same category.
9.1.2 Conducting the Audit 9.1.2.1 The Manager, Inservice Inspection, shall be notified of the audit time and purpose at least two work days prior to the audit.
9.1.2.2 The general format or checklists shall be used as a guide.
The. Quality Assurance Engineer may deviate from the format depending on the progress of the audit provided the scope of the audit is not changed.
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Procedure No. 00000-MLE-C55 4
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9.1.2.3 A preliminary audit report shall be prepared by the Quality Assurance Engineer, listing the per-sonnel contacted, a brief description of the purpose of the audit and the preliminary findings.
9.1. 3 Audit Review and Corrective Action 9.1.3.1 After the preparation of a preliminary report, the Quality Assurance Engineer shall debrief the Manager, Inservice Inspection, or the Cognizant Engineer, as applicable, and thoroughly discuss the findings and agree on necessary corrective action.
9.1.3.2 The final audit report shall include names of personnel contacted, purpose, findings, reconnenda-tions and corrective action required with suspense dates.
Copies of the report shall be transmitted to the Manager, Systems Integrity Services, and the Manager, Inservice Inspection.
The Quality Assurance Engineer shall review the report, set up a suspense file for corrective action and schedule a follow-up audit, if required.
9.2 The Quality Assurance Engineer shall maintain audit records for a O
and for determining progre.s will provide meterial for future audits minimum of two years.
Thi ss of the total quality program.
.d 9.3 Audits shall be performed at.least once during each phase of an Inservice Inspection contract, e.g., once during the Shop Preservice Examinations, once during the Field Preservice Examinations and once during the Inservice Examinations.
10.0 ORGANIZATION-10.1 The Manager, Inservice Inspection, shall report to the Manager, Systems Integrity Services.
I 10.2 The Manager, Inservice Inspection, is responsible for the overall inservice inspection program.
The program includes the development and preparation of all procedures, instructions, drawings and other documents necessary to treet tne requirements of the contract -
. including the conduct of examinations and final report preparation.
10.3 Cognizant Engineers shall be assigned to specific tasks or contract responsibility by the Manager, Inservice Inspection, and shall report directly to the ' Manager, Inservice Inspection.
O Procedure No. 00000-NLE-056 V
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10.4 The Quality Assurance Engineer shall report to the Quality Assurance
{O Manager.
He shall be responsible for conducting the quality func-tions related to Inservice Inspection.
10.5 The Organization Charts in the Development Department Quality Assurance l
Manual show the internal structure of the Development Department and its relationship to the Nuclear Power Systems Division, Combustion Engineering, Inc.
10.6 The Organization Chart of Appendix I shows the relationship of the Inservice Inspection Group within the Development Department.
l 11.0 DESIGN CONTROL 11.1 The Inservice Inspection Group does not participate in direct design activities of safety related equipment.
In those cases where examina-tion and/or remote handling equipment is procured.from others either by purchase or lease, the Cognizant Engineer snall review the equip-ment for adequacy in meeting Code requirements and material comoati-bility with the NSSS.
Control of this nature is exercised through purchase documents and by conducting periodic and final reviews of the equipment prior to manufacture and/or receipt of the equipment.
12.0 PROCUREMENT DOCUMENT CONTROL O
,2.1 The Cognizant Engineer shall prepare purchase order requisitions in accordance'with the specifications required by the contract.
Special
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requirements, such as materiaT or examination personnel qualifications, quality control requirements, etc., shall be noted en the purchase order.
12.2 The vendor shall be instructed to submit reports, deviations and contract changes on contracts. involving fabrication or engineering design to the originator of the purchase order.
12.3 Changes to contracts shall be controlled through formal agreements between the vendor and purchaser.
The Manager, Inservice Inspection, shall be responsible for obtaining necessary approvals for purchase order and purchase order supplements that affect technical or quality' requirements imposed on vendors and sub-tier vendors.
'12.4 The Manager, Inservice Inspection; Manager, Systems Integrity Services; and Quality Assurance Engineer; as a minimum, shall review and approve all purchase requisitions.
12.5 The purchase requisition is sent to the Purchasing Department and a purchase order is transmitted to an approved vendor.
If the purchase order has not been properly approved or if there are discrepancies, the requisition is returned to the originator for correction, Procedure No. 00000-NLE-056 w
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7-\\3.0 PROCEDURES AND DRAWINGS D
13.1 Procedures pertaining to personnel qualification, operation of equip-ment, NDE examinations or other special processes required by con-tract or at the direction of the Manager, Inservice Inspection, shall be prepared in accordance with the Development Department Procedure 00000-NLO-001.
Procedures shall be approved by the Manager, Inservice Inspection.
13.2 Drawings shall be prepared and maintained in accordance with the practices established by Nuclear Power Systems Division of Combustion Engineering, Inc.
14.0 DOCUMENT CONTROL 14.1 The Cognizant Engineer shall control the procurement and disposition of documents such as specifications, instructions, drawings and procedures, incl.uding revisions, to ensure that they are reviewed and approved by authorized persons, distributed to prescribed parties and maintained current and complete.
The procedure for the preparation, release and revision of engi-14.2 neering drawings and distribution of prints is described in NPS-MPI-2, Control of Engineering Drawings.
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14.2.1 In instances when it becomes necessary to make changes to a vendor drawing, the Cognizant Engineer may have.a new C-E Windsor drawing prepared and issued.
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14.2.1.1 The new drawing shall be issued as Revision "0",
shall carry a new drawing number and. be con-trolled in accordance with the provisions of NPS-MPI-2.
14.2.1.2 The new drawing shall reference the drawing and revision from which it was prepared.
14.2.1.3 A copy of the new C-E Windsor drawing, or an l
" Engineering Change or Drafting Request" (ECDR) may be transmitted to the vendor for informa-tion.
14.3. Procedures for nondestructive examinations, personnel qualification, operating instructions, etc., are prepared, maintained and revised in accordance with the Development Department Procedure 00000-NiQ-001.
14.3.1 In instances when changes to inservice inspection procedures or drawings are needed to eliminate costly delays and/or expedite field operations, the Engineering Notice (E.N.),
l (reference Appendix II) shall be used to document and
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authorize these changes.
Procedure No. 00000-MLE-056
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14.3.2 One, or more, E.N.'s may be issued as outstanding against
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C-246-393-2 Pressurizer surge nozzle inner radius j
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l UT-13 11"x19" dia.,
C-246-395 3 Pressurizer spray nozzle inner radius 120' segment UT-14 7"x19" dia.,
C-246-443 Pressurizer safety nozzle inner radius 120 segment UT-20 7" dia. x 36" B-246-438-2 '
Reactor vessel closure stud UT-21 10-9/16" dia.
B-246-419-1 Reactor vessel closure nut x 7-1/2" long r
UT-22 5-9/16" OD x C-245-570-2.
Closure head instrument nozzle 15/32" thick x 12" long UT-37 7" thick C-246-528-2 Steam generator secondary side unclad O.UT-3..
t 5" thick C-246-529-1 Steam generator secondary side i
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/O PS4TTE F.XVIINATIM MJIDENT AkW.Section XI, Boiler and Pressure Vessel Code, requires that preservice exam-
- ination be done using the sa e equipnent and techniques which are used during inservice inspections.
Descriptions of the equipment used for the reactor ves-sel examination folicw:
1.
Flange Scanner The flange-to-shell weld and the flange ligament areas of the reactor pres-sure vessel were examined frca the tcp surface of the flange. Because of the high radiation in this area during any inservice examinaticn, mechanized equipment was used for the. inservice examination. A track was mounted on a o
frame that was concentric with and slightly larger than the stud hole circle.
It was long enough to cover slightly nore than one quadrant and was supported
. and located by alignnent pins in stud holes beyond the examination area and by a trusswork extending away frc= the vessel. A carriage moved along the track carrying either a three-transducer search unit along the closure mating surface to exanine the flange weld or a single-transducer search unit which l
could be rotated around each stud hole to examine the ligament areas. Photo-graphs of this nechanis are sh=c in Figure 1.-
4 2.
Vessel h* eld and No::le Insuection Device The vessel shell welds, no::le-to-shell welds, and no:zle radius sections p
lwere examined by means cf the par Model ISI-2 positioning device, shose
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.in Figure 2.
'Ihe des-ice was colmted on the flange of the vessel and positioned the search unit fixtures w-1 thin the vessel. An electric hoist atop the nast provided the vertical =crement along the vessel centerline by actuating a rultisection te:es:cping tube. Aninspectionboomgas mounted at the bottc2 of the tube and could be rotated through 360 by means of an electric n: tor.
Tne end of the boom could be extended outward.
t by a hydraulic rechanism. At the end of the boom was a rotator upon which the various bT exa inatica devices were counted.
In this way, complete flexibility of motion was provided to carry out the required Code examin.
ations.
The ' control console of the par device centained digital readouts for the hoist, rotation and extension notica.s, and the control module for the 7
rotator contained a digital readeut' fer its rotational position. Tne control consoles for both devices are sham in Figures 3 and 4.
The initial alignment of the device was provided by its acunting on three guide pins located Lin predeter.ined stud holes in the reactor pressure vessel flang'e.
Reference!1ocaticas on the reactor vessel shell which were used to locate the weld seats were provided by accurately located weld builduo index pads on the outside.of:the vessel,' adjacent to the intersections of the longi-
- tudinal. and circu=ferential. welcs and Ailich were located ultrasonically.
' Details can be found in C-E Frocedure 00000-NLE-061 and its appendix and
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h data sheets, which are contained in 1*citre 2. of this Preservice Examination 1 Prop and repcrt.
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No::le Scanner s
n e examination of the vessel no::le-to-shell welds from the vessel ID was perfomed using the shell side nozzle scanner. This scanner was mounted on the end of the par boom and was alinned on each no::le center-line by means of the par controls.
It was rotated about the no::le 1
centerline by the rotator on the end of the par boom, and had an inde-pendent mechanism for radial motion which was controlled by the hbclear Reflectoscope. Provision was also made for keeping the search units in contact with the vessel wall as the fixture was rotated around the cam-pound curvature of the vessel ID.
In this way flexibility of motion was provided to carry out the necessary examinations. A photograph of this device in operation is provided in Figure 5.
4.
Automated Data Acauisition System Both the flange examination device and the par device operated in con-junction with the Nuclear Reflectoscope, which is an instmment contain-ing five multiplexed Ur channels and common con. trol, data acquisition, and printing systems; each channel can operate one Ur transducer, meaning that up to five different transducers giving five different examin-ations can be mn simultaneously. D e channels are sequentially pulsed at a rate chosen in conjunction with the scan speed to give at least A) 25 percent overlap *between pulses for each transducer, and all returning i
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signals are examined. 'If an echo is observed, its a:plitude is compared electronically with the calibration curve for the examination being per-t fomed.
If the amplitude is a large enough fraction of the calibration curve (this fraction being set by the operator during the calibration),
a printout is produced giving the coordinates of the fixture being used, the channel (and therefore the search unit) receiving the signal, and amplitude of the signal, and the approximate depth in the material from which the' echo originated. Be Nuclear Reflectoscope is shown in Figure
-6.
Incorporated into the unit is'a cathode-ray screen which can be
-switched manually to display the signal seen by any of the channels.
For the flange ligament and flange weld examinations, the carriage mechanisms were controlled automatically by the Nuclear Reflectoscope.
For the-vessel shell examinations, using the par device, the device was controlled manually, with -the positional infomation fed ' electron-ically into the Nuclear Reflectoscope for use in triggering and'
- printing. he examination tool used for the examinations of the no::le welds from the vessel shell side was controlled from both the par control panel and the hbclear Reflectoscope. - Re following discussion is given to assist in the interpretation of the basic data output of the Nuclear
~
.Reflectoscope used for the automated examinations, which is a printout paper-tape. An example of the data printout and a guide to its inter-pretation is given in Figure 7; The first column of five digits and the
~O second colum of four show the two coordinates of the positioning device,
.e.g., the elevation and-angular position of the boom when the vessel shell 3 welds: are being examined.
Re. third column of ~seven digits shows the echo X-2
Date:
.. _2_01-77
]
Revisien_i by:
yyn infomation. H e firs $ digit is the channel numbeg; for the vessel shell welds,, channel #1 is 0, channels #2 and #3 are 45, and channels #4 and #5 are 60. The second, third and fourth digits show information about the largest received echo. The second digit is a measure of echo amplitude,1 being the smallest amplitude and 9 being the largest.
The depth information is given by the third and fourth digits. The time of the received signal which is of interest (between the front surface reflection and the back surface reflection) is divided electronically into segments called gates, and, den a printout occurs, the number of the gate in which the echo ap-pears is given by the third and fourth digits.
If a second echo, smaller than the first but still recordable, appears in the same series of pulses, its infomation is given in the fifth, sixth and seventh' columns, whose interpretation is iden*tical to that of the second, third and fourth.
A line of print taken from Figure 7 can be interpreted as follows:
10245 8764 2906423
%e first two columns show the location of the posjtioning device, e.g.,
102.45" grom the flange of the vessel and at 87.64 with respect to the
~
o vessel 0. Two indications appeared in channel.#2, e.g., from a 45 transducer. The larger was of amplitude 9 in gate 6, and the smaller was of amplitude 4 in gate 23. For any particular examination, the exact significance of each amplitude number and the approximate depth C
to which each gate corresponds can be obtained from the calibration
. sheets for that examination.
fa' During the automated examinations, all echoes which approached the report-ing level of 50 percent of DAC appear on the printout as amplitude 9 indications. The examination scans were done at an ultrasonic gain setting of twice the reference sensitivity, and indications of a size dmn to 20 percent D-\\C were recorded on 'the printout. All such indi-cations were examined and evaluated individually at reference sensi-tivity by the SNT-TC-1A UT. Level II operator of the Nuclear Reflecto-
. scope.
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Flange Weld Examination Flange Ligament Examination Figure 1 - Views of Reactor Vessel Flange Examination Device par Mode S-Vessel Examination Device l
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,t:; ~J J Figure 3 Figure 4 Control Console for Nozzle Examination par Examination Tool Device and Control Consoles
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2-n1 77
..O aevision:
i sy: 11n Channel number Larger echo Position Coordinates Smaller echo n
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y 10089 8764 17b000'0 10097 8764 1307122 10104 8764 1701000 t
10216 '8764 1401000 10245 8764 2906423 Example line 10389 8764 1823201 10435 8764 5512411 10563 8764 36120@
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000 2&3 45
- 9 - Largest 4&5 600 rs DATA ACQUISITIO'i - PRINTER ~ FORMAT
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Date:
2-01-77 Revision: 1 By: IIG
,0 EXAMINATION PROCEDURES The Louisiana Power and Light, Waterford III Steam Electric Station, Inservice Inspection Program was based upon meeting the requirements of the ASME Boiler and Pressure Vessel Code,Section XI,1974 Edition to the maximum extent pos-sible.
Paragraph IWA-1400 of the Code requires the preparation of written pro-cedures necessary for the conduct of the non-destructive examinations associated with the program. Accordingly, written procedures have been prepared for the conduct of volumetric, visual, and surface examinations. The procedures have been approved by the plant owner (LP&L) and the inservice inspection contractor (C-E/Aii).
Volumetric examinations were performed using ultrasonic methods. The prccedures prepared for the examinations comply with Appendix I of the 1974 Edition of the
All procedures will be retained by Louisiana Power and Light and will be retained for use on subsequent inservice examinations.
Revisions to any procedures deemed necessary because of experience gained by utilization or Code changes have been made and recorded using acceptable quality assurance practices.
(
A standard format has been employed during the preparation of all volumetric procedures.
A typical cutline has been included in this section to acquaint the user with structure, organization, and content of the procedures.
A table is also contained in this section which gives a complete listing of ali volumetric examination procedures. required to perform the shop preoperational examinations associated with the Louisiana Power and Light, Waterford III Steam Electric Station.
A second table lists all other procedures used in the examina-tions.
l
- The examination procedures are contained in Volume 2 of this program.
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Date:
7/28/75 O
Revision:
0 By:
e UT PROCEDURE OUTLINE 1.0 SCOPE 1.1 Area of Examination 1.2 Type of Examination 1.3 Time of Examination 1.4 Weld Configuration 1.5 Materials
2.0 REFERENCES
2.1 Reference Documents x
2.2 Applicable Drawings 2.3 Operational Manuals 3.0 PROCEDURE CERTIFICATION 4.0 PERSONNEL CERTIFICATION 4.1 Personnel Certification Requirements 4.2 Personnel Records l
5.0 EXAMINATION REQUIREMENTS 5.1 Examination Frequency 5.2 Examination Angles 5.3 Liquid Couplant 5.4 Surface Preparation 4(])
5.5 Weld Identification 5.6 Datum Point 1
5.7 Examination Coverage 6
~
Date:
7/ pans Revision:
-0 By:
UT PROCEDURE OUTLINE (Cont'd.)
,6.0 EQUIPMENT REQUIREMENTS 6.1 Examination Contractor's Equipment 6.2 Plant Owner's Equipment 7.0 CALIBRATION REQUIREMENTS 7.1 Reference Standard's 7.2 Reference Sensitivity Level 7.3-Times of Calibration 7.4 Calibration Response
>p:
'U 8.0
. INSTRUMENT CALIBRATION VERIFICATION 8.1 Amplitude Linearity 8.2 Amplitude Control Linearity 9.0 EXAMINATION SYSTEM CALIBRATION 9.1 Straight Beam Calibration 9.2 Straight Bham Calibration Check 9.3 Angle Beam Calibration 9.4 Angle Beam Calibration Check 10.0 EXAMINATION PROCEDURES 10.1 Straight Beam Examination of Weld and Heat Zone 10.2 Straight Beam Examination of Base Material h
10.3 Angle Beam Examinations
Date:
7/28/75
(})
Revision:
0 By:
UT PROCEDURE OUTLINE (Cont'd.)
11.0 EVALUATION CRITERIA 11.1 Recording of Indications 11.2' Evaluation of Indications 12.0 EXAMINATION RECORDS 12.1 Certification of Records 12.2 Filing of Records 13.0 EXAMINER'S CRITIQUE 13.1 Procedure Corrections and Additions l -(']}
13.2 Critique Report i
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Date: 2-01-77 Revision: 1 By:
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'V011bEIRIC EXAMINATION PROCEDURES Procedure Number NIP-230 Rev. 1 Ultrasonic Examination Procedures for Reactor Vessel longitudinal and Circumferential Nelds NIP-231 Rev. 1 Ultrasonic Examination Procedures for Reactor Vessel Shell Welds - Full Vee Techniques NIP-232 Rev.' 0 Ultrasonic Examinatio'n Procedures for Bottam Head to Reactor Vessel Weld, Bottom Head Meridional and Circum-ferential Welds and Tapered Portions of the Reactor Vessel I m er Shell longitudinal Welds NIP-233 Rev. 1 Ultrasonic Examination Procedures for Reactor Vessel to
, Flange Weld NIP-234 Rev. 1 Ultrasonic Examination Procedures for Reactor Vessel Flange Ligament Areas p NIP-235 Rev. I Ultrasonic Examination Procedures for Reactor Vessel to V
Nozzle Welds f
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NIP-236 Rev. 1 Ultrasonic Examination Procedures for Reactor Vessel Inlet and Outlet Nozzle Inner Radii f
NIP-238: Rev. 0 Ultrasonic Examination Procedures for Closure Head Meridional, Circumferential Dome and Flange Welds NIP-239 Rev. O Ultrasonic Examination Procedures for Closure Head Nozzle Welds
' NIP-241 Rev.~ 1 Ultrasonic Exarination Procedures for Closure Head Studs and Nuts NIP-242 Rev. 1 Ultrasonic Examination Procedures for Pressurizer Vessel Circumferential, Longitudinal and Nozzle Welds NIP-243 -Rev. l' Ultrasonic Examination Procedures for Pressurizer Support Stnicture Weld NIP-245 Rev. 0 Ultrasonic Exannation Procedures for Pressurizer Vessel Nozzle Inner Radii-NIP 247 Rev. 2 Ultrasonic Examination Procedures for Steam Generator gG Extension Ring and Tube Sheet Welds NIP-248 Rev. 1 Ultrasonic Examination Procedures for Steam Generator e
Imer (Higit Pressure) Head and Nozzle Welds
Date:
2-01-77 Revision: 1 By:3 O
T^se '
YOI1FETRIC EX.WI.%\\ TION PIOCEDURES (continued)
Procedure Nrber NIP-251 Rev. O Ultrasonic Exa-ination Procedures for Steam Generator Nozzle Inner Radii NIP-264 Rev. 0 Ultrasenic Exa:'ination Procedures for Steam Generator (Secondary Side) Upper Shell and Top Head Circumferen-tial Kelds, and Feedwater and Steam Outlet Nozzle Welds e
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Date:
2-01-77 Revision:
1 By: IIG TABLE 2
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Other procedures used in the perfomance of the Louisiana Power and Light, Waterford 3 Steam Electric Station, preservice examinations are:
~ Visual T:xamination Procedures 00000-ESS-029 Rev. 0 - Visual Examination Test Procedure 00000-ESS-002 Rev. 0 - Procedure for the Operation of the Inservice Inspec-tion Positioning Device for the Visual Examination of Reactor Pressure Vessel Interior Areas (with applicableAppendix)
' Surface Examination Procedures 00000-ESS-028 Rev. 0 - Liquid Penetrant Examination Procedure
~ Nechanical' Examination Procedure 00000-hE -061 Rev. 3 - Procedure for the Operation of the Insenice Inspec-tion Positioning Device for the Inside Surface Ultra-
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Date:
2-01-77 Revision:
1 By: IIG t
EVALUATI0fl CRITERIA It was the intent of this program to utilize, to the maximum extent possible, the latest published evaluation criteria. A listing of the various Code examination categories and the applicable evaluation criteria follows:
Examination Cateaory Evaluation Criteria Used B-A IWB-3510,Section XI,1974 Edition and Summer of 1974 Addenda B-B IWB-3511, Summer 1974 Addenda to Section XI B-C IWB-3511. Summer 1974 Addenda to Section XI B-D IWB-3512, Summer 1974 Addenda' to Section XI B-G-1 Stud:
IWB-3515, Summer 1974 Addenda to Section XI Nut:
NB-2585.4,Section III,1974 Edition B-H NB-5330,Section III, 1974 Edition
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B-I-l & 2 IWB-3517, Summer 1974 Addenda to Section XI C-A IWB-3511, Summer 1974 Addenda to Section XI C-B IWB-3511, Summer 1974 Addenda to Section XI C-C NC-5352,Section III,1974 Edition and Summer of 1974 Addenda C-D IWB-3515.1,Section XI, Summer 1974 Addenda to Section XI All other categories do not apply to shop preservice examinations.
4