ML17250A754
| ML17250A754 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/05/1980 |
| From: | Anderson C, Cantrell A, Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17250A753 | List: |
| References | |
| NUDOCS 8011120401 | |
| Download: ML17250A754 (39) | |
Text
4 R EV.
PAGE 42 52A QUALITY ASSURANCE MANUAL GINNA STATION.
ROCHESTER GAS
& ELECTRIC CORPORATIO 4
1 0F 21 EFFECTIVE DATEI
'ovember 10, 1980 SIGHATURE DATE TITLE:
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval PREPARED 8Y:
QUALITY ASSURAHCE REVIEW APPROVED 8Y<
%/IEI Pro ram Table of Contents
==
Introduction:==
Program:
Discussion ISI 1.0 Scope and Responsibility It XSI 2.0 Inspection Intervals ISI 3.0 Extent and Frequency ISI 4.0 Examination Methods ISI 5.0 Evaluation of Examination Results ISI 6.0 Repair Requirements ISI 7.0 System Pressure Testing ISI 8.0 'ecords and Reports ISX 9.0 Exemptions
References:
Tables:
ISI 1.1 Quality Group A Components, Parts and Method of Examination ISX 1.2 Quality Group B Components, Parts and Method of Examination Attachment A Quality Groups A, B, and C Exemptions
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QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B Ginna Station Inservice Xnspection Program For the 1980-1989 Interval DATE 11/10/80 PAGE 2
21 OF INTRODUCTION Appendix B of this Quality Assurance Manual describes Ginna's Xnservice Insp'ection~ Program for the 120 month inspection interval commencing January 1,
1980 and ending December 31, 1989.
Included in this program are the following portions of systems and/or components:
Quality Group A Components Quality Group B Components Quality Group C Components High Energy Piping Outside of Containment Steam Generator Tubing Reactor Coolant Pump Flywheels Following the guidance of Reference 1,Section XI of the
- Code, Ginna's Inservice,Inspection Program adheres to the re-quirements of Section 50.'55a of'he Code of Federal Regulations, Reference 2.
This program,
- however, excludes the controls of the Authorized Nuclear Inspector, Enforcement Authority., Re-porting Systems, and N-Stamp, Symbol.
The Inservice Inspection'Program for Quality Groups A,
B and C components, as defined in Regulatory Guide 1.26, Refer-ence 3, is controlled by Ginna's -Quality Assurance Program for Station Operation.
This same program which is also in compliance, with the referenced Section XI, provides the most acceptable guidelines and latest techniques currently being utilized in the performance of an inservice inspection.
Repairs to Quality Groups A,
B and C components shall be performed in accordance with the Owner's Design Specification and Construction Code of the component or system.
Later editions of the Construction Code or ASME Section III, either in its entirety or portions thereof, can also be used.
If repair welding can not be performed in accordance with these requirements, then Article 4000 of Reference 11 will be used.
As indicated in Rochester Gas and Electric's report, Reference 4,
and Augmented Inservice Inspection Program for high energy piping outside of containment has been es-tablished.
The inspection program provides for volumetric examination on all circumferential butt welds situated at design break locations or at discontinuity locations where probable failure could occur.
Surveillance of these welds
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX B Ginna Station Inservice Xnspection Program For the 1980-1989 Interval DATE 11/10/80 PAGE 3
21 OF can detect material changes in advance of a potential failure, thereby assuring that the design basis or consequential main steam or feedwater break will not occur.
The Xnservice Inspectioni Program for steam generator tubes was developed to meet the 'guidance of Reference 5.
At regular intervals, tubes within each leg of the steam generator are examined and evaluated for acceptable tube wall thickness.
The Inservice Inspection Program for reactor coolant pump flywheels was developed to meet the guidance of Reference 12.
At the intervals suggested, the reactor coolant pump flywheel will be examined by either the volumetric or surface exami-=
nation method, and evaluated to the specified acceptance
=criteria.
Identification is given in Section 9.0 of Ginna's Inservice Inspection Program for those areas which deviate from the requirements of Reference 1.
Where applicable, currently approved edition and addendas of Section XX will be utilized for clarification and guida'nce.
Xt is the intent of Rochester Gas and Electric Corporation>> to continually apply appropriate changes in the Code which improves the overall quality of Ginna's total Inservice Inspection Program.
PROGRAM XSX 1.0 I
1.2 Sco e and Res onsibilit Components of Quality Groups A and B are listed in Tables ISI-1.1 and 1.2, respectively.
Quality Group C components are identified in Appendix A
of Ginna's Quality Assurance Manual.
The specific components to be examined for each Quality Group shall be defined in the Examination Plans by title and/or number.
The Inservice Inspection Program for high energy piping outside of containment consists of main steam and feedwater piping welds is detailed in the Examinations Plan for High Energy Piping.
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QUALITY ASSURANCE MANUAL GXNNA STATION TITLE:
APPENDIX B Ginna Station Inservice Xnspection Program For the 1980-1989 Xnterval DATE 11/10/80 PAGE 4
21 OF 1.3 1.4 The Inservice Xnspection Program for steam generator
- tubes, which is outlined in this pro-
- gram, was developed to the guidance provided in Reference 5, is: detailed in Ginna's station procedures.
The Inservice Inspection Program for reactor coolant pump flywheels, which is outlined in this program, was developed to the guidance pro-vided in Reference 12, is detailed in Ginna's station procedures.
ISI 2.0 Ins ection Intervals 2.1 The inservice inspection (ISI) intervals for Quality Group A components shall be ten. year intervals of service commencing January 1, 1970.
This program defines the XSI requirements for the second interval for Quality Group A components.
The ten year examination plan shall describe the distribution of examinations within the inspection interval in accordance with IWB-2400 of Reference 1.
2.2 The inservice inspection intervals for Quality Group B components shall be ten year intervals of service commencing on January 1,
1970.
This program defines the ISI requirements for the second interval for Quality Group B components.
The ten year examination plan shall describe the distribution of examinations within the inspection interval in accordance with IWC-2400 of Reference 1.
2.3 The inservice inspection intervals for Quality Group C components shall be ten year intervals of service commencing on January 1,
1970.
This program defines the ISI requirements for the second interval Quality Group C components.
The ten year examination plan shall describe the distribution of examinations within the inspection interval in accordance with IWD-2400 of Reference 1.
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QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 11/10/80 PAGE 5
21 OF 2.4 The inservice inspection intervals for the high energy piping outside of containment shall be ten year intervals of service commencing May 1, 1973.
The ten year ex'amination plan shall describe the distribution of) examinations within the inspection interval in accordance with the requirements of Reference 4.
2.5 The inservice inspection intervals for the exami-nation of steam generator tubes shall not be more than 24 months.
However, if over a nominal 2
year period (e.g.,
two normal fuel cycles) at least 2 examinations of the separate legs result in less than 10% of the tubes with detectable wall penetration
( ) 20%)
and no signifcant
( > 10%)
further penetration of tubes with previous indi-
- cations, the inspection intt rval of the individual legs may be extended to once every 40 months.
2.6 2.7 As permitted by INA-2400 of Reference 1, the inservice inspection interval for Quality,Groups A,
B and C and high energy piping outside con-tainment may be; extended as necessary.
The inservice inspection intervals for the reactor coolant pump flywheel shall be approximately 10 year intervals of service commencing on January 1,
1970.
For areas of high stress concentration at the bore and keyway, a reduced interval of approxi-mately 3 years shall be applied.
The ten year examination plan shall describe the distribution of examinations within the inspection interval in accordance with the requirements of Reference 12.
ISI 3. 0 Extent and Fre uenc 3.1 Quality Group A components, as listed in Table ISI-1.1 shall be examined to the extent and frequency as required in Table IWB-2500 of Refer-ence 1.
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QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval 42 52C PAGE 6
21 OF DATE 11/10/80 3.2 3.3 Quality Group B components, as listed in Table ISI-1.2, shall be examined to the extent and frequency's required in Table IWC-2500 of Reference 1.
Quality Group C components as described in the ten year examination plan shall be examined to the extent and frequency required in IWD-2400 and IWD-2600 of Reference 1.
3.4 3.4.1 High energy piping welds outside of containment shall be examined to the following extent and frequency:
During each period of the first inspection inter-val; all welds at design break locations and one-third of all welds at locations where a weld failure would result in unacceptable consequences, will be volumetrically examined.
3.4.2 During each period of succeeding intervals, one-third of all welds at design break locations and one-third of all welds at locations where a weld failure would result in unacceptable consequences, shall be volumetrically examined.
3.5 The 'extent and selection of 'steam generator tube examinations shall be as described in Sections C.4 and C.5 of Reference 1, with the interpretation that examination of all previously defective tubes
( > 20% detectable wall penetration) and up tp a maximum of two hundred previously defect-free tubes
( < 20% detectable wall penetration) is deemed sufficient in meeting the requirements of Refer-ence 5.
3.5.1 In the event a primary to secondary leak exceeds technical specification limits, a limited number of tubes shall be examined't the next refueling outage.
3.5.2 In the event of",.a seismic occurance greater than that for which the plant is designed to continue operation, Reference 6,
a special examination of a limited number of tubes shall be conducted.
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QUALITY ASSURANCE MANUAL GINNA STATION TITLEs APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 11/10/80 PAGE 7
OF 21 3.5.3 In the event of a major steam line or feedwater line break, or a loss-of-coolant accident (LOCA) which imposes a significant pressure transient on the steam generators and requires actuation of the engineered safe-guards, a special exami-nation of a limited number of tubes shall be conducted.
3.6 The reactor coolant pump flywheel, listed in Table XSI-1.1, shall be examined to the extent and frequency as required in Reference 12.
ISI 4.0 Examination Methods 4.1 Quality Groups A and B components shall be examined by the required visual, surface or volumetric methods.
These examinations shall include one or a combination of the following:
.visual, liquid penetrant, magnetic particle, ultrasonic, eddy-current. or radiographic exami-
-nation.
These
- methods, shall as a minimum, be in accordance wj.th the rules of INA-2000 of Reference 1.,
4.1.1 4.1.1.1 Ultrasonic examinations shall be performed in accordance with the following:
For ferritic vessels with wall thickness of 2-1/2 inches or greater, an ultrasonic examination shall be conducted in ac'cordance with the rules of Appendix I of Reference 1.
4.1.1.2 For ferritic piping systems, an ultrasonic exami-nation shall be conducted in accordance with the rules of Appendix III of Reference 7.
4.1.1.3 4.1.1.4 For components other than those listed in 4.1.1.1 and 4.1.1.2, an ultrasonic examination shall be conducted in accordance with the rules of Article 5 of Reference 8.
All indications" which produce a response greater than 50% of the reference level shall be recorded.
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QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 11/10/80 PAGE 8
21 OF 42 ~ 52 C 4.1.1.5 All indications which produce a response 100%
of the reference level shall be investigated to the extent that the operator can evaluate the
- shape, identity; and location of all such re-flectors in terms of the acceptance/rejection standards of IWA-3100 (b) of Reference 1.
The length of reflectors shall be measured between points which give amplitudes equal to 100% of the reference level.
4.2 Quality Group C components shall be visually examined for leakage during a system pressure test.
4.3 4.4 High energy piping welds outside of containment shall be radiographically examined.
Steam generator tubes shall be examined by a volumetric method (e.g.
eddy current) or al-ternative method which is accep'table.
4.5 Reactor coolant,'pump flywheels shall be examined by the required; surface and volumetric methods, in accordance with the requirements of IWA-2200 of Reference 1.
ISI 5.0 Evaluation of Examination Results 5.1 The evaluation of nondestructive examination results shall be in accordance with Article IWB-3000 of Reference 1.
All reportable indications shall be subject to comparison with previous data to aid in its characterization and in deter-mining its origin.
5.2 Quality Group B Components The evaluation of nondestructive examination re-sults shall be in accordance with Axticle IWC-3000 of Reference 1.
All reportable indications shall be subject to comparison with previous data to aid in its characterization and in determining its origin.
5.3 Quality Group C Components
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QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 11/10/80 PAGE 9
21 OF 42 ~ 5R C 5.3.1 5.4 5.4.1 The evaluation of the visual examination results shall be in accordance with Article IWA-5000 of Reference 1.
High Energy Piping The evaluation of nondestructive examination results shall be in accordance with Reference 9.
5.5 Indications that were recorded in previous pre-service or inservice inspections and which were not characterized as propagating flaws are acceptable for continued service.
5.6 The evaluation of any corroded area shall be performed in accordance with Article IWA-5000 of Reference 11.
5.7 Steam Generator Tubes 5.7.1 5.7.1.1 The evaluation of nondestructive examination results shall be as follows:
Plant operation'ay resume when all tubes are within acceptable wall thickness criteria and the conditions of (a) or (b) are met:
(a)
When less than 10 percent of previously defect-free tubes
- examined, (i.e.
C.
20% of wall penetration) have developed detectable wall penetrations of greater than 20%, or (b)
When previously degraded tubes exhibit further wall penetration of ) 10%.
NOTE:
An acceptable tube wall thickness is one which can sustain a LOCA in combination with a seismic occurrence, for which the plant is designed to continue operation, without a loss of function to Class 1
- systems, Reference 8.
For a maximum of ten tubes, sleeves may be used to provide an acceptable tube.
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 11/10/80 PAGE 10 21 OF 5.7.1.2 ISI 6.0 If no more than 3 tubes have unaccpetable tube wall thickness and the criteria of 5.7.1.1 is otherwise met, plant operation may resume after corrective meas'ures have been taken.
When the above criteria Rs not met, the situation shall be immediately reported to the Commission.
Plant operation may resume after corrective measures are taken.
All abnormal degradation to steam generator tubes shall be reported with a Licensee Event Report (LER) in accordance with technical specification requirements.
Re air Re uirements 6.1 Repair of Quality Groups A,
B and C components shall be performed in accordance with the appli-cable Subsections of Reference 11.
6.2 6.2.1 Examinations associated with repairs or modifi-cations shall meet the applicable design and inspection Code requirements as described.in the following paragraphs:
Whenever Quality Groups A,
B or C System modifi-cations or repairs have been made which involve new strength welds on components greater than 2
inches'iameter, the new welds shall receive both surface and 100 percent volumetric nondestructive examinations.
6.2.2 Whenever system modifications or repairs have been made which involve new strength welds on Quality Groups A,
B or C components of 2 inches or less, a surface examination shall be performed.
6.3 Surface defects in Quality Groups A,
B or C
- bolts, studs, nuts and ligaments may be removed by mechanical means provided the removal of that defect does not alter the basic configuration of the item.
Bolts, studs and nuts that have de-fects that cannot be removed by mechanical means shall be-replaced.
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QUALITY ASSURANCE MANUAL GINNA STATION TITLE)
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval 42 5RC PAGE 11 21 OF DATE 11/10/80 6.4 6.5 6.6 Repair of high energy piping welds outside of containment shall be performed in accordance with the applicable Code specified in Reference 11.
Repair of steam generator tubes that have un-acceptable defects shall be performed by using a tube plugging technique.
A maximum of ten tubes may be repaired with sleeves.
Repair of reactor coolant pump flywheel that have unacceptable defects shall be performed in accordance with Reference 12.
ISI 7.0.
7.1 S stem Pressure Testin General Requirements 7.1.1 System pressure test shall be conducted in accordance with Article IWA-5000 of Reference 11.'.
1.2 7.2 Repairs of corroded areas shall be performed in accordance with; Section 6.0 of this program.
Quality Group A Components 7.2.1 Whenever the reactor coolant system is closed after it has been
- opened, the system shall be leak tested to the requirements of Article IWB-5000 of Reference 11.
Temperature and pressure requirements of Figure 3.1-1, Section 3.1 of Ginna's "Technical Specifications" shall not be exceeded.
7.2.2 At or near the end of each inspection interval, a
hydrostatic pressure, test shall be performed on the reactor coolant system components.
This test shall be conducted in accordance with the require-ments of Article IWB-5000 of Reference 11.
Test pressures and temperatures shall be maintained for at least four hours prior to performing the visual examination.
Section 3.1 of Ginna's "Technical Specification" shall not be exceeded.
7.3 Quality Group B Components
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QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval 42 52C PAGE 12 21 OF DATE 11/10/80 7.3.1 At or near the end of each inspection interval, a hydrostatic pressure test shall be performed on Quality Group B Systems and Components.
This test shall'e conducted in accordance with the requirements of~ Article IWC-5000 of Reference 11.
When Quality Group A systems and components are also being pressurized, the pressure and temper-ature shall comply with the requirements of Paragraph 7.2.2 of this Appendix.
This test temperature and pressure shall be maintained for at least 10 minutes prior to the performance of the visual examination.
7.4 7.4.1 ISI 8. 0 Quality Group C Components Quality, Group C components shall have system pressure test in accordance with Article IWD-5000 of Reference 11.
Records and Re orts 8.1 Records and reports developed from those exami-nations performed in accordance with this Appendix shall be maintained in accordance with Article IWA-6000 of Reference 11.
ISI 9.0 Exem tions 9.1 Quality.Groups A,
B and C components exemptions are identified in Attachment A to this Appendix.
- nations, where certain conditions are met.
These exemptions will be applied to the components listed on Tables ISI-l.l and 1.2 with the result that only those non-exempt components are listed herein.
REFERENCES
- 1. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BGPVC)Section XI "Rules for Inservice Inspection of Nuclear Power Plant Components",
1974 Edition through Summer 1975 Addenda.
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QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval 42 52C PAGE 13 21 OF DATE 11/10/80 2.
Code of Federal Regulations, Title 10, Part 50, dated January 1,
1978.
t
- 3. Nuclear Regulatory Commission, Regulatory Guide 1.26, Revision 1, dated February 1976 "Quality Group Classifi-cations and Standards for Water,
- Steam, and Radioactive Waste-Containing Components of Nuclear Power Plants".
- 4. Rochester Gas and Electric Corporation Report "Effects of Postulated Pipe Breaks Outside the Containment Building", dated October 29, 1973.
- 5. Nuclear Regulatory Commission, Regulatory Guide 1.83, Revision 1, dated July 1975, "Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes".
- 6. Ginna's Final Safety Analysis Report, Section 2.9.3.
7.
ASME, BGPVC,Section XI, 1974 Edition through Summer 1976 Addenda.
8.
ASME, BGPVC, Section Addenda.
V, 1974 Edition through Summer 1975 9.
USAS B31.1.0 1967, "Power Piping".
10.
- ASME, B&PVC,Section III, 1974 Edition through Summer 1975 Addenda.
11.
- ASME, BGPVC Section XI, 1977 Edition through Summer 1978 Addenda.
- 12. Nuclear Regulatory Commission, Regulatory Guide 1.14, Revision 1, dated Auguset
- 1975, "Reactor Coolant Pump Flywheel Integrity".
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EXAMINATION CATEGORY ITEM TABLE No.
IWB-2500 TABLE ISI 1.1 QUALITY GROUP A
COMPONENTS,
- PARTS, AND METIIODS OF EXAMINATION COMPONENTS AND PARTS TO BF. FXAHINED MET1IOD A
RCZM&
WWUl&
Q)c:XV PL O<
0 81.1 81.2 81.3 81'.4 81 ~ 5 8-A B-B 8-D 8-E Reactor Vessel Longitudinal and circumferential shall welds in core region.
Longitudinal and circurmfexential welds in=shell (other than those of Category 8-A and 8-C) and meridional and circumferential beam welds in bottom head and closure head (other than those of Category B-C).
Vessel-to-flange and head-to-flange circumferen-tial welds.
Primary nozzle-to-vessel welds and nozzle inside tiara welds.
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c)
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Vessel penetrations, including control rod drive and instrumentation penetrations.
Volumetric Volumetric Vo'lumetric Volumetric Visual (IWA-5000)
H 0
M 8 9 rt 4 Wk 8 08 Qr P
'LD& Q cog g 0
orna R I 'Zf R
~m ma mO rtH cortm X ml rt orth'V 0
rt 5 8 8
- 8. 0 9
81.6 8-F
- 86. 10 8-G-1
- 86. 20 8-G-1
- 86. 30 8-G-1 Nozzle-to-safe-end welds.
Closure head nuts.
Closure studs, in place.
Closure studs, when removed.
Volumetric and Surface Surface Volumetric Volumetric and Surface O
O C) co CI
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~
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II
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FXAHINATION CATEGORY ITEM TABLE
'o.
IWB-2500 TABLE ISI 1.1 (Cont'd)
COHPONFNTS,
- PARTS, AND HFTIIODS OF EXAHINATION COMPONENTS AND PARTS TO BF. FXAMINFD METlIOD A
aRRMlO V~M cl MC',+~
RWNH Pt RR A<
0 B6.50 B7.10 B8.10 I
B1.15 B1.17 B1.18 Bl.19 B-G>>l BW-2 B-ll B-N-1 B-N-3 B6. 40 B-G-1 Reactor Vessel Ligaments between stud holes.
Closure Washers, bushings.
Bolts, studs and nuts.
Integrally-welded attachments.
Vessel Interior.
Core-support structures.
Control rod drive housings.
Exempted components.
Pressurizer Volumetric Visual Visual Surface Visual Visual Volumetric Visual (IWA-5000)
H tzf p 0 M 8 III O'
III 08 A LD H Q OIng X I'd R,
I 8MU M Q coram X EDI 'N 0!.U7 H5 0 III8 0 fu 8 R Ql9 B2.1 B2.2 B2.3 B2.4 B-F Longitudinal and circumferential welds.
Nozzle-to-vessel welds and nozzle-to-vessel radiused section.
Ileater penetrations.
Nozzle-to-safe-end welds.
Volumetric Volumetric Visual (IWA-5000)
Volumetric and Surface O
O m
c)
n FXANTNATION CATEGORY ITEM TABLE No.
IWH-2500 TABLE ISI 1.1 (Cont'd)
COMPONENTS,
- PARTS, AND MFTIIODS OF EXAMINATION COMPONENTS AND PARTS
'TO BF.
F.XAHINF.D METIIOD A
M~
P P CO Cl SCAN Mc'N V PURR O<
tu 0
B6.80 B-G-1 B8.20
~
B-II B2.10 B-P B7.20 B-G-2 B3.1 B-B B3.2 B-D B3.3 B6. 90 B-G-l B6.60 B-G-1 B6.70 BW-1 Pressurizer C
Bolts and studs, in plae.
V Bolts and studs, when removed.
Bolting.
Integrally-welded at tachments.
Exempted components.
Bolts, studs, and nuts.
lleat Exchangers and Steam Generators Longitudinal and circumferential welds, including Tube sheet-to-head or shell welds on the pri-mary side.
Nozzle-to-head welds and nozzle inside radiused section on the primary side.
Nozzle-to-safe-end welds.
Bolts and studs, in place.
Volumetric Volumetric and Surface Visual Surface Visual (IWA-5000)
Visual Volumetric Volumetric Volumetric and Surface Volumetric O
0 m
8 8 8 0 O Q tQ & Q cod 8 C) Ul Ql I '6 F>>
l SOlU
~ArtH mrtQ N 0 l.bt Mg 0 88 0 w QJ9 O
C) 00 C)
0 1
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EXAMINATION CATEGORY ITEM TABLE No.
IWB-2500 TABLE ISI 1.1 (Cont'd)
COMPONFNTS,
- PARTS, AND MFTllODS OF EXAMINATION COMPONENTS AND PARTS TO BF, EXAMINFD METllOD A
'2e Z MIO WWMc:
'Z c: W M KX V HPPH PVZH ON 0
B6.100 B-G-1 B6.110 BW-1 B8.30, B-11 BS.40 B3.9 B-P B7. 30, B-G-2 B7.40 B4.1 lleat Exchangers and Steam Generators Bo'its and studs, when removed.
Bolting.
Integrally-welded attachments.
Exempted components.
Bolts, studs, and nuts.
Piping Pressure Boundary Safe-end to piping welds and safe-end in branch piping welds.
Volumetric and Surface Visual Surface Visual (IWA-5000)
Visual Volumetric and Surface H
0 M
8 8 rt 4 9 08 Q I
cog' otnQW I'0 R
HN MU MO AH mrtm N
'LD I rt 0
I N
H5 0 rt M 8 8 8 0 R
Q19 r
m B6.170 B-G-1 B4.5 B-J B6. 150 BW-1 B6.160 B-G-1 Bolts and studs, in place.
Bolts and studs, when removed.
Bolting.
Circumferential and longitudinal pipe welds.
Volumetric Volumetric and
- Surface, Visual Volumetric O
O m
I c)
CQ CO
~
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EXAMINATIOtt CATEGORY ITEM TABLE No.
IMB-2500 TABLE ISI 1.1 (Cont'd)
CottPONENTS,
- PARTS, AND METttons OF EXAMINATION COttPONEHTS AND PARTS TO BE FXAMrt<ED Piping Pressure Boundary METltOD A
R Z tnt W~O)Cl RCP M~A~
PVRH A<
H0l4 84.6 B-J.
84.7 8-J 84.8 84.11 87.50 8-P 810. 10 8-K-1 811.10 8-K-2 Branch pipe connection welds six inch diameter and smaller.
Surface.
Socket welds.
Integrally welded attachments.
Component supports.
Exempted components.
Bolts, studs and nuts.
Surface Surface.
Visual Visual (IVA-5000)
Visual Pump Pressure Boundary Branch pipe connection welds exceeding six inch Volumetric diameter.
Q R 5 8 Wl.
6 08 Q I
'EO& Q coNP 0
NUl Ql
> "d R
&S AU
'EO 0 cortQ N LO f Cf' I". tu 0
rt 5 8 80 m 8 M Qp9 86.180 8-G-1 86.190 B-G-1 86.200 8-G-1 810.20 8-K-1 811.20 8-K-2 Bolts and studs, in place.
Bolts and studs, when removed.
Bolting.
Integrally-welded attachments.
Component supports.
Volumetric Volumetric and Surface Visual Surface Visual O
m CO
0 4.
~
~
EXAMINATION CATEGORY ITEM TABLE No.
IWB-2500 TABLE ISI 1.1 (Cont'd)
COMPONENTS,
- PARTS, AND MFT)lODS OF EXAMINATION COMPONENTS AND PARTS TO BE EXAMINED METllOD A
RRco83 WWcoc'P MCg ~
HWNM VL O<
tg 0
85.6 8-L-1 85.8 8-P 87.60 BW-2 86.210 8-G-1 86.220 8-G-1
- 86. 230 B-G-1 810.30 8-K-1 811.30 8-K-2 86.6 8-M-1 86.8 8-P
- 87. 70 BW-2 Pump Pressure Boundary Pump casing welds.
Exempted components.
Bolts, studs, and nuts.
Reactor Coolant Pump Flywheel.
Valve Pressure Boundary Bolts and studs, in place.
Bolts and studs, when removed.
Bolting.
Integrally welded attachments.
Component supports.
Valve-body welds.
Fxempted components.
Bolts, studs, and nuts.
Volumetric Visual Visual Volumetric and Surface Volumetric Volumetric and Surface Visual Volumetric Visual Volumetric Visual (IWA-5000)
Visual Im O
m C)
CO C) 0 M
4 0 rt 4 v r.
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EXAMINATION CATEGORY ITFM TABLF.
No.
IWC-2520 TABLE ISI 1 ~ 2 QVALITY G ROUP 9
COHPONFNTS,
- PARTS, AND HETllODS OF EXAMINATION COMPONFNTS AND PARTS TO BE FXAMINED MF.T110D QHRRZ MK3 Q 3Y M N 2a-c: N Mc;Q~
RNWH O<
H0 Pressure Vessels Cl.l C-A C1.2 C3.30 C-E C2.1 C2.2 C2.3 C4.20 C3.40 C3.50 C-F, CW C-F, CW C-F, CW C-D C-E-1 C-E-2 C3.10 C-C C4.10 C-D
'C3.20 C-E Circumferential butt welds.
Nozzle-to-vessle welds.
Integrally-welded support attachments.
Bolts and studs.
Component supports.
Supports mechanical and hydraulic.
Piping Circumferential butt welds.
Longitudinal weld joints in fittings.
Branch pipe-to-pipe weld points.
Bolts and studs.
Integrally welded support attachments.
Component supports.
Volumetric Volumetric Surface Volumetric Visual Visual Volumetric Volumetric Volumetric Volumetric Surface Visual 0
m 5 8 rt 4 en6 Qr v
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I CD CO CO C3.60 Supports mechanical and hyraulic.
Visual
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EXAMINATION CATEGORY ITEM TABLE No.
IWC-2520 TABLE ISI 1.2 (Cont'd)
COMPONENTS,
- PARTS, AND METIIODS OF EXAMINATION COMPONENTS AND PARTS TO BE FXAMINI'.D MFTIIOD A
R+ ~~ 0) IO QSMcl Mc:Q V AK h3 0
C3.1 C-F, CW C4.30 C-D C3.20 C3.80 C3.90 C-E-1 C-E-2 c4.1 C-F, CW C4.40 C-D C3.100 C-E-1 C3.110 C-E-2 C3.120 Pumps Pump casing welds.
Bolts and studs.
Integrally welded support attachments.
~
Component supports.
Supports mechanical and hydraulic.
Valves Valve body welds.
Bolts and studs.
Integrally welded support attachments.
Component supports.
Supports mechanical and hydraulic.
Volumetric Volumetric Surface Visual Visual Volumetric Volumetric Surface Visual Visual O
H 0
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