ML17255A575
| ML17255A575 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/14/1983 |
| From: | Anderson C ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17255A573 | List: |
| References | |
| NUDOCS 8312280381 | |
| Download: ML17255A575 (31) | |
Text
GINNA STATION REY.
42 52A PAGE 1
PF 22 ROCHESTER GAS 6 ELECTRXC CORPORATION EFFECTIVE DATE.
January 1,
1984 SIGNATURE DATE TITLE:
PREPARED BY IL APPENDIX B Ginna Station Xnservice Inspection Program For the 1980-1989 Interval QUALITY ASSURANCE REVIEW APPRDYED BYi C. IL~~
I iv/P7 10/1 Q Pro ram Table of Contents
==
Introduction:==
Program:
Discussion ISI 1.0 Scope and Responsibility ISI 2.0 ISX 3.0 ISI 4.0 Inspection Intervals Extent and Frequency
/
Examination Methods ISI 5.0 Evaluation of Examination Results XSI 6.0 Repair Requirements ISI 7
0 System Pressure Testing ISI 0.0 Records and Reports
- ISI 9.0 Exemptions
References:
Tables:
ISI 1.1 Quality Group A Components, Parts and Method of Examination ISI 1.2 Quality Group B Components, Parts and Method of Examination Attachment A Quality Groups A, B, and C Exemptions 83i228038i 83i220P PDR ADOCK 05000244 8
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 01/01/84 PAGE 2
OF 22 INTRODUCTION Appendix B of this Quality Assurance Manual describes Ginna's Inservice Inspection 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 the 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 pinna'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 TlTLE:
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 01/01/84 PAGE 3
OF 22 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 Inservice Inspection 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 XI will be utilized for clarification and guidance.
It 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 ISI 1.0 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.
1.2 The Inservice Inspection Program for high energy piping outside of containment consists of main steam and feedwater piping welds is detailed in the Examination Plan for High Energy Piping.
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval 42 52C PAGE 4
Of 22 DATE 01/01/84 1.3 The Inservice Inspection Program for steam generator
- tubes, which is outlined in this program, was developed to the guidance provided in Reference 5, is detailed in Ginna's station procedures.
1.4 ISI 2.0 The Inservice Inspection Program for reactor coolant pump flywheels, which is outlined in.this
- program, was developed to the guidance provided in Reference 12, is detailed in Ginna's station procedures.
Ins ection Intervals'.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 ISI 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 '
The inservice inspection intervals for Quality Group B components shall be ten year intervals of service beginning on May 1, 1973, January 1,
- 1980, 1990 and 2000, respectively.
This program defines the ISI requirements for the second interval for Quality Group B components.
The ten year examination plan shall describe the distri-bution of examinations within the inspection interval in accordance with IWC-2400 of Reference 1 ~
2 '
The inservice inspection intervals "for Quality Group C components shall be ten year intervals of service beginning on May 1, 1973, January 1g
- 1980, 1990 and 2000, respectively.
This program defines the ISI requirements for the second interval Quality Group C components.
The ten year examination plan shall describe the distri-bution of examinations within the inspection interval in accordance with IWD-2400 of Reference 1.
1
s QUALITY ASSURANCE
'ANUAL GINNA,STATION TITLE:
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 01/01/84 PAGE 5
OF 22 2.4 The inservice inspection intervals for the high energy piping outside of containment shall be ten year intervals of service beginning May 1, 1973, January 1,
- 1980, 1990 and 2000, respectively.
The ten year examination 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 significant (Q 10%) further penetration of tubes with previous indications, the inspection interval of the individual legs may be extended to once every 40 months.
2.6 2.7 As permitted by IWA-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.
I 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 approximately 3 years shall be applied.
The ten year examination plan shall describe the distri-bution 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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~g'UALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX B,.
Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 01/01/84'AGE 6
OF 22 3.2 Quality Group B components, as listed in Table ISI-1.2, shall be examined to the extent and frequency as required in IWC-2400 and Table IWC-2500 of Reference 1.
3.3 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 3.4.2 3.5 3.5.1 3.5.2 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.
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.
I The extent and 'selection of steam generator tube examinations shall be as described in Sections C.4 and C.5 of Reference 5, with the interpretation that examination in a leg of all previously defective tubes (R 20% detectable wall penetration) and up to a maximum of two hundred previously defect-free tubes (4,20$ detectable wall pene-tration) is deemed sufficient in meeting the requirements of Reference 5.
In the event a primary to secondary leak exceeds technical specification limit, a limited number of tubes shall be examined at the next refueling outage.
X 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.
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
AP PENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 01/01/84 PAGE 7
OF 22 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 ISI-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 with the rules of IWA-2000 of Reference 1.
4.1.1 4.1.1.1 Ultrasonic examinations shall be performed in accordance 4rith %he following:
For ferritic vessels with wall thickness of 2-1/2 inches or greater, an ultrasonic examination shall be conducted in accordance with the rules of Appendix I of Reference 1.
4.1.1.2
- 4. 1. 1.3 For ferritic piping systems, an ultrasonic exami-nation shall be conducted in accordance with the rules of Appendix III of Reference 7.
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.
4.1.1.4 All indications which produce a response greater than 50% of the reference level shall be recorded.
l 1
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval PAGE 8
OF 22 DATE 01/01/84 All indications which produce a response 0'00%
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 in accordance with IWA-2200 of Reference 11.
Supports and hangers shall be visually inspected in accordance wtih IWD-2600 of Reference 1.
4.3 High energy piping welds outside of containment shall'be radiographically examined.
4 ~ 4 4 ~ 5 Steam generator tubes shall be examined by a volumetric method (e.g.
eddy current) or al-ternative method which is acceptable.
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 The evaluation of nondestructive examination results shall be in accordance with Article IWB-3000 of Reference 1.
All reportable indi-cations shall be subject to comparison with previous data to aid in its characterization and in determining its origin.
5.2 Quality Group B Components 5.2.1 The evaluation of nondestructive examination re-sults shall be in accordance with Article 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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X QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 01/01/84 PAGE 9
OF 42 52C 22 5.3.1 5.4 The evaluation of the visual examination results shall be in accordance with Article IWA-5000 of Reference 1 for hangers and supports and Reference 11 for pressure tests.
High Energy Piping 5.4.1 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 and Tube Sleeve Combinations 5.7.1 The evaluation of nondestructive examination results shall be as follows:
5.7.1.1 Plant operation,may resume when'll tubes and sleeves are within acceptable wall thickness
'criteria and the conditions of (a) and (b) are met:
(a)
When less than 10 percent of previously defect-free tubes or sleeves
- examined, (i.e.
4 20% of wall penetration) have developed detectable wall penetrations of greater than 20%,
and (b)
When previously degraded tubes or sleeves exhibit further wall penetration of< 10%.
NOTE:
An acceptable tube wall thickness is one which can sustain a LOCA in combination'ith a seismic occurrence, for which the plant is designed to continue operation, without a loss of function to Class 1
- systems, Reference 8.
Sleeves may be used to provide an acceptable tube.
1
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x QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 01/01/84 PAGE 10 OF 22 5.7.1.2 If no more than 3 tubes or sleeves have unacceptable wall thickness and the criteria of 5.7.1.1 are otherwise met, plant operation may resume after corrective measures have been taken.
When the above criteria are not met, the situation shall be immediately reported to the Nuclear Regulatory Commission.
Plant operation may resume after corrective measures are taken.
All abnormal degradation of steam generator tubes shall be reported with a Licensee Event Report (LER) in accordance with Technical Specification require-ments.
5.7.1.3 5.7.1.4 ISI 6.0 Steam generator tubes that have defect indications
+ 40% through wall, as indicated by eddy current, shall be repaired by plugging or by sleeving.
Steam generator sleeves that have defect indi-cationsP 30% through wall, as indicated by eddy current, shall be repaired by plugging.
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 Examinations associated with repairs or modifi-cations shall meet the applicable design and inspection Code requirements as described in the following paragraphs:
6.2.1 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 diameter, 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.
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QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE PAGE 01/Ol/84 1 1 DP 22 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.
6.4 6.5 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 6.5.1 6.5.2 Repair of steam generator tubes that have un-acceptable defects shall be performed by using a
tube plugging technique or by sleeving.
Preventative sleeving of tubes as part of a pre-ventative maintenance program may also be accom-plished.
6.6 6.7 Repair of steam generator sleeves that have unacceptable defects shall be performed by using a tube plugging technique.
I Repair of reactor coolant pump flywheel that have unacceptable defects shall be performed in accordance with Reference 12.
ISI 7. 0 7.1 7.1.1 S stem Pressure Testin General Requirements System pressure test shall be -conducted in accordance with Article IWA-5000 of Reference 11.
QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B Ginna Station Inservice Inspection Program For the 1980-1989 Interval DATE 01/01/84 PAGE 12 OF 22 7.1.2 Repairs of corr'oded areas shall be performed in accordance with Section 6.0 of this program.
7.2 7.2.1 Quality Group A Components 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 7.3.1 Quality Group B Components At or near theI end of each inspection interval, a
hydrostatic pressure test shall be performed on Quality Group B Systems and Components.
This test shall be 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 for uninsulated pipes and
,4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated pipes.
During each period, systems or portions of, systems not required to operate during normal reactor operation shall be pressure tested in accordance with IWC 5221.
Inservice leakage tests may also be performed on other systems and components which are normally in service once each period.
g ai
QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B Ginna Station Inservice Inspection Program
,For the 1980-1989 Interval DATE 01/01/84 PAGE 13 OF 22 7.4 7.4.1 Quality Group C Components Quality'Group C components shall have system pressure test in accordance with Article IWD-5000 of Reference 11.
ISI 8.0 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-1.1 and 1.2 with the result that only those non-exempt components are listed herein.
S
) REFERENCES
- 1. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BSPVC)Section XI "Rules for Inservice Inspection of Nuclear Power Plant Components",
1974 Edition through Summer 1975 Addenda.
2.
Code of Federal Regulations, Title 10, Part 50, dated January 1, 1978.
- 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.
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x QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B Ginna Station Inservice Inspection'Program For the 1980-1989 Interval DATE
.01/01/84 PAGE 14 OF 22
- 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, B6PVC,Section V, 1974 Edition through Summer 1975 Addenda.
9.
USAS B31.1.0 1967, "Power Piping".
10.
- ASME, B&PVC,Section III, 1974 Edition through Summer 1975 Addenda.
11.
- ASME, B&PVC Section XI, 1977 Edition through Summer 1978 Addenda.
- 12. Nuclear Regulatory Commission, Regulatory Guide 1.14, Revision 1, dated August 1975, "Reactor Coolant Pump Flywheel Integrity".
FXAMIHATIOH CATFGORY ITFM TAIII.E No.
IMB-2500 TABLE ISI l.l QlIALITY'GROIIP A
COMPOHFNTS,
- PARTS, AIID }II".I'IIODS OF EXAl'ITNATIOH COMPONFNTS AND PARTS TO BF. FXAMINFD METIIOD Q
R2eZMA 0 0 CA C CcW'CQt HWXH H
A<
H0 81.1 81.Z 81.3 81.4 81.5 81.6 8-A B-D 8-F Reactor Vessel Longitudinal and circumferential shall zelda in core region.
I Longitudinal and circurmferential Melds in shell (other than those of Category 8-A snd BW) and meridional and circumferential beam zelda in bottom head snd closure head
{other than those of Category B-C).
Vessel-to-flange.
and head-to<<flange circumferen-ti.al Melds.
Pri.mary nozz'le<<to-'vessel Melds and nozzle inside tial ~ Melds~ i '
t ~ I.>
i
~ c I
I. >g ~
I Vessel penetrations, including control rod drive snd instrumentation penetrations.
I Nozzle-to-safe-cnd Melds.
Volumetric Volumetri.c Volumetric Volumetric Visual (IMA-5000)
Volumetric and Surface H
0m r
g Ill I 08 A EOHS d
cD N Ql I '5 R
$ MU
'LOO rtH
~rtQ LD P ft 0I" ts Hg 0 I 8 8 0 4 tQ I
9 86.10 8-G-1 86.20 8-0-1 86.30 8-G-I Closure head nuts.
Closure studs, in place.
Closure studs, Mhen removed.
Surface Volumetric Volumetric and Surface m
C)
C)
CO
I
ITF.M No.
FXAMINATION CATEOORY TABLE I'll-2500 TADl.E ISI 1.1 (Cont'd)
COMPONFHTS,
- PARTS, AHD Ml'.TllODS OF FXA)lINATION COMPONENTS AHD PARTS TO AF.- FXAHlHFD Reactor Vessel HFTllOD QHR+ Q U)KO PVo)N R c! W o) a x L RQWH 0VRR ON H0R.
D8.10 B1.15 B1.17 B1.18 Bl.le B-N-1 B-N-3 B6.40 B-C-1 B6.50 B-C-1 B7.10 B-C-2 Ligaments between stud holes.
Closure Mashers, bushings.
Bolts, studs and nuts.
Integrnlly-welded at tnchments.
Vessel Interior.
Core-support structures.
Control rod drive housings.
I Exempted components.
Pressurizer Volumetric Visual Visual Surface Visual Visual Volumetric Visual, (IMA-5000)
H 0
m 8 N er e 09 Qr p LOHN 0
C)m Ql W I M R
&8 o)o LOQ ff' co&A mr rt 0
I u!
Hg 0 r) '5 6 8 8 0 9
B2.1 B2.2 B2.3 B2.4 B-B B-F l,ongitudinal and circumferrntinl welds.
Nozzle-to-vessel welds nnd nozzle-to-vessel md iused sect l.on.
Ileater penetrations.
Nozzle-to-safe-end welds.
Volumetric Volumetric Visual (IMA-5000)
Volumetric and Surface O
O Ill C)
CO
FXAMIHATIOH CATEOORY ITFM TABLE Ho.
1MB-2SOO TABLE ISI 1.1 (Cont'd)
COMI'ONENTS,
- PARTS, AND MFTIIODS OI'XAMl'NATION COMPONENTS AND PARTS TO BF, FXAMIHFD MFTIIOD QHR 2e ZM&
WNCQ c'g N
Coc;Q V HOP H WVR H H
O N H
h]
0
- 86. 60 B-C-1 B6.70 BW-1 B6.80 B-C-1 B8.20 R-11 B2.10 B-P B7 ~ 20 BW-2 B3.1 pressurizer CY Bolts nnd studs, in plae.
Bolts and studs, chen removed.
Bo 1 ting.
Integrally-Melded attachments.
Fxempted components.
Bolts, studs, and nuts.
liest Exchnngers and Steam Generators Longitudinal and circumferential zelda, including Tuhe sheet-to-head or shell Molds on the pri-mary side, Volumetric Volumetric and Surface Visual Surface Visual (IMA-5000)
Visual Volumetric H
Ixj Q 0 N 8 8 8 08 Q
'LD H g c)RQ W
I'5 R
WSCQU MO AH cartQ R
~ I
~ rt Ol" td MP 0 rt %
I 8 8 0 5
m B3.2 83.3 86 ~ 90 B-C-1 Hozzle-to-head velds anrl nozzle
- inside radiused section on the primary side.
Nozzle-to-safe-end Melds.
Bolts and studs, in place.
Volume tric Volumetric and Surface Volumetric Cl O m C>
CO
F.XAMIIIATION CATFGORY ITEM TABLF.
No.
IWII-2500 TABLE ISI 1.1 (Cont'd)
COHPONFNTS,
- PAIITS, AND HETIIOIIS OF FXAHINATTON COMPONFNTS AND PARTS TO nE EXAHIlrFD MFTIIOD Q
RR3lMND WWMK RAW Coc'.Q V HWPM i-3 O N H
g 0R B6.100 B-c-1 B6.110 B-c-1 B8 ~ 30e B-II 08.40 B3.9 B"P 87'0, BW-2 n7.40 B4.1 Itent Fxchnngers and Steam Generators Bolts and studs, Mhen removed'.
Bolting.
Integrally-Malded at tnchments.
Exempted components.
Bolts, studs, and nuts.
Piping I'ressure Boundary Safe-end to piping Melds and safe-end in branch piping Melds.
Volumetric and Surface Visual Surface Vis us I (IWA-5000)
Visual Volumetric and Surface H
Om 5 I W I" 8 08 Q LOMB CO M I d
&8 Mt7 WQ NH
~NQ Qk" N Mg 0 8 ~0 B6. 150 B-C-l B6.160 B-c-1 B4-.5 B-J B6.170 B-c-l Bolts and studs, in place.
Bolts and studs, Mhen removed.
Bolting.
Circumferential and longitudinal pipe ~olds.
Volumetric Volumetric and Surface Visual Volumetri.c O
O m
C)
C)I
EXAHINATION CATEGORY ITFM TABLE No, IMB-2500 TADI.E ISI 1.1 (Cont'd)
COMPONENTS,
- PARTS, AND HETllons OF FXAMINATION COMPONENTS AND PARTS TO BE FXAHlNEO Piping Pressure Boundary MFTllOD Q
RRgMlO Mc'.Q V HWWM ON OR B4.6 B-J Branch pipe connection velds exceeding six inch dl.ameter.
Volumetric Im B4.7.
B-J B4.8 0-J B10.10 B-K-1 B11.10 B-K-2 B4.11 B-P Branch pipe connecTion velds six inch. diameter and sma 1 ler.
Socket velds.
Integrally velded attachments.
Component supports.
I Fxempted components.
Surface Surface Surface Visual Visual (I@A-5000)
B7.50 B-Ci-2 Bolts, studs and nuts.
I Pump Pressure Boundary Visual B6,180 B-C-1 86.190 B-C-I 86..200 Il-C-I Bolting.
B10. 20 B-K-1 B11.20 B-K-2 Int egra I 1 y-.ve 1 ded attachments.
Component supports.
Bolts and studs,
]n place.
I Bolts and studs, vhen removed.
I I
Volumetric Volumetric and Surface Visual Surface Visual O
O C)
C) 00
EXAMlNATlON CATFGORY ITFM TADI.F.
Ho.
I'MD-2500 B5. 6 8-L-I 85.8 B-P 87.60 BW-2 B6.210 D-C-1 B6.220 D-C-1 TABLE lSI 1.1 (Cont'd)
COMPONFHTS,
- PARTS, AHD HFTIIOI)S OF FXAHTHATIOH COMPONENTS AND PARTS TO DF. F.XAI'IIHI;I)
Pump Pressure Boundary Pump casing Melds.
Fxempted components.
Bolts, studs, and nuts.
Reactor CooJant Pump FlyMhecl.
Valve Pressure Dnundary Bolts and studs, in place.
Bolts anti studs,
@hen removerl.
HFTIIOD Volumetric Visual Visual Volumetric and Surface Volumetric Volumetric and Surface
.H
'a.
M RMlO WVMc:
Rc'W MclQV RWNH A N H
h7 0R H
Om 8 8 rt 9 8 r)I Ar v
~HO W coP P co ra jb W I ~
R
&EMU
'LOQ rt H COft Q
~ r-rt 0 t'N HP0 rt M 8 4 Q
m 86.230 D-G-1 B10.30 B-K-I 811.30 8-K-2 B6.6 8-M-1 86.8 B-P.
87.70 BW-2 Bolting.
integrally Melded attachments.
Component supports.
Valve-body Mclds.
Fxcmptcrl compnnents.
Bolts, studs, anrl nuts.
Visual Volumetric Visual Volumetric Visual (lych-5000)
Visual
'g Cl m
CO m
c) c)
FXAHINATION CATF.GORY ITFH TABLF.
No.
IMC-2520 TABI.F. ISI 1.2 QVAI.ITY GROVP 0
COMPONFNTS,
- PARTS, AND Hl:.TIIODS OF FXAHINATION COMPONFNTS AND PARTS TO BI'. I'.XAMINF.D MFT1IOD A
HRQ 3,'MlO WWMD R c' toad~
GNASH PO'RH AN H0R C1.1 C1.2 C3.10 C4.10 C3.20 C3.30 C-A C-D C-E C-E Pressure Vessels Circumferential butt welds.
Nozzle-to-vessle weMs.
Integrally-welded siipport nt tnchments.
Bolts and studs.
Component supports.
Supports mechanical and hydraulic.
Piping Volumetric Volumetric Surface Volumetric Visual Visual H
0 M 8 8 rt 4 wr.
8 0I Qr. v co 5 otn g ta 1'0 R
rmMU
'LD0 N H CO fl
'Lo r0 r. txt Hg 0 rt %
8 8 8 0 C2.1 C-F, CW C2.2 C-F, C-0 C2.3 C4.20 C3.40 C-Fo C-G C-D C-E-1 C3. 50.
C-E-2 C3.60 Circumferential butt-welds.
longitudinal weld joints in fittings.
I Brnnch pipe-to-pipe weld joints.
Bolts and studs.
Integrally welded support nttnchments.
Component supports.
Sup por te mechanical and l>yt au I Ic.
Volumetric Volumetric Volumetric Volumetric Surface Visual Visual O
m C)
C)
4
~
f
~
ITFM tto.
FXAMIHATIOH CATF.GORY TABLE INC-2520 TABLE ISI 1.2 (Cont'd)
COMPONFHTS,
- PARTS, ACCD MFTCIODS OF FXAMINATION COMPOHFNTS AND PARTS TO BF. FXAMINFtt MF.TCCOD QHRR Z M&
W W Ql K RAW MclQV HWWH PVRH H
O Q H0 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-F.-1 C3.110 C-I;-2 C3.120 Pumps Pump casing zelda.
Bolts and studs.
Integrally Meld ed support n t tnctimen ts.
Component supports.
Supports mechnnical nnd hydraulic.
Valves Valve body velds.
Bolts nnd studs.
Integrally Melded support nttnchments.
Component supports.
Sopports meet>anicnl nnd hyrlrnolic.
Volumetric Volume tric Surface Visual Visual Volumetric Volumetric Surface Visual Visual O
H Om 8 N 8 08 Q I.Q
@)HER C) M I'0 R
&8 MO LOG rt H cort P 0 I". td Hg 0 8 8 8 0 m
C)
C)
CO