ML17255A575

Rev 7 to Inservice Insp Program for 1980 - 1989

ML17255A575
Person / Time
Site:	Ginna
Issue date:	10/14/1983
From:	Anderson C ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17255A573	List: ML17255A572 ML17255A575 ML17255A576
References
NUDOCS 8312280381
Download: ML17255A575 (31)

Text

42 52A REY. PAGE GINNA STATION 1 PF 22 EFFECTIVE DATE.

ROCHESTER GAS 6 ELECTRXC CORPORATION January 1, 1984 SIGNATURE DATE TITLE: PREPARED BY IL APPENDIX B Ginna Station Xnservice Inspection Program For the 1980-1989 Interval QUALITY ASSURANCE REVIEW C. IL~~ I iv/P7 APPRDYED BYi 10/1 Q Pro ram Table of Contents

Introduction:

Discussion Program: ISI 1.0 Scope and Responsibility ISI 2.0 Inspection Intervals ISX 3.0 Extent and Frequency

/

ISI 4.0 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 PDR

TITLE: DATE QUALITY APPENDIX B 01/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 2 22 OF 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

TlTLE: DATE QUALITY APPENDIX B 01/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 3 22 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 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.

42 52C TITLE: DATE QUALITY APPENDIX B 01/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 4 Of 22 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 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.

ISI 2.0 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

TITLE: DATE QUALITY APPENDIX B 01/01/84 ASSURANCE Ginna Station

'ANUAL Inservice Inspection Program PAGE GINNA,STATION For the 1980-1989 Interval 5 22 OF 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 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 2.7 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.

'I

~g'UALITY TITLE:

APPENDIX B,.

DATE ASSURANCE Ginna Station 01/01/84'AGE MANUAL Inservice Inspection Program GINNA STATION For the 1980-1989 Interval 6 22 OF 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 High energy piping welds outside of containment shall be examined to the following extent and frequency:

3.4.1 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.

I 3.5 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.

3.5.1 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.

In the event 'of a seismic occurance greater than X

3.5.2 that for which the plant is designed to continue operation, Reference 6, a special examination of a limited number of tubes shall be conducted.

TITLE: DATE QUALITY AP PEND IX B 01/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 7 22 OF 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 Ultrasonic examinations shall be performed in accordance 4rith %he following:

4.1.1.1 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 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 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

TITLE: DATE QUALITY APPENDIX B 01/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 8 22 OF 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 Steam generator tubes shall be examined by a volumetric method (e.g. eddy current) or al-ternative method which is acceptable.

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 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

I i ~ X 42 52C TITLE DATE QUALITY APPENDIX B 01/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 9 22 OF 5.3.1 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.

5.4 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 a seismic occurrence, for which the combination'ith 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 ~

~ x TITLE DATE QUALITY APPENDIX B 01/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 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 Steam generator tubes that have defect indications

+ 40% through wall, as indicated by eddy current, shall be repaired by plugging or by sleeving.

5.7.1.4 Steam generator sleeves that have defect indi-cationsP 30% through wall, as indicated by eddy current, shall be repaired by plugging.

ISI 6.0 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.

~ 1 0

TITLE DATE QUALITY APPENDIX B ASSURANCE Ginna Station 01/Ol/84 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 11 22 DP 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 Repair of high energy piping welds outside of containment shall be performed in accordance with the applicable Code specified in Reference 11.

6.5 Repair of Steam Generator Tubes 6.5.1 Repair of steam generator tubes that have un-acceptable defects shall be performed by using a tube plugging technique or by sleeving.

6.5.2 Preventative sleeving of tubes as part of a pre-ventative maintenance program may also be accom-plished.

6.6 Repair of steam generator sleeves that have unacceptable defects shall be performed by using a tube plugging technique.

I 6.7 Repair of reactor coolant pump flywheel that have unacceptable defects shall be performed in accordance with Reference 12.

ISI 7. 0 S stem Pressure Testin 7.1 General Requirements 7.1.1 System pressure test shall be -conducted in accordance with Article IWA-5000 of Reference 11.

TITLE DATE QUALITY APPENDIX B 01/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 12 22 OF 7.1.2 Repairs of corr'oded areas shall be performed in accordance with Section 6.0 of this program.

7.2 Quality Group A Components 7.2.1 Whenever the reactor coolant system is closed after leak it has been opened, the system tested shall be 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 7.3.1 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

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TITLE DATE QUALITY

• APPENDIX B 01/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION ,For the 1980-1989 Interval 13 22 OF 7.4 Quality Group C Components 7.4.1 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.

However, Paragraphs IWB-1220 and IWC-1220 of Reference 1 exempt certain components from exami-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.

~ x TITLE DATE QUALITY APPENDIX B ASSURANCE Ginna Station .01/01/84 MANUAL Inservice Inspection'Program PAGE GINNA STATION For the 1980-1989 Interval 14 22 OF

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 1975 Addenda.

III, 1974 Edition through Summer

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".

TABLE ISI l.l Q QlIALITY'GROIIP A COMPOHFNTS, PARTS, AIID }II".I'IIODS OF EXAl'ITNATIOH R 2eZMA 0 0 CA C CcW'CQt FXAMIHATIOH HWXH CATFGORY H H

A<

ITFM TAIII.E COMPONFNTS AND PARTS 0 No. IMB-2500 TO BF. FXAMINFD METIIOD Reactor Vessel H

81.1 8-A Longitudinal and circumferential shall zelda in Volumetric 0m g

r Ill core region.

81.Z I

Longitudinal and circurmferential Melds in shell Volumetri.c I 80 A (other than those of Category 8-A snd BW) and EOHS d meridional and circumferential beam zelda in cD N Ql bottom head snd closure head {other than those I '5 R of Category B-C). $ MU

'LOO

~rtQ rtH LD P ft 81.3 Vessel-to-flange. and head-to<<flange circumferen- Volumetric 0I"0 ts ti.al Melds. Hg 81.4 B-D Pri.mary nozz'le<<to-'vessel Melds and nozzle inside Volumetric I8 80 4 tQ t ial Melds~ i ' t I.> i ~ I I . >g ~

~ ~ c I

I 9 81.5 Vessel penetrations, including control rod drive Visual (IMA-5000) snd instrumentation I

penetrations.

81.6 8-F Nozzle-to-safe-cnd Melds. Volumetric and Surface m C) 86.10 8-G-1 Closure head nuts. Surface C) 86.20 8-0-1 Closure studs, in place. Volumetric CO 86.30 8-G-I Closure studs, Mhen removed. Volumetric and Surface

I TADl.E ISI 1.1 (Cont'd)

Q COMPONFHTS, PARTS, AHD Ml'.TllODS OF FXA)lINATION H R

+Q U)KO PVo)N R c! W FXAMINATION o) a x L CATEOORY RQWH 0VRR ITF.M TABLE COMPONENTS AHD PARTS H ON No. I'll-2500 TO AF.- FXAHlHFD HFTllOD 0 R.

Reactor Vessel B6.40 B-C-1 Ligaments between stud holes. H Volumetric 0 m 8 N B6.50 B-C-1 Closure Mashers, bushings. Visual B-C-2 er e 0 B7.10 Bolts, studs and nuts. Visual 9 Q LOHN r p0 D8.10 Integrnlly-welded at tnchments. Surface C)m Ql W I M R B1.15 B-N-1 Vessel Interior. Visual

&8 o)o LOQ ff' co&A B-N-3 mr rt B1.17 Core-support structures. Visual 0 I u!

Hg 0 B1.18 Control rod drive housings. r) '5 Volumetric 6 8 8 0 Bl.le Exempted components.

I Visual, (IMA-5000) 9 Pressurizer B2.1 B-B l,ongitudinal and circumferrntinl welds. Volumetric O

B2.2 Nozzle-to-vessel welds nnd nozzle-to-vessel Volumetric Ill md iused sect l.on.

C)

B2.3 Ileater penetrations. Visual (IMA-5000) O CO B2.4 B-F Nozzle-to-safe-end welds. Volumetric and Surface

Q TABLE ISI 1.1 (Cont'd) H R

COMI'ONENTS, PARTS, AND MFTIIODS OI'XAMl'NATION 2e ZM&

WNCQ N

c'g Coc;Q V FXAMIHATIOH HOP WVR H H

CATEOORY H O N H h]

ITFM TABLE COMPONENTS AND PARTS 0 Ho. 1MB-2SOO TO BF, FXAMIHFD MFTIIOD pressurizer H C Ixj Q Y Volumetric 0 N

86. 60 B-C-1 Bolts nnd studs, in plae. 8 8 m B6.70 BW-1 Bolts and studs, chen removed. Volumetric and Surface 8 0 8 Q

'LD H g B6.80 B-C-1 Bo 1 t ing. Visual c)RQ W I'5 WSCQU R

B8.20 R-11 Integrally-Melded attachments. Surface MO AH cartQ R Visual (IMA-5000)

~ I ~

Ol" rt B2.10 B-P Fxempted components. td MP 0 rt %

B7 ~ 20 BW-2 Bolts, studs, and nuts. Visual I8 80 liest Exchnngers and Steam Generators 5

B3.1 Longitudinal and circumferential zelda, including Volumetric Tuhe sheet-to-head or shell Molds on the pri-mary side, Cl Hozzle-to-head velds anrl nozzle inside radiused Vo lume t r ic B3.2 O section on the primary side. m C>

Nozzle-to-safe-end Melds. Volumetric and 83.3 Surface .

CO 86 ~ 90 B-C-1 Bolts and studs, in place. Volumetric

TABLE ISI 1.1 (Cont'd) Q COHPONFNTS, PAIITS, AND HETIIOIIS OF FXAHINATTON R R3lMND WWMK RAW Coc'.Q V F.X AMIIIAT ION HWPM CATFGORY i-3 O N ITEM TABLF. COMPONFNTS AND PARTS H 0 g No. IWII-2500 TO nE EXAHIlrFD MFTIIOD R Itent Fxchnngers and Steam Generators H

B-c-1 Bolts studs, Mhen removed'. Volumetric and Om B6.100 and Surface 5 I W I" B6.110 B-c-1 Bolting. Visual 8 0 8 Q B-II Integrally-Mal ded at tnchments. Surface LOMB B8 ~ 30e M

08.40 CO I d

&8 WQ NH Mt7 B3.9 B"P Exempted components. V is us I (IWA-5000) ~NQ Qk" N 87 '0, BW-2 Bolts, studs, and nuts. Visual Mg 0 n7.40 8 ~

0 Piping I'ressure Boundary B4.1 Safe-end to piping Melds and safe-end in branch Volumetric and piping Melds. Surface B6. 150 B-C-l Bolts and studs, in place. Volume tr ic O m

B6.160 B-c-1 Bolts and studs, Mhen removed. Volumetric and C)

Surface C)

B6.170 B-c-l Bolting. Visual O

I B4-.5 B-J Circumferential and longitudinal pipe ~olds. Volumetri.c

TADI.E ISI 1.1 (Cont'd)

COMPONENTS, PARTS, AND HETllons OF FXAMINATION Q R

RgMlO EXAH I NATION Mc'.Q V CATEGORY HWWM ITFM TABLE COMPONENTS AND PARTS ON No, IMB-2500 TO BE FXAHlNEO MFTllOD O

R Piping Pressure Boundary B4.6 B-J Branch pipe connection velds exceeding six inch Volumetric I

dl.ameter. m B4.7. B-J Branch pipe connecTion velds six inch. diameter Surface and sma 1 ler.

B4.8 0-J Socket velds. Surface B10.10 B-K-1 Integrally velded attachments. Surface B11.10 B-K-2 Component supports. Visual I

B4.11 B-P Fxempted components. Visual (I@A-5000)

B7.50 B-Ci-2 Bolts, studs and nuts. Visual Pump I Pressure Boundary B6,180 B-C-1 Bolts and studs, ]n place. Volumetric I O 86.190 B-C-I Bolts and studs, vhen removed. Volumetric and I Surface C)

I C) 86..200 Il-C-I Bolting. Visual O 00 B10. 20 B-K-1 In t egra I 1 y-.ve 1 ded attachments. Surface B11.20 B-K-2 Component supports. Visual

TABLE lSI 1.1 (Cont'd)

COMPONFHTS, PARTS, AHD HFTIIOI)S OF FXAHTHATIOH .H 'a.

M RMlO WVMc:

Rc'W EXAMlNATlON CATFGORY MclQV RWNH ITFM TADI.F. COMPONENTS AND PARTS AN Ho. I'MD-2500 H h7 TO DF. F.XAI'IIHI;I) HFTIIOD 0 R

Pump Pressure Boundary B5. 6 8-L-I Pump casing Melds. Volumetric H Om m 85.8 B-P 8 8 Fxempted components. Visual rt 9 8 r) 87.60 BW-2 Bolts, studs, and nuts. Visual IA r Wv Reactor CooJant FlyMhecl.

~HO coP Pump Volumetric and P co ra jb W Surface I ~ R

&EMU

'LOQ rt H Valve Pressure Dnundary COft Q

~ r-rt 0 t'N B6.210 D-C-1 Bolts and studs, in place. Volumetric HP0 rt M B6.220 D-C-1 Bolts 8 4 anti studs, @hen removerl. Volumetric and Q Surface 86.230 D-G-1 Bolting. Visual B10.30 B-K-I integrally Melded attachments. Volumetric 'g 811.30 8-K-2 Component supports. Visual Cl m m c)

CO B6.6 8-M-1 Valve-body Mclds. Volumetric c) 86.8 B-P. Fxcmptcrl compnnents. Visual (lych-5000) 87.70 BW-2 Bolts, studs, anrl nuts. Visual

TABI.F. ISI 1.2 QVAI.ITY GROVP 0 A COMPONFNTS, PARTS, AND Hl:.TIIODS OF FXAHINATION H R

GNASH Q 3,'MlO WWMD R c' FXAHI NATION toad~

CATF.GORY PO'RH ITFH TABLF. COMPONFNTS AND PARTS H AN No. IMC-2520 TO BI'. I'.XAMINF.D 0

MFT1IOD R Pressure Vessels H

C1.1 C-A Circumferential butt welds. Volumetric 0 M 8 8 C1.2 Nozzle-to-vessle weMs. rt 4 Volumetric wr.

C3.10 Integrally-welded siipport nt tnchments. Surface 8 0 I Qr. v otn5 g co C4.10 C-D Bolts and studs. Volume t r ic ta 1'0 R C3.20 C-E rmMU

'LD0 N H Component supports. Visual fl C3.30 C-E CO

'Lo r0 r. txt Supports mechanical and hydraulic. Visual Hg 0 rt %

Piping 8 8 8 0 C2.1 C-F, CW Circumferential butt- welds. Volumetric C2.2 C-F, C-0 longitudinal weld joints in fittings. Volumetric I

C2.3 C-Fo C-G Brnnch pipe-to-pipe weld joints. Volumetric Bolts m C4.20 C-D and studs. Volumetric C)

C3.40 C-E-1 Integrally welded support nttnchments. Surface O C)

C3. 50. C-E-2 Component supports. Visual C3.60 Sup por te mechanical and l>y t au I I c. Visual

4 ~

f ~

Q TABLE ISI 1.2 (Cont'd) H R

COMPONFHTS, PARTS, ACCD MFTCIODS OF FXAMINATION R Z M&

W W Ql K RAW MclQV HWWH FXAMIHATI OH PVRH H O Q CATF.GORY H ITFM TABLE COMPOHFNTS AND PARTS 0 tto. INC-2520 TO BF. FXAMINFtt MF.TC COD Pumps H

@)HER Om C3. 1 C-F, CW Pump casing zelda. Volumetric 8 N C4.30

• C-D- Bolts and studs. Volume t r ic 8 0 8 Q I .Q C3.20 c-E-1 Integrally Meld ed support n t tnctimen ts. Surface C) M C-E-2 supports. Visual I'0 R C3.80 Component &8 MO LOG rt H Visual cort P C3.90 Supports mechnnical nnd hydraulic.

0 I". td Hg 0 Valves 8 8 Volumetric 8 0 C4.1 C>>F, CW Valve body velds.

C4.40 C-D Bolts nnd studs. Volumetric C3. 100 C-F.-1 Integrally Melded support nttnchments. Surface C3.110 C-I;-2 Component supports. Visual m

C)

C3.120 Sopports meet>anicnl nnd hyrlrnolic. Visual C)

O CO