ML17258A980

to App B of QA Program for Inservice Insp

ML17258A980
Person / Time
Site:	Ginna
Issue date:	04/21/1981
From:	Anderson C, Curtis A ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17258A979	List: ML17258A977 ML17258A980
References
NUDOCS 8104280389
Download: ML17258A980 (35)

Text

42 2A R EV. PAGE QUALITY 'ASSURANCE MANUAL GINNA STATION EFFECTIVE DATEE ay , 81 ROCHESTER GAS & ELECTRIC'CORPORATION SIGNATURE DATE TITLE PREPARED BY APPENDIX B Ginna Station QUALITY Inservice Inspection Program ASSURANCE REVIEW V/~i/S (

For the 1980-1989 Interval APPROVED BY:

Pro ram Table of Contents

==

Introduction:==

Discussion Program: ISI 1.0 Scope and Responsibility ISI, 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 I

ISI 7.0 System Pressure Testing ISI 8.0 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

I C Ir p

I

42 52C TITLE) DATE QUALITY APPENDIX B 5/01/ 81 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 2 OF 22 INTRODUCTION Appendix 'B of. this Quali~ty Assurance Manual describes Ginna's Inservice Inspection'rogram 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-StampI Symbol.

The Inservice Inspection'rogram 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 Constructio'n 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

0 I

P

TITLEi DATE QUALITY APPENDIX B 5/01/ 81 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 3 F22 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.

0 gl l A

u II

42 52C TITLEi DATE QUALITY APPENDIX B 5/01/ 81 AS SURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 4 22 1.3 The Inservice Inspection Program for steam generator tubes, which is outlined in this pro-gram, was developed to the guidance provided in Reference 5,.isI 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 pro-vided in Reference 12, is detailed in Ginna's station procedures.

ISI 2.0 Ins ec'tion 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 ISI requirements for the second interval for Quality Group A components.

The ten year examination plan shall describe the of examinations within the inspection 'istribution 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.

r l

TITLE DATE QUALITY APPENDIX B 5/01/ 81 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval OF 22 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 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 ( T 20%) and no significant ( 7 10%)

further penetration of tubes with previous indi-cations, 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.

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 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 r

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 J

t

TITLE: DATE QUALITY APPENDIX B 5/01/81 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 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 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' 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 5, with the interpretation that examination in a leg of all previously defective tubes (Q 20% detectable wall'enetration) 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.

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.

f o I i'

H tI P

4I

TITLEi DATE QUALITY APPENDIX B 5/01/ 81 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 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 wj.th the rules of IWA-2000 of Reference 1.

4.1.1 Ultrasonic examinations shall be performed in accordance with the 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.

0 f ~

'l

42 ~ 52 C TITLEt DATE QUALITY APPENDIX B 5/01/ 81 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 8 22 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 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 I pump flywheel s 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 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

c ~

A j "I J

42 52C TITLE: DATE QUALITY APPENDIX B 5/01/81 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA" STATION For the 1980-1989 Interval OF 22 5.3.1 The evaluation of the visual examination results shall be in accordance with Article IWA-5000 of Reference 1.

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 all tubes and sleeves 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 or sleeves examined, (i.e.

C 20% of wall penetration) have developed detectable wall penetrations of greater than 20%, or (b) When previously degraded tubes or sleeves exhibit further wall penetration ofC 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. Sleeves may be used to provide an acceptable tube.

J

(

fl N

0

/

I

. J 1V

4 C TITLE DATE QUALITY APPENDIX B 5/01/ 81 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'bnormal 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 P 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-cations +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.

42 6RC TITLE DATE QUALITY APPENDIX B 5/01/81 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 11 OF 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 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 unaccept-,

able defects shall be performed by using a tube plugging technique or by sleeving. If sleeving is to be performed the requirements of 6.5.3 must be implemented.

6.5.2 Preventative sleeving of tubes as part of a pre-ventative maintenance .program may also be accom-plished provided the requirements of 6.5.3 are met.

6.5.3 During each steam generator inspection a maximum of 25 sleeves may be installed in each steam generator for repair or preventative maintenance.

Any additional sleeve installation shall require the approval of the Nuclear Regulatory Commisssion, Nuclear Reactor Regulation Branch.

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

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.

42 ~ 52 C TITLE: DATE QUALITY APPENDIX B 5/01/ 81 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 12 OF 22 7.1.2 Repairs of corroded 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 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 7.3. 1 At or near the end of each inspect'ion 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.

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.

5 < ~

,t 1F,

TITLE e 42 52C QUALITY APPENDIX B 5/01/81 ASSURANCE Ginna Station

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

REFERENCES

1. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PVC)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.

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.

'K l ~ J Al

~ e II

(

42 ~ 52 C TITLE DATE QUALITY APPENDIX B 5/01/81 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 14 22 OF

8. ASME, BGPVC, Section V, 1974 Edition through Summer 1975 Addenda.

9. USAS B31.1.0 1967, "Power Piping".

10. ASME, BGPVC, Section 1975 Addenda.

III, 1974 Edition through Summer

11. ASME, B6PVC 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".

~ g ~

rik 3

),

~ P"'" )f I p

g ~ p y p i 'l J,J

Q TABLE ISI 1 ~ 1 (Cont'd) H R

COHPONFNTS, PARTS, AND METHODS OF EXAHINATION RZMx3 WVM<<

M <<

RWQH EXAMINATION Pt O N CATEGORY ITEM TABLE COMPONENTS AND PARTS 0 No. IWB-2500 TO BF. EXAHINFD METHOD Heat Exchangers and Steam Generators H Volumetric and Q M 86.100 8-G-1 Bolts and studs, when removed. 8 6 Surface rt r.

ee 40 BW-1 Bolting. Visual 86.110 O rA 88.30, 8-H Integrally-welded attachments. Surface <<0 c) 8 V) 5 h3 88.40 I '0 we <<oU

'ClQ <<tH 83.9 8-P Exempted components. Visual (IWA-5000) m<<tQ Q BW-2 Bolts, studs, and nuts. Visual HgOr% 0 87.30,

<<t 'u 87.40 8 8 8 0 Piping Pressure Boundary R jll Volumetric 9 84.1 8-F Safe-end to piping welds and safe-end in branch and piping welds. Surface

86. 150 B-G-1 Bolts and studs, in place. Volumetric O m

86.160 B-G-1 Bolts and studs, when removed. Volumetric and Surface Vl CO O

86. 170 BW-I Bolting. Visual I

84.5 8-J Circumferential and longitudinal pipe welds. Volumetric

TABLE ISI 1.1 (Cont'd)

Q CONPONENTS, PARTS, AND METIIODS OF EXAMINATION M R

RZMIO WQMK EXAMINATION Ul C CATEGORY RWWH ITEM TABLE COlfPONENTS AND PARTS OQ H Id No. IWB-2500 TO BE FXAHINFD MFTHOD 0 Piping Pressure Boundary six inch Volumetric H B4.6 B-J Branch pipe connection welds exceeding diameter. Q Ill 8 Ill six inch diameter Surface rt 4 B4.7 B-J Branch pipe connection welds and smaller. III 0 III A MIME r v B4.8 Socket welds. Surface co5 5 C) Ol Ill I '0 B10.10 B-K-1 Integrally welded attachments. Surface. 8 MU ClO Ct M Cort Ill R B11.10 B-K-2 Component supports. Visual 'Lo I I.td H5Q Q B4.11 B-P Exempted components. Visual (IWA-5000) rt 0 6 8 Q

B7 ~ 50 BW-2 Bolts, studs and- nuts. Visual M Ill Pump Pressure Boundary 9 B6.180 B-G-1 Bolts and studs, in place. Volumetric B6.190 B-G-1 Bolts and studs, when removed. Volumetric and Surface Vl B6.200 B-G-1 Bolting. Visual CD B10.20 B-K-1 Integrally-welded attachments. Surface CO 5I B11.20 B-K-2 Component supports. Visual N 0

~ ~ ~

TABLE ISI 1.1 (Cont'd) A COMPONENTS'ARTS'ND MFTllODS OF EXAMINATION H ERMA WVCOCl M Cl.+ ~

EXAMINATION HO~ H CATEGORY COMPONENTS AND PARTS H O<

ITEM TABLE No. IWB-2500 TO BE EXAMINED METIIOD 0 Pump Pressure Boundary H

B5. 6 B-L-1 Pump casing welds. Volumetric I 0 Ul m 8 0 B5.8 B-P Exempted components. Visual rt 4 Visual 8 0 B7.60 BW-2 Bolts, studs, and nuts. 8 A Reactor Coolant Pump Flywheel. Volumetric and cD Vl Ql td Surface ) 'd

&S MU MA tt'H Valve Pressure Boundary co&A ft t.Cd Vo lume tric Hg0 0 B6.210 B-G-1 Bolts and studs, in place.

rt M 8

B6.220 B-G-1 Bolts and studs, when removed. Volumetric and 8 0 Surface H PP 8

B6. 230 B-G-1 Bolting. Visual B10. 30 B-K-1 Integrally welded attachments. Volumetric B1 1 . 30 B-K-2 Component supports. Visual B6.6 B-M-1 Valve-body welds. Volumetric O

B6.8 B-P Fxempted components. Visual (IWA-5000)

B7.70 BW-2 Bolts, studs, and nuts. Visual

TABLE ISI 1.1 (Cont'd) Q COMPONENTS, PARTS,'ND METIIODS OF EXAMINATION M Z ch g3 WWMC EXAMINATION M ~N.>

RWNH CATEGORY H

AN ITEM TABLE COMPONENTS AND PARTS No. IWB-2500 TO BF. FXAHINED METIIOD 0

Pressurizer C H V

B6. 60 B-G-1 Bolts and studs, in plae. Volumetric 0 tn C m

8 e B6.70 B-G-1 Bolts and studs, when removed. Volumetric and Surface enO Q

r. ve B6. 80 B-G-1 Bolting. Visual wM5 odd p C)0) 5 B8.20 . B-H Integrally-welded attachments. Surface &6 Mt]

C)O 0tH 006' B2.10 B-P Fxempted components. Visual (IVA-5000) m r.rf Or MQ 0 ta B7.20 B-G-2 Bolts, studs, and nuts. Visual rt M 8 5 IIeat Exchangers and Steam Generators 8 0 B3.1 B-B Longitudinal and circumferential welds, including Volumetric 9 Tube sheet-to-head or shell welds on the pri-mary side.

B3.2 B-D Nozzle-to-head welds and nozzle inside radiused Volumetric section on the primary side.

B3.3 B-F Nozzle-to-safe-end welds. Volumetric and Surface B6. 90 BW-1 Bolts and studs, in place. Volumetric

TABLE ISI 1.1 (Cont'd)

A COMPONFNTS, PARTS, AND METIIODS OF EXAMINATION H R R chlO WWMcl FXAMINATION Mc:Q V CATEGORY HWWH ITEM TABLE COMPONENTS AND PARTS H O 4 No. IWB-2500 To BF. FXAMINED METlIOD 0 Reactor Vessel Volumetric H B6.40 BW-1 Ligaments between stud holes.

0 N 8 0 B6.50 B-G-1 Closure Washers, bushings. Visual B7.10 BW-2 Bolts, studs and nuts. Visual 8 0

,8 A LO H Q B8.10 B-ll Integrally-welded attachments. Surface MP Q otnQ '6 tu I

B1.15 B-N-1 Vessel Interior. Visual . I tDQ SMUft H Mt'ft 00 ft Ql B1.17 B-N-3 Core-support structures. Visual 0 I.tZI Hg 0 B1.18 B-O Control rod drive housings. Volumetric rt M S 8 8 0 B1.19 B-P Exempted components. Visual (IWA-5000)

Pressurizer 8 B2.1 B-B Longitudinal and circumferential welds. Volumetric O

B2.2 B-D Nozzle-to-vessel welds and nozzle-to-vessel Volumetric m radiused section. Vl lleater penetrations. Visual (IWA-5000) c)

B2.3 O CO B2.4 B-F Nozzle-to-safe-end welds. Volumetric and Surface

TABLE ISI 1.1 A QUALITY GROUP A COMPONENTS, PARTS, AND METHODS OF EXAHINATION R3,'M&

PNME 2a A P MClXV EXAMINATION CATEGORY O N W

ITEM TABLE COMPONENTS AND PARTS 0 No. IWB-2500 TO BE EXAMINED HETHOD Reactor Vessel H Bl.l B-A Longitudinal and circumferential shall welds in Volumetric 0 8 e M

core region. rt 4 Kl e 0 B1.2 B-B Longitudinal and circurmferential welds in shell Volumetric e Q

{other than those of Category B-A and B-C) and 'N mH5l W meridional and circumferential beam welds in mggM c)m Ql h5 bottom head and closure head (other than those 'd of Category B-C). we MU wA AH co& m B1.3 Vessel-to-flange and head-to-flange circumferen- Volumetric

'EOt 'N tial welds. &50 I0 to rt W e 8 B1.4 B-D Primary nozzle-to-vessel welds and nozzle inside Volumetric 8 0 tiagwelds. g Cl m

8 B1.5 B-E Vessel penetrations, including control rod drive Visual (IWA-5000) and instrumentation penetrations.

Bl.6 Nozzle-to-safe-end welds. Volumetric and Surface B6. 10 B-G-1 Closure head nuts. Surface B6. 20 B-G-1 Closure studs, in place. Volumetric B6.30 B-G-1 Closure studs, when removed. Volumetric and Surface

TABLF. ISI 1.2 A QUALITY GROUP B COMPONENTS'ARTS'ND MFTllODS OF EXAHINATION RP.M&

WWvlc's Cl W M c EXAMINATION CATEGORY H

A<

W' ITFM TABLE COHPONENTS AND PARTS No. IWC-2520 TO BE FXAHINED MF.TllOD Pressure Vessels H

C1.1 C-A Circumferential butt velds. Volumetric 0 lA 8 8 Nozzle-to-vessle velds. rt 4 C1.2 Volumetric 8 0 8 Q C3.10 Integrally-welded support attachments. Surface 'EOH 5 co 8 5 'u C4.10 C-D Bolts and studs.- Volumetric otnmR I '0 MS (OU u)O rtH C3.20 C-E Component supports. Visual mrtfu Q

'LD t 0 I.lxl C3.30 C-E Supports mechanical and hydraulic. Visual Hg 0 rt M Piping e N 8 0 m

C2.1 C-Fe C-G Circumferential butt velds. Volumetric Mm 8

C2.2 C-F, CW Longitudinal veld )oints in fittings. Volumetric C2.3 C-F, CW Branch pipe-to-pipe veld )oints. Volumetric C4.20 C-D Bolts and studs. Volumetric Vl C3.40 C-E-1 Integrally velded support attachments. Surface O

C3.50 C-E-2 Component supports. Visual CO C3.60 Supports mechanical and hyraulic. Visual

MVMPS Q

TABLE ISI 1.2 (Cont'd) a pl QRMIO COMPONENTS, PARTS l AND METIIODS OF EXAMINATION 2e K W M<Q V I-I l-3 Q Q PL EXAMINATION ON CATEGORY O ITEM TABLE COMPONFNTS AND PARTS No. IWC-2520 TO BE FXAMINED MFTIIOD Pumps H

0 UI Volumetric 8 8 C3.1 C-F, CW Pump casing fields. rt 4 C4o30 C-D Bolts and studs. Volumetric 8 0 8 Q

'LOH Q C3.20 C-E-1 Integrally welded support attachments. Surface CON V

'6 5 C) Ul hS I

C3.80 C-E-2 Component supports. Visual I QMU

~

loo mrtQ rtH X

Supports mechanical and hydraulic. Visual lo r. rI.

C3.90 Ol" uI HP 0 Valves rI '0 III 0

C-F, CW Valve body fields. Volumetric v 59 C4.40 C-D Bolts and studs. Volumetric C3.100 C-E-l Integrally welded support attachments. Surface C3.110 C-E-2 Component supports. Visual C3.120 Supports mechanical and hydraulic. Visual