ML17251A846

Rev 9 to QA Manual,App B Re Inservice Insp Program for 1980-1989 Interval

ML17251A846
Person / Time
Site:	Ginna
Issue date:	09/22/1986
From:	Anderson C, Jonathan Brown ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17251A845	List: ML17251A844 ML17251A846
References
NUDOCS 8611070332
Download: ML17251A846 (29)

Text

REV. PAGE QUALITY AS> RANCE MANUAL OF GINNA STATION

'<<<<TIYE DATectober 1s 1986 ROCHESTER GAS 6( ELECTRIC CORPORATION SIGIIATURE DATE TITLE: PREPARED BYs is/is/sS APPENDIX B Ginna Station QUALITY ASSURAIICE Inservice Inspection Program REVIEW s s.r/R For the 1980-1989 Interval APPROVED BYs V/iz/ag 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 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

0 TITLE: DATE P

QUALITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAL Inservice Inspection Program 2 22 GINNA STATION For the 1980-1989 Interval 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 Ginna!s Quality Assurance Program for Station Operation. This same program which is also in compliance with the referenced Section XI, provides the most acceptable guidelines and latest techniques currently being utilized in the performance of an inservice inspection.

Repairs to Quality Groups A, B and C components shall be performed in accordance with the Owner's Design Specification and Construction Code of the component or system. Later editions of the Construction Code or ASME Section III, either in its entirety or portions thereof, can also be used. If repair welding can not be performed in accordance with these rec{uirements, then Article 4000 of Reference ll will be used.

As indicated in Rochester Gas and Electric's report, Reference 4, and Augmented Inservice Inspection Program for high energy piping o'utside of containment has been established. 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

S 42 ~ 52 C 0

~ ~

T ITLEs DATE QUAI ITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAI Inservice Inspection Program GINNA STATION For the 1980-1989 Interval ,3 'DP 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.

42 ~ 52 C TITlEs DATE QUALITY APPENDIK B 10/1/86 ASSURANCE Ginna Station PAGE q MANUAL Inservice Inspection Program 22 GINNA STATION For the 1980-1989 Interval OF 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 was developed to the guidance provided 'rogram, in Reference 12, is detailed in Ginna's station procedures.

ISI 2.0 Ins ection Intervals 2.1 The inservice inspection (ISI) intervals for Quality Group A components shall be ten year intervals of service commencing January 1, 1970.

This program defines the 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 l.

2.2 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.

2.3 The inservice inspection intervals for Quality Group C 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 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 l.

~

~

4Ri62C TITLE) DATE QUALITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAL Inservice Inspection Program 22 GINNA STATION For .the 1980-1989 Interval OF inservice inspection intervals for the high

• 2.4 The 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 (

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.

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 enc 3.1 Quality Group A components, as listed in Table ISI-l.l shall be examined to the extent and of Refer-frequency as required in Table IWB-2500 ence l.

TITLEi DATE QUALITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAL Inservice Inspection Program 22 GINNA STATION For the 1980-1989 Interval 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.

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 ( 20/ detectable wall penetration) and up to a maximum of two hundred previously defect-free tubes ( 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 which the plant is designed to continue 'hat'for operation, Reference 6, a special examination of a limited number of tubes shall be conducted.

TITLE3 DATE QUALITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAL Inservice Inspection Program 22 GINNA STATION For the 1980-1989 Interval 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.

f 3.6 The reactor'coolant pump flywheel, listed in Table ISI-l.l, 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 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 l.

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.

42 ~ 52 C TITLE) DATE QUALITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAL Inservice Inspection Program 22 GINNA STATION For the 1980-1989 Interval OF 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 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.

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 5.1 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-shall be in accordance with Article IWC-3000 'ults 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

0 TITLEs DATE QUALITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAL Inservice Inspection Program 22 GINNA STATION For the 1980-1989 Interval 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 Repair 5.7.1.1 Steam generator tubes that have imperfections greater than 40/ through wall, as indicated by eddy current, shall be repaired by plugging or sleeving.

5.7.1.2 Steam generator sleeves that, have imperfections greater than 30/ through wall, as indicated by eddy current, shall be repaired by plugging.

5.7.2 Reporting 5.7.2.1 Within 15 days following the completion of the evaluation of each inservice inspection of steam generator tubes, the number of tubes required by 5.7.1 above to be plugged or sleeved in each steam generator shall be reported to the Commis-sion in a Special Report pursuant to Technical Specification 6.9.3.4.

.5.7.2.2 The complete results of the steam generator tube inservice inspection shall be submitted to the

0 TITLE) DATE QUALITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAL Inservice Inspection Program 22 GINNA STATION For the 1980-1989 Interval OF 4

Commission in a Special Report pursuant to Tech-nical Specification 6.9.3.4 within 12 months following the completion of the .inspection. This Special Report shall include:

1. Number and extent of tubes inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged or sleeved.

5.7.2.3 If the number of tubes in a generator falling into categories (a) or (b) below exceeds the criteria, then results of the inspection shall be considered a Reportable Event pursuant to 10 CFR 50.73. Oral notification of NRR shall be accomplished within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, .but no sooner than the next normal working day after the final review of the eddy current results. .A written followup report shall provide a description of investigations conducted to determine the course of the tube degradation and corrective measures taken to preclude recurrence. Categories (a) and (b) are:

(a) More than 10% of the total tubes inspected are degraded (imperfections greater than 20%

of the nominal wall thickness). However, previously degraded tubes must exhibit at least. 10% further wall penetration to be included in this calculation.

(b) More than 1% of the total tubes inspected are degraded (imperfections greater than the plugging limit) .

ISI 6.0 Re air Re irements 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:

~ '

TITLE) DATE QUALITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAL Inservice Inspection Program 22 GINNA STATION For the 1980-1989 Interval OF 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 wilds on Quality Groups A; B or C components of 2 inches or less, a surface examination shall be performed.

6.3 Surface defects in Quality Groups A, B or C bolts, studs, nuts and ligaments may be removed by mechanical means provided the removal of that defect. does not alter the basic configuration of the item. Bolts, studs and nuts that have de-fects that cannot be removed by mechanical means shall be replaced.

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.

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 i DATE QUALITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAL Inservice Inspection Program 22 GINNA STATION For the 1980-1989 Interval OF 7.1.2 Repairs of corroded areas shall be performed in a'ccordance 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 shall be tested to the requirements of Article IWB-5000 of Reference -'ll. 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 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 reguirements of Paragraph 7.2.2 of this Appends.x. 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 servo.ce once each period.

TIT LE i DATE QUALITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAL Inservice Inspection Program

~

22 GINNA STATION For the 1980-1989 Interval 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 ll; ISI 9.0 E~t'uality 9.1 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 KI "Rules for Inseryice 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.

TITLE) DATE QUALITY APPENDIX B 10/1/86 ASSURANCE Ginna Station PAGE MANUAL Inservice Inspection Program 22 GINNA STATION For the 1980-1989 Interval 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, B&PVC,Section XI, 1974 Edition through Summer 1976 Addenda.

8. ASME, B&PVC, Section V, 1974 Edition through Summer 1975 Addenda.

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

10. ASME, B&PVC,

'975 Addenda.

Section III, 1974 Edition through Summer 11.'SME, 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".

0 V TABLE ISI I.l A qOALiTY CnnNP A M COMPONFHTS, PARTS, AllD llFTllnnS OF RXAllrHATION R 3: Ul K3 WwM c:

2e i roc gv FXANINATION XL CAT FGORY M nw ITFH TAOI,E COHPOHFHTS AHD PARTS O C

Ho. I Mll-2500 TO OF. F.XAHlHF.D HETllnn Reactor Vessel H Bl.l Longitudinal and circumferential shall uelds in Volumetric 0 or

. 8 re I

m core region. rt g e 0 B1.2 8-B Longitudinal and circurmferentinl velds in shell Volumetric A (other than those of Category B-A nnd B-C) and nr io H 8 r >

meridiona) and circumferential beam uclds in CO 0

& rrl ar tg bottom head nnd closure lrcnd (other tlran those of Cntegory B-C). SCAN MQ rt&

r cart rrr N Bl ~ 3 Vessel-to-flange and head-to-flange circumferen- Volumetric Ol r-r~ 0 t5 tia1 vclds.

re ~

BI.4 B-0 Primary nozzle-to-'vessel vcldn and nozzle inside Voiumettic Q tial.vclds.

I BI.> Vessel penetrations, inclurllng control rod drive Visual (I@A-5000) anil instrumentation pcnctrnt iona.

I B1.6 Nozzle-to-safe-end uclds. snd a U Surface m m O6.10 B-C-I Closure head nuts.

rcmovcil.'olumetric Surface C)

B6.20 B-C-I Closrrre studs, in place. Vo lume t ric O6. 30 O-C-I Clonirre studs, uhcn Volumetric and Surface

TAQ1,E ISI .1 (Cont'd) A H

CO)IPONFIITS, PARTS, AND Hf'.TIIOI)S OI'XAHINATIOM, M 3;o)lO W~MN Zch FX AH 1 N AT I ON MCg t CATF.GOR'I H

O<

lTF.H TAIII.F. COHPONEtfTS Afff) PARTS 0 No. I Mll-2500 TO l)F. FXAHINf'.I) HF.TIIOD Reactor Vcsscl H

B6.40 B-C-I. Ligaments betucen stud hnlca-. Volumetric 0 m 8 6 86.50 B-C-1 Closure Mashers, bushinps. Visual rt g 8 0 e Q 87.10 BW-2 Bolts, studs snd nuts. Visual &HO r>

CO g co Ul D8.10 Integrnlly-ueldcd at tnclImcnta. Surface QJ h3 MR V)U MQ AM B1.15 B-N-1 Vessel Interior. Visual . COrtQ IO r0 ftr-u)

OC sl.i7 B-N-3 Core-aIIpport structures. .Visual HP 0 ft e

'u sl.ls Control rod drive hoI)sings. Volumetric 8 0 B1.19 Fxcmptcd components. v isi)al (I@A-5000) '-g ~

Pressurizer sz.i l.ongitudinnl and circumfcrcntinl uclds. Volume'tric 'O B2.2 tfozzle-to-vessel uelIls and nozzle-to-'vessel Vo lume tric rndiuscd section.

00 B2 ~ 3 lfcatcr penctrat(ons. Visual (IMA<<5000) CA IIZ.4 B-F Nozzle-to-safe-cnIf uelds. Volumetric and Surface ~

n 1

TAllLK ISl 1.1 (Cont'>I)

A H

COIIIOHFHTS, PARTS, ANn MFTIIOIIS OF FXAIIINATION RMN>C>

P P V> C'.

(o c FXAMINATION HW&r>

CATrrORY H

nw h7 a0 IT F.M Thill,K COMPOHFHTS AHD PARTS Hn. lull-2500 'O llF. I'.XAICIHI'.I) MF.TIIOD Pressurizer C

V

86. 60 8-G-I Bolts and studs, in plan. Volumetric B6.70 B-C-1 Bolts and studs, Vien 'rcmove>l. Volumetric and Surface Bb. 80 DW-1 Bol ting. Visual BB. 20 B-ll Integrally-Melded at tschmcnts. Surface 82.10 8-P Fxempted components. Visual (I@A-5000) 87.20 8-C-2 Bolts, studs, end nuts. Visuai Iieet Exchangers and Steam Gencrntors 83.1 I.ongitudinnl nn>l circ>>>>>fercnt lnl vclde, including Volumetric

"-I 0 Tube sl>cct-to-head or sl>cll Mcl>I>> on the pri-mary slclc, O

83.2 Nozzle-to-head Mclds and nozzle lnsl>le radiused Vo 1ume t r ic m section on the primary sl>lc.

C>

83.3 Nozzle-to-safe-end Melds. Volumetric and c>

Surface Co Ch

86. 80 B~-I Bolts and st>>ds,.in place. Volumetric

TADI.E iSI I ~ 1 (Cont'd) A COllPONFNTS PAIITS, ANO Ill'.TIIOI'IS OF FXAHINATION

~

RRNa3 W~U)c ZC 0 HCAVY'PP FXAHIllATION H CATFGORY PVROW R H

ITEH TARLF. COMPOHFNTS ANII PARTS MFTIIOD 0

Nn. lull-ZSOO To nr; rxAMINrli Ilent Fxchnngcrs nnd Stcam Generators n6.100 B-c-1 Bolts and studs, Mhen rcmovcd. Volumetric nnd 0 m A 8 Surface rt g Visual vr-S 0 B6.110 D-C-I Bo 1 t f.ng. O A I

Surface 'LO H0 D8.30, D-II Integrally-welded at tnchments. @op CO 0 p

Ql hl De.40

&RCOQ visuals (ILIA-5000) MArtM mrtP 83.9 Exempted components. X

'LO I rt Hg0 I ta B7.30 'W-2 n7.40 Bolts, studs, and nuts. Visual ft ~

0 8 8 8 0 Piping I'rcssure no>>ndary n4.1 'afe-end to piping acids nnd'afe-cnd fn branch Volumetric and piping Mclda. Surface n6.150 B-c-I Bolts and studs, in ploce. Volumetric D6.160 D-G-I Bolts nnd st>>ds, Mhen removed. Volumetric and Surface C) 06.170 B-6-1 noltfng. Visual O I Ch n4. 5 B<<J Circ>>mfcrentfal nnd 1ongit>>dfnnl pipe vclds. Volumetric

TADl.C ISI 1.1 (Cont'd) A COWONCNTS, PARTS, AND HFTIIOI)S OF CXAHINATION M M 3,'0) C3 WWMc CX AH I tt AT I Ott coc:NV CATFIsORY I TF.tf TADI.C COtIPONCNTS AND PARTS H OK No. IVII-2500 TO DI'. F.XAHlttl'.D HFTIIOD 0 Piping Prcssure Boundary H

84.6 B-J- Branch pipe connection vclds exceeding six inch Volumetric 0 m diame tcr. 8 e W V.

84.7 B-J Dranch pipe connexion Melds six inch diameter Surface O 0 and smaller. tb Q

'LO M5 Surface Co 8 D4.8 ~

. Socket velds. C) tO Ql h3 I M VsO CAD B1 o. 10 B-K-1 Integrally Mclded attachments. Surface MQ ftH co rt.S X LO V ft Visual Q V tg D11 ~ 10. B-K-2 Component supports. HP Q 84.11 Fxcmptcd components. Visual (I@A-5000) e 6 0

87.50 B-G-2 Bolts, studs and nuts. Visual '-g ~

Pump'Pressure Boundary 86.180 8-C-I Bolts and studs, ]n place. Vo 1ume t ric D 86.190 B-C-I Bolts nnd studs, Mhcn removed. Volumetric and ITl Surface C)

86. 200 8-C-1 Bolting. Visual O CO 810.20 B-K-1 Integrally-Mclded bttachmrnts. Surface

-K-2 Com onen su orts Visual,

TABLE ISI 1.1 (Cont'd) A H

COMPOHI'.HTS ~ PARTS, AND fll'.TIIOI)S OF EXAIfTNATION K R

W~MC Rrn&

EXAMIHATI OH roag>

CATFGORY O N ITFH TA III.F. COMPONENTS AHD PARTS M W Ho. I'Mfl-2SOO TO IIF. F.XAHfHI;I) 0 HF.TIIOD Pump Pressure Boundary M

BS.6 II-L-1 Pump casing vclds. Volume tric 0 m I 8 O m D5.8 B-1 Exempted components. Visual ff' r.

nI 0 87.60 B-C-2 Bolts, studs, nnd nuts. O Q Vieual 'lO MV co 0 lfenctor Coolant Pump Flyvlrccl. Volumetric and ED Ol QI hl Surface rb $ 0

%0 NH cort nI R Valve Pressure ffoundnry ClV rt Hg0 I 0

uf B6 ~ 210 D-C-1 Bolts nnd studs, in place. Volumetric N 8 B6.220 BW-1 Bolts 0 nnrf studs, MIIen removed. Volumetric and .

Surface B6.230 D-C-I Bo1 ting. Vieual B10.30 B-K-1 Integrally velrfcd attnchmcnts. Volume tr ic II11.30 B-K-2 n Component supports. Visual M Irl C)

CI B6.6 .D-M-1 Va 1 ve-body oa I de. Volumetric O

CQ D6.8 B-P. Fxcmptcrf components. Visual (If'-5000) fl7.70 B-C-2 IIolts, studs, anrf nuts. Vkaual

J I

TABI.E ISI 1.2 QUAI.TTY CROIIP B A

H COMPOIIFHTS, PARTS, AHA III',TIIODS OF FXAMTttATION R Ro)lO W~olC gCW OlCP &

FXAMTHATIOII CATF.GORY O N H

TTF.M TABI.F. COMPONFtITS ANO PARTS 0 Ho. ~ Tuc-2520 TO III'. I'.XAIIIIIF.I) MFTIIOD Pressure Vessels, Cl.i C-A Circumferential butt vclds. Volumetrfc Om 8 8 I

m C1.2 Nozzle-to-vessle zelda. Volumetric W v O 0

.e rA C3.10 C-C Integrally-uelded support" attachments. . Surface 'c) M 8 v'O

<<0 8 C4.10 C-n Bolts and studs. Volumetric orna ta I 8 OlU MO WM C3.20 C-E Component supports. Visual corfu

%D V ft X

o r.ta C3.30 C<<E Supports mechanical and hydraulic. Visual 0 rt 0

' S 4 fping 0" C2.1 C-F, CW CI rcumferentinl butt- vc Tds. Volumetric C2.2 C-F, C-0 T.ong f tud 1 nnl uc1 d go in ts fn f i t t in ps; Volumetric C2.3 C-F, C-C Brnnch pipe-to-pipe veld Joints. Volumetric O m

C4.20 c-n Bolts and studs. Volumetrfc C)

C3.4O C-E-1 TntegralJy welded support nttnctiments.. Surface CO C3.50. C-E-2 Component supports. ~

Vfsunl C3.60 Supports mechanfcnl and hyrnultc. Visual

A M

TABLE ISI 1.2 (Cont'd) R R 3lMlO COMPONFNTS, rhllTS, AND MFTllODS OF FXAMINATIOtI WQto&

C C to c FXAHltlATIOtl M AK CATFGORY 0 ITFM TAHI,E COHPONFNTS AND PARTS tto. IuC-2520 TO llF. 1;XAMINFI) MFTttnn M

Pumps 0 N 8 O m C3.1 C-F, C-C Pump casing zelda. Volumetric ft g Bolts studs. Volumetric O 0 c4.3o C-lt and O A MQ C3.20 C-E-1 Integrally velded support attachments. Surface coypu CO c) cn Qt C-E-2 supports. Visual I RtoQ C3.80 Component NO CtM C3.90 Supports mechnnical nncl hydraulic. Visual COt 0

Mg 0

-Ct t I Valves rt W O t1 c2 C4.1 C4o40 C-F, C-C C-D Valve bocly Melds.

Bolts nnd studs ~

Volumetric Volumetric

~

C3.100 .C-E-1 Integrally Melcled support nttnchmen'tn. Surface o

C3. 110 C-I'.-2 Component supports. Visual n Ill c3.12o Supports 'mechanical nnd hy<lrnnl I c. Visual C)

O CQ CZl