ML17255A768

QA Manual App B, Inservice Insp Program for 1980-1989 Interval.

ML17255A768
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Site:	Ginna
Issue date:	04/03/1984
From:	Anderson C ROCHESTER GAS & ELECTRIC CORP.
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42 52A QUALITY ASSURANCE MANUAL REV. PAGE GINNA STATION 1 DF 22 ril 1

~

~k 1984 ROCHESTER GAS 6 ELECTRIC CORPORATION SIGNATURE DATE TITLE: PREPARED BY e.II ~ nr'g APPENDIX B DUALITY Ginna Station ASSURANCE Inservice Inspection Program REVIEW 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 ISI 7.0 System Pressure Testing ISI 8.0 Records and Reports ISZ 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 8404i70i9i 8404ii PDR ADOCK 05000244 8 PDR

42 52C TITLE DATE QUALITY APPENDIX B 04/01/84 ASSURANCE Ginna Station MANUAL Xnservice Inspection Program PAGE GXNNA STATION For the 1980-1989 Interval 2 22 INTRODUCTION Appendix B of this Quality Assurance Manual describes Ginna's Xnservice Xnspection 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 ZI, 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 Electxic'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

TITLE DATE QUALITY APPENDIX B ASSURANCE Ginna Station 04/01/84 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 3 pF 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.

TITLE: DATE QUALITY APPENDIX B 04/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval pF 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 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 1.

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 lg 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.

TITLE DATE QUALITY APPENDIX B 04/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 5 OF 22 2.4 The inservice inspection intervals for the high energy piping outside of containment shall be ten year intervals of service beginning May 1, 1973, January 1, 1980, 1990 and 2000, respectively.

The ten year examination plan shall describe the distribution of examinations within the inspection interval in accordance with the requirements of Reference 4.

2.5 The inservice inspection intervals for the exami-nation of steam generator tubes shall not be more than 24 months. However, if over a nominal 2 year period (e.g., two normal fuel cycles) at least 2 examinations of the separate legs result in less than 10% of the tubes with detectable wall penetration ( 20%) and no significant (

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 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.

TITLE: DATE QUALITY APPENDIX B ASSURANCE Ginna Station 04/01/84 MANUAL Inservice Inspection Program PAGE GXNNA STATION For the 1980-1989 Xnterval 6 22 DF 3.2 Quality Group B components, as listed in Table XSI-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 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 APPENDIX B ASSURANCE Ginna Station 04/01/84 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 7 22 F

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 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.

TITLE DATE QUALITY APPENDIX B 04/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA,STATION For the 1980-1989 Interval 8 DP 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 in accordance with IWA-2200 of Reference 11.

Supports'nd 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 ' 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 XWA-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 data to aid in its characterization and

'revious 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 XWC-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

TITLE: DATE QUALITY APPENDIX B ASSURANCE Ginna Station 04/01/84 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 9 pp 22 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

TITLE DATE QUALITY APPENDIX B Ginna Station 04/01/84 ASSURANCE MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 10 pp 22 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 imper fection.

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. 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 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:

TITLE: DATE QUALITY APPENDIX B 04/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 11 22 DP 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.

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 DATE QUALITY APPENDIX B 04/01/84 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 12 DP 22 7.1.2 Repairs of corroded areas shall be performed in accordance with Section 6.0 of this program.

7 ' 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 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 shal'l be pressure tested in accordance with IWC 5221.

Inservice leakage tests may also be performed on other systems and components which are normally in sexvice once each period.

TITLE: DATE QUALITY APPENDIX B AS S URANCE Ginna Station 04/01/84 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 13 QF 22 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 Appendjx.

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 (BGPVC)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.

0 TITLE DATE QUALITY APPENDIX B ASSURANCE Ginna Station 04/01/84 MANUAL Inservice Inspection 'Program PAGE GINNA STATION For the 1980-1989 Interval 14 ~

pF 22

5. Nuclear Regulatory Commission, Regulatory Guide 1.83, Revision 1, dated July 1975, "Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes".

6. Ginna's Final Safety Analysis Report, Section 2.9.3.

7. ASME, B&PVC,Section XI, 1974 Edition through Summer 1976 Addenda.

8. ASME, BEPVC,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, BSPVC 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 1.1 A qoALITY CRONP A COMPONFNTS, PARTS, AtN) tlETNODS OF EXAllINATION R R3:MN PQM <

Mt FXAMINATION CATFGORY M O <

ITFH TABl.E COMPONFtiTS AND PARTS 0 Idyll-2500 METttnn R

No. TO DF. F.XAMINF.O Reactor Vessel H Bl.l 0 m Longitudinal and circumferential shall Melds in C

. Volumetric 8 8 core region.

V V-Nn B1.2 Longitudinal and circurmfetential Melds in shell Volumetric e Q (other than those of Category G-A nnd B-C) and C) HQ meridional and. circumferential beam zelda in O Ul Ql bottom head nnd closure hend (other than those I '0

~QSM+

I of Cntegory G-C). AM cortQ N aV0Vrt txf G1.3 Vessel-to-flange and head-to-flange circumferen- Volumetric Mg 0 ti.al Melds. N 'o 8 N G1.4 B-D PrimAry nozzle-to-'vessel zelda and nozzle inside Volumetric 8 0 ting.+olds.

I B1.5 Vessel penetrations, including control rod drive Visual (IMA-5000) nnd instrumentation I

penetrntions.

B1.6 Nozzle<<to-safe-end Me1ds. Volumetric and O Surface O G6.10 G-c-1 Closure head nuts. Surface O B6. 20 G-C-1 Closure'tuds, jn place. Vo lume t tie B6.30 B-c-1 Clonure studs, Mhen removed. Volumetric and'urface

T DLE ISI .I Cont d) A H

COMPONFHTS, PARTS, AHn METttnlis OF EXAMINATION a 3,'MlO Q

WQO)N RKN FXAMItlATION tA c,'g ~

CATF.GORY WVRH O N I TF.M TADI.F. COMPONEtiTS Atln PARTS H tto. Iun-2500 0

TO llF. F.XAlllH1'.0 MF.TllOD R Reactor Vessel H

B6. 40 B-C-1 . Ligaments betveen stud holes. Volume tr f c 0 m 8 8 aS.So B-c-1 Closure flashers, bushfngs. Visual K k" 8 0 B7.10 BW-2 Bolts, studs and nuts. Visual SA I LO H5 CO P Da.lo a-11 Tntegrnlly-Melded at tncliments. Sur'face ornate h5 R 1

WQ t'nil

'LD 0 Ct' B1.15 B-N-1 Vessel Tnterior. Visual . mrtQ> X C) P. ft 0 I td Bl.17 a-N-3 Core-support structures. Visual H>0 rt %

8 8 Bl.18 D-0 Control rod drive housings. Volumetric 8 0 S>.i9 n-P Exempted comp'onents. Vfsual (IMA-5000)

Pressurizer B2.1 a-B l.ongf tudinal and circumferentinl Melda. Volumetric Q fll B2.2 D-D Nozzl'e-to-vessel zelda and nozzle-to-vessel Volumetric rndiused section. C)

O 82.3 Ileater penetratfons. Visual (IMA-5000)-

112.4 B-F Hozz I e-to-sa fe-end we 1 ds. Volumetric and Surfnce

'I) A I

TAHLE IS I . I (Con t H R

COtII'OHEHTS, PARTS, AND MFTIII)DS OI'XhMItlhTION R3:M<0 QQQ)~

oi IBNWH F X AMIH AT ION CATECORV H n<

ITFM TAHI.E COMPONFNTS AND PARTS 0 R

Ho. Idyll-2500 TO HF, EXAMIHFI) MF.TIIOD Presnuri.zer H V 'oliimetric 0 rn

86. 60 8-C-I Bolts nnd studs, in pine. 5 8 86.70 8-C-1 Bolts and stiidn, Vien "rcmove<l. Volumetric and Siir f ace 8 0 a< A

<o H0 I . +

B6. 80 HW-I Bolting. Visual CO c)

P c<i Q rc I <ri In tcgra 1 ly-Me lded t tachmen ts. Surface WS CoU 88.20 B-ll a <oO NH Ct Visual (IMA-5000) Oi" 82.10 8-P Fxemptcd components. Hg 0 N 87.20 8-C-2 Holts, studs, and nuts. Visual rt <o 8 5 8 0 liest Exchnngers and Steam Generntors 83.1 I.ongit<idinnl nn<l circumfercnt inl Mclds, including Volumetric Tube alicct-to-liead or shell Mcl<ln on tlic pri-mnry side, O

83.2 tlozzle-to-head acids and nozzle inside radiused Volumetric <<l section on the primary si<lc.

CO 83.3 8-F Nozzle-to-safe-cnd acids, Volumetric and Surface CO 86.90 BW-I Bolts and stiids,.in place. Volumetric

TABLE ISI I.l (Cont'ct) A roMPONFNTS, PARTS, ANn MFTitOOS OF FXAMTNATTON R W3:MtO WQM C'.

Mc:Q >

F X AH I tlATI ON HWQH PVRH C AT F.OORY O N COMPONFNTS AND PARTS H TABLF. 0 IWtt-2500 To nr; rxAMl corti MF.Ttton R llent Exchnngers nnd Steam Generators H

ll6,100 BW-I Bolts and studs, Mhen removctl.- Volumetric and '0lrf m Surface 8 8 B6.110 n-c-I Bolti.ng. Visual 8 0 eQI Surface C) H0 B8.30, B-ll Integrally-velded attnchments. CDNm B8.40 I <

&8 WnrtH M U n-p ted components. V isttal (IMA-5000) > rt Q B3.9 Exemp ft 0 I 87 ~ 30, BW-2 Bolts, attends, and nuts. Vlsttal Hg 0 n7.40 8 5 0

. Piping t'rcssure nn>>ndary n4.1 Safe-end to piping zelda and safe-cnd in branch Volumetric and piping Meids. Surface I

B-c-I Bolts and stttds, in place. Volumetric n6.150 Cl Volumetric and O m B6.160 B-c-I Bolts nnd stttds, Mlten removed.

Surface CO n6.170 Bc-I no I t ing. Visual CO sD n4.5 Circttmferential nnd longit>><linnl pipe zelda. Volumetric

TABI.E I Sl 1. 1 (Cont ') .

CO>IPONEHTS, PARTS, AHD HETIIOI)S OF FXAHIHATION A

R Q 3,'top)

WQtoQ EXAM I tIATI Ott to C. N >

CATFGORY HWPH ITFM TABLE COMPONENTS AHD PARTS H ON ta No. IMB-2S00 TO BI'. F.XAMIttl'.0 HFTIIOD C) a Piping Pressure Boundary B4.6 Branch pipe connection ve1ds exceeding six inch Volumetric p m d i arne ter ~ 8 8 m six inch diameter Surface W V.

B-J Branch pipe connection Melds 6 0 8 Q and smaller.

%HO 'u rP COP P B4.8 B-J Socket velds. Surface &0) Ql ta I 'rt we WO rtH toa B10.10 B-K-1 Integrally Melded attachments.

'urface COrtQ Q Bli.lO B-K-2 supports. Uisual p r txI

~

Component HQ 0 rt %

B4.11 B-P Fxempted components'. Visual (IVh 5000) 8 8 p

g aQ 87.50 BWi-2 Bolts, studs and nuts. Visual Pump'Pressure Boundary B6.180 B-C-1 " Bolts and studs, )n place. Vo1uaie t r ic O

B6.190 B-C-1 Bo1ts nnd studs, Mhen removed. Volumetric snd o m Surface C)

B6..2no B-C-I Bolting. Visual, O Co B1 o. 20 B-K-.1 Integrally-voided attachments. Surface Ll 20 B-K-2 Com onent su orts. Visual

TABLE ISI 1.1 (Cont'd) A H

COHPONI;NTS, PARTS, AND HI'.Tll()l)S OF EXAHINATION R R"Z M lO

'PNMC RCP EX A HI tlAT I Ot(

MCPV CATFGORY PURR O 4 ITFH TA BI.E COHPONENTS AND PARTS H tlo. 0 Ion-ZSOO To BF. F.XAtlrNEO HF.TI IOD a Pump Pressure Boundary H

BS.6 B-L-1 Pump casing uclds. Volume t ric 0 m 8 II)

B5.8 Exempted components. Visual rI g ae r.n II) Gl 87.60 Bolts, studs, and nuts. Visual I I"'

LD H5 CO g Iteactor Coolant Pump Flyul)ccl. Volumetric and C)

I OI Ql

~ MU R Surface &S

&nrtH cortm N m I rt Hg0r0 Valve Pressure Boundary ~

ta B6.210 BW-1 Bolts and studs, in place. Volumetric rt %

8 8 8 0 B6.220 BW-1 Bolts and studs, ulIen removcrl. Volumetric and Surface B6.230 B-C-I Bolting. Visual B10.30 B-K-1 Integrally ueldcd attachments. Volumetric O B11.30 B-K-2 Component supports. Visual Q Pl C)

B6.6 Valve-body uclds. Volumetric I CO B6.8 B-P. Fxcmptcrl components. Visual (IMA-5000) oD B7.70 BW-2 Bolts, studs, anrl nuts. Visual

TAIII.E jS1 1.2 QUAI.ITY GROlIP II A COMPOHEHTS, PARTS, AHD III'.TIIODS OF FXAMIHATION g 3loIlO R

PNME2gNW tnaX RNPH V FXAMIHAT ION CATFOORY WVCH ON ITF.M TAIII.F. COMPOHFHTS AHD PARTS 0 Ho. IMC-2520 TO IIE I'.XAIII HFI) HF.TIIOD Pressure Vessels H

cl.l C-A Circumferential bott velds. . Volumetric 0 m I m

Cl . 2 C-0 Nozzle-to-vessle velds. rt

~ ~

Volumetric VI nI 0

'C-C NArv C3. 10 Integrally-welded s<<pport attachments. Surface vH5 u CO 5 coOl Ql ITI C4.10 C-D Bolts end studs. Volumetric I & R I SVlU LD 0 C3.20 C-E Component supports." Visual Cart m LD P Hg0 I

C3.30 C-E mechanical and

'upports hydraulic. Visual- 0 rI. %

nI 5 Pfping 8 0 C2.1 C-F, CW Cfrcomferential bott- vclrls. Volumetric C2:2 C-I', C-0 I.onpf todfnnl veld joints fn fittings. Volumetric C2.3 C-F, CW Ilrnnch pipe-to-pfpe veld Jnfnts. Volumetric m

C4.20 C-D IIo'Its and studs. Volumetric CO C3.40 C-E-1 Integrally welded support nttnchments. Surface O CD C3.50 C-E-2 Component, supports. Vieunl C3.60 Supports meehan'icn1 anrf hyrnol fc. Visual

A TABLE ISI 1.2 (Cont'd) R R ZMlO ~

COMPONENTS, PARTS, htlD MF.'I'IIODS OF FXAMINATION PNMERAN Mc',NV HWQH WVRH FXAHItlATION H O<

CATFGORY 0 I.E COHPONFNTS AND PARTS R

ITFH TAB tin. IMC-2520 TO BE EXAMINED MF.TIIOD Pumps 0 m I m

C3.1 C-F, C-C Pump casfng zelda, .Volumetric Volumetric e n C4.30 C-D Bolts and studs. e Q

r. >

C3.20 C-E-1 Integrally veided support nttact~ments. Surface CO g C0 m Ql I '0 C3.80 C-E-2 Component supports. Visual WS WO M>

rtH C3.90 Suppor ts mechanical nnd liydrau I f c. Visual HP 0 Or@

Valves rt 'o 8 8 0

c4.1 C-F, C-G Valve bocIy velds. Volumetric C4.40 C-D Bolts and studs. Volumetric C3.100 C-F.-l Integrally welded support attnctiments. Surface O

C3.110 C-E-2 Component supports. Vf.sual Ill C3.120 Supports meet>an ical nnd l~y<tranl f c. Visuai C) 00