ML17258A458

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

ML17258A458
Person / Time
Site:	Ginna
Issue date:	01/11/1982
From:	Anderson C, Curtis A ROCHESTER GAS & ELECTRIC CORP.
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ML17258A459	List: ML17258A458 ML17309A215
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QUALITY ASSU ANCE MANUAL REY. PAGE GINNA STATXON 6 1 oF 22 EFFECTIVE DATE:

April Ol, 1982 ROCHESTER GAS Ec ELECTRXC CORPORATION SIGNATURE DATE TITLE: PREPARED BY:

APPENDIX B QUALITY Ginna Station ASSURANCE i u/az Inservice Inspection Program REVIEW For the 1980-1989 Interval APPRDYED BY: ~/%

Pro ram Table of Contents Xntroduction: Discussion Program: XSI 1.0 Scope and Responsibility ISI 2.0 Inspection Xntervals ISI 3.0 Extent and Frequency ISI 4.0 Examination Methods ISX 5.0 Evaluation of Examination Results ISI 6.0 Repair Requirements XSI 7.0 System Pressure Testing ISI 8.0 Records and Reports ISX 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 820ii5 820i20058805000 PDR ADOC~

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42 2C TITLEi DATE QUALITY APPENDIX B 4/01/82 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GXNNA STATION For the 1980-1989 Interval 2 0F 22 INTRODUCTION Appendix B of this Quality Assurance Manual describes Ginna's Inservice Inspection Program for the 120 month inspection interval commencing January 1, 1980 and ending December 31, 1989. Included in this program are the following portions of systems and/or components:

Quality Group A Components Quality Group B Components Quality Group C Components High Energy Piping Outside of Containment Steam Generator Tubin'g 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 Xnspector, 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 XX, provides the most acceptable guidelines and latest techniques currently being utilized in the performance of an inservice inspection.

Repairs to Quality Groups A, B and C components shall be performed in accordance with the Owner's Design Specification and Construction Code of the component or system. Later editions of the Construction Code or ASME Section III, either in its entirety or portions thereof, can also be used. If repair welding can not be performed in accordance with these requirements, then Article 4000 of Reference 11 will be used.

As indicated in Rochester Gas and Electric's report, Reference 4, and Augmented Inservice Inspection Program for high energy piping outside of containment has been es-tablished. The inspection program provides for volumetric examination on all circumferential butt welds situated at design break locations or at discontinuity locations where probable failure could occur. Surveillance of these welds

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TITLEt DATE QUALITY APPENDIX B 4/01/82 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATXON For the 1980-1989 Interval 3 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 Xnspection 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 Xnspection Program.

PROGRAM ISI 1.0 Sco e and Res onsibilit Components of Quality Groups A and B are listed in Tables ISI-l.l 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.

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TITLE: DATE QUALITY APPENDXX B 4/01/82 ASSURANCE Ginna Station MANUAL Inservice Xnspection Program PAGE GINNA STATION For the 1980-1989 Interval 4 DF 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, 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 pro-vided 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 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 l. I 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 l.

TITLEi DATE QUALITY APPENDIX B 4/01/82 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 5 oP 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 (> 20$ ) and no significant (~ 108) 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 Ext.ent and. Fre uenc 3.1 Quality Group A components, as listed in Table ISI-l.l shall be examined to the extent and frequency as required in Table IWB-2500 of Refer-ence l.

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42 52C TITLEi DATE QUALITY APPENDIX B 4/01/82 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 6 oP 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 l.

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 l.

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 ( 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.

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aa.5Z c TITLE: DATE QUALITY APPENDIX B ASSURANCE Ginna Station ..'4/01/82'AGE MANUAL Inservice Inspection Program GINNA STATION For the 1980-1989 Interval 7 DP 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-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 l.

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'.l.l 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.

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42 52C TITLE) DATE QUALITY APPENDIX B 4/01/82 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 8 DF 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 pump flywheels shall be examined by the required surface and volumetric methods, in accordance with the requirements of IWA-2200 of Reference l.

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 l. 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 l. All reportable indications shall be subject to comparison with previous data to aid in its characterization and 'in determining its origin.

5.3 Quality Group C Components

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TITLEi 'DATE QUALITY APPENDIX B 4/01/82 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 9 DP 22 5.3.1 The evaluation of the visual examination results shall be in accordance with Article IWA-5000 of Reference l.

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) and (b) are met:

(a) When less than 10 percent, of previously defect-free tubes or sleeves examined, (i.e.

C 208 of wall penetration) have developed detectable wall penetrations of greater than 20%, and (b) When previously degraded tubes or sleeves exhibit further wall penetration of<10%.

NOTE: An acceptable tube wall thickness is one which can sustain a LOCA in combination 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.

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42 52C TITLE) DATE QUALITY APPENDIX B 4/01/82 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 10 oF 22 5.7.1.2 If no more than 3 tubes or sleeves have unacceptable wall thickness and the criteria of 5.7.1.1 are otherwise met, plant operation may resume after corrective measures have been taken. When the above criteria are not met, the situation shall be immediately reported to the Nuclear Regulatory Commission. Plant operation may resume after corrective measures are taken. All abnormal degradation of steam generator tubes shall be reported with a Licensee Event Report (LER) in accordance with Technical Specification require-ments.

5.7.1.3 Steam generator tubes that have defect indications R40% 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.

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42 52C TITLEi DATE QUALITY APPENDIX B 4/01/82 ASSURANCE Ginna Station MANUAL Inservi'ce 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 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.

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42 52C TITLE: DATE QUALITY- APPENDIX B 4/01/82 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval Of 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 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 ll. 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

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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.

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.

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42 52C TITLE) DATE QUALITY APPENDIX B 4/01/82 ASSURANCE Ginna Station Inservice Inspection Program PAGE MANUAL'INNA STATION For the 1980-1989 Interval 13 DP 22 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-l.l and 1.2 with the result that only those. non-exempt components are listed herein.

REFERENCES

l. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BEPVC)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, BSPVC,Section XI, 1974 Edition through Summer 1976 Addenda.

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42 52C TITLEi DATE QUALITY APPENDIX B 4/01/82 ASSURANCE Ginna Station MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 14 oF 22

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

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

10. ASME, B6PVC, Section 1975 Addenda.

III, 1974 Edition through Summer ll. ASME, BEPVC Addenda.

Section XI, 1977 Edition through Summer 1978

12. Nuclear Regulatory Commission, Regulatory Guide 1.14, Revision 1, dated August 1975, "Reactor Coolant Pump Flywheel Integrity".

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TABLE ISI I.l {Cont'd) Q 'NCAA COHPONFNTS, PARTS, AND HETliOOS OF FXAHTNATTON Fi z roG V V Vl C MCXV I I FX AM 1l AT ON P t" C R CATEGORY H

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ITEM TABLF. COMPOtlENTS AND PARTS 0 tto. IWA-2500 TO BE FXAHlttEO MFTllOn liest Fxchnngers nnd Steam Generators n6.100 B-C-I Bolts and studs, Mhen removerl. Volumetric and 0 Ul A e Surface K V.

D-G-I Visual 8 0 B6.110 Bolting. 8 Q V

LD MQ B8.30, B-ll Integrally-Melded a t tnchments. Surface 008 8 c)mm B8.40 I '0

&8 ClQ rtM tot7 B3. 9 tt-P Exempted components. Visual {IMA-5000) 00'V.rt m

B 7. 30, BW-2 Bolts studs and nuts. Visual Hg0 V0 B7.40 rt 0 6

I 8 0 Piping Pressure Ttoundary m 8 m Ql Safe-end to pIping velds nnd safe-end In branch Volumetric and 8 B4.1 piping Melds. Surface I

B6.150 BWi-I Bolts and studs, in place. Volumetric O m

B6.160 B-C-I Bolts and studs, vhen removed. Volumetric and Surface tD Visual O B6. 170 BW-I Bo1 t i.ng.

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Tt4.5 Circumferential nnd longItudinn1 pipe zelda. Volumetric

TABI.E ISI 1.1 (Cont'd)

Q COHPONFNTS, PARTS, AND HFTNODS OF FXAHINATION M P

REMA W Ol N 2s KW EXAHINATION HWWH CATFGORY PVKH O<

ITFH TABLE COHPONKNTS AND PARTS H

No. TMB-2SOO TO BE F.XAHINF.D HFTllOD 0 Piping Pressure Boundary B4.6 B-J Branch pipe connection welrIs exceeding six inch Volumetric I diameter. 0 I

Ol m Branch pipe connection welds six inch diameter Surface rt 4V.

B4.7 B-J, K and smaller. O IQ 0

'EOH Q B4.8 Socket welds. Surface 0008 'u otnm

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B10.10 B-K-.1 Integrally welded at tachmen ts. Surface. MS OlU MOrtM

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00 rt jll B11.10 B-K-2 Component supports. Visual u r.rt 0 r.td Mg 0 Visual (IMA-5000) rt W B4.11 B-P Fxempted components.

I8 0 B7.50 BWi-2 Bolts, studs and nuts. Visual g

I vS8 Pump, I Pressure Boundary B6.180 B&-,1 Bolts and studs, in place. Volumetric I

B6.190 B-G-1 Bolts and st,uds, when removed. Volumetric and 1

I Surface B6..200 Bolting. Visual B10.20 B-K-1 Integrally-welded at tachmen ts. Surface I

B11.20 B-K-2 Component supports. Visual

l TABLE ISI 1.1 (Cont'd)

A COHPONFNTS, PARTS, AND HFTNODS OF FXAHINATION H

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W W Ol V EXAHINATION McA V CATEGORY VL ITFM TABLE COMPONENTS AND PARTS AN No. IMB-2500 TO BF. FXAHINED MPTIIOD 0 Pump Pressure Boundary B5.6 8-L-1 Pump casing zelda. Volumetric 0 0) 5 S 85.8 8-P Fxempted components. Visual rt g Wr.

Visual S 0 87.60 BW-2 Bolts, studs, nnd nuts. S A V. W

'LD H5 Reactor Coolant Pump Flywheel. Volumetric and caP 8 Surface otn 5 to WS 0)'t3 mA rtH Valve Pressure Boundary co rt Ql mt-rt P.t5 0

86. 21D 8-C-1 Bolts and studs, in place. Volumetric HQ 0 rt tl S

86.220 8-G-1 Bolts and studs, phen removed. Volumetric and 8 0 Surface 44" RQ 8-a-I Visual 8 86.230 Bolting.

810.30 8-K-1 Integrally veided attachments. Volumetric v

811. 30 8-K-2 Component supports. Visual n 86.6 Valve-body zelda. Volumetric O

86.8. B-P Fxempted components. Visual (IMA-5000) 87.70 BW-2 Bolts, studs, and nuts. Visual

TABLE ISI l.l (Cont'd) A COMPONFNTS, 1'ARTS,- AND HFTIIO1)S OF FXAMTNATION RE U) JQ W P Ul c; W c'g U)c:QV ~

FXAHINATION tB Q ~ M CATEGORY AN ITEM TABLE COMPONFNTS AND PARTS No. IWB-2500 TO BE FXAM1NFD MFTllnD 0

Pressurf,zer C

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86. 60 B-C-1 Bolts nnd studs, in pine. Volumetric 0 v) 8 I 86.70 8-G<<l Bolts and studs, when removed. Volumetric and Surface

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0 8 Q 86.80 BW<<1 Bolting. Visual LO MQ

'u ED Ul Ql 88.20 Integrally-welded attachments. Surface I '0 8-11 &$

QOrtH toU 82.10 8-P Exempted components. Visual (IWA-5000) 00 lt'l mrorts rt Mg 0 87.20 8-G-2 Bolts, studs, and nuts. Visual rt 'u 8

lleat Exchnngers and Steam Generators 8 0 4 ul w Ql 83.1 8-8 Longitudinal and circumferential welds, including Volumetric 9 Tube sheet-to-head or shell welds on the pri-mary side.

83.2 B-D Nozzle-to-head welds and nozzle inswe radiused Volumetric section on the primary side.

83.3 8-F Nozz le-to-sa fe-end we lds. Volumetric and Surface O 86.90 8-C-1 Bolts and studs, in place. Vo lume tr i.c

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TADI.E ISI 1.1 (Cont'd)

COHPONFNTS, PARTS, AND HETIIOI)S OF. FXAHINATION A H

R3; MlO WWM C FXAHI NATION MCX ZCW V

CATFGORY b9W+H ITF.M TADl.F. COHPONENTS AND PARTS O N IWD-2500 H No. TO DF. FXAHINFI) HETNOD 0 Reactor Vessel

86. 40 8-G-I Ligaments between stud holes. Volume tri.c H 0 Vl 86.50 BW-1 8 S Closure flashers, bushi.ngs. Visual rt V.g K

87.10 BW-2 Bolts, studs and nuts. Visual S 0 S Q I

De.lo 8-ll Integrally-welded attachments. 'LQ H Q Surface DON 8 'u C) Ul Ql tu

) '0 81.15 8-N-1 Vessel Interior. Visual HS MU LOO rtH co rt 81.17 8-N-3 Core-support structures. Visual MV rt v.u)

H50 0 Bi.ie Control rod drive housings. Volumetric rt 0 S 8 I 8 0 81.19 Exempted components. Visual (I@A-5000) m 8 v Ql8 Pressurizer 82.1 l.ongitudinal and circumferential welds. Volumetric 82.2 " 8-D Nozzle-to-vessel welrls and nozzle-to-vessel Volumetric rad fused section.

82.3 8-E lfcater penetrat(ons. Visual (IVA-5000) O n.

82.4, 8-F ~ Nozzle-to-safe-end welds. Volumetric and Surface

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TABLE ISI 1.1 Q qVALITY GRDDP h ril&

0Z Z COMPONFNTS, PARTS, AHD METHODS OF EXhlfrNATIDN 0 Ql C 5CW OlCQt RVPH FXAMlINATIDN PL CATEGORY AK W

ITEM TAOl. E CDMPOHFHTS AND PARTS O No. IWO-2500 TO OF. F.XAM I NF.D METI1DD Reactor Vessel H 81.1 Longitudinal and circurafercntial shall zelda in core region.

Volumetric 0 8 I rfr 81.2 Longitudinal and circurmferential teide.in shell Voluraetric I Irl Q

{other than those of Category 8-A and 8-C) end AH r0 I

meridional and circumferential beam Melds in erg 0 bottom head end closure lrend {other tlran those o 'trto rrr ru l

rrl U of Category B-C). r

@70 rrr rt H mrt rrr R rt 81.3 Vessel-to-flange and head-to-flange circumferen- Volumetric ro H5 0ore I ~

tial zelda.

rt 81.4 8-D Primary nozz)e-to-'vessel rrelds and nozzle inside Volumetric I tr tr 0 W

tia1 Meldso j lr ry ') wc ') r )'r Crn .. ~

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v8 rrr 81 ' 8-E Vessel penetrations, including controi rod drive Visual (IWA-5000) nnd instrumentation I

penetrntions.

81.6 Nozzle-to-safe-end Melds. Volumetric and Surface 86.10 . B-C-1 Closure head nuts. Surface C) 86.20 BW-1 Closrrre studs, in place. Vo lume tric co 86.30 BW>>l Closure studs, ~hen removed. Voluraettic and Surface

l; TABI,F. ISI 1.2 Q qUAI.ITY CROIIP B M COMPONFNTS, PARTS, AND III'.TIIODS OF FXAMINATIOII pM3; t083 p8CN ro c!

cacNV ROACH' FXAMI HAT ION CATFCORY N

4 ITF.H TABI.F. COHPONFATS AND PARTS 0 Ho. IWC-2520 TO B I'. I'.X AH IN F.D MF.TIIOD Pressure Ve..sels M

Cl. 1 Circumferential butt velds. Volumetric 0 m 8 e Cl. 2 Nozzle-to-vessle velds. Volumetric rt v.

4 W

ene C3.10 C-C Integrally-velded support attachments. Surface rA P coN 8 'u c4.1o c-n Bolts and studs. Volumetric c)m Ql hl I '6

~e u)A rtH raa c3.20 Component supports. Visual cDrtQI N m r. rt 0 r.ta C3.30 C-E Supports mechanical and hydraulic. Visual &g 0 rt M Piping e 8 8 0

< ul C2.1 C-Fo C-C Circumferential butt velds. Volumetric Rm 8

C2.2 l.ongitudinal veld joints in fittings. Volumetric C2.3 C-F, CW Branch pipe-to-pipe veld joints. Volumetric CJ C4.20 c-n Bolts and studs. Volumetric C>

c3.4O C-E-1 Integrally veldcrl support attacliments. Surface CO Visual

~

C3. 50. C-E-2 Component supports. bD c3.60 Supports mechanical and hyrau I ic. Visual

A M

TABLE ISI 1.2 (Cont'd) MQ U) Ã3 COMPONFHTS, PARTS'HD MFTIIOf)S OF FXAMINATION QWM C MCX 8CN0 FXAMINATION M

O<

CATFC;ORV 0 ITFM TABLE COMPONFHTS AND PARTS No. IWC-2520 TO BE FXAMIHI'.I) MFTIIOD Pumps M 0 IA C3.1 C-F, CW Pump casing zelda. Volumetric 8 8 rt 4 C4.30 C-D Bolts and studs. Volumetric 8 0 8 Q l

C3.20, C<<E-1 Integrally Irelded support attachments. Surface coN 5 'u Ct U) jll I 'd C3.80 C-E-2 ~ Component supports. Visual we AU

'100 ft M aorta rC C3.90 Supports mechanical nnd hydraulic. Visual IO I ~

rt 0 ).W M5 0 Valves rt W S

C4.1 C Fe CW Valve body zelda, Volumetric 440 t

C4.40 C-D Bolts and studs. Volumetric 8 C3.100 C-F.-I Integrally veltded support attachments. Surface U

C3.110 C-E-2 Component supports. Visual )

C3.120 Supports medlanical nnd hyIlrnulic. Visual (Q

tV .

~ 4~

ll