ML17261A562
| ML17261A562 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/24/1987 |
| From: | Anderson C, Lilley M ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17261A561 | List: |
| References | |
| NUDOCS 8707300049 | |
| Download: ML17261A562 (42) | |
Text
R EV. PAGE QUALITY ASSURANCE MANUAL 11 OF GINNA STATION EFFECTIVE DATE>
November 1, 1987 ROCHESTER GAS & ELECTRIC CORPORATION SIGNATURE DATE TITLE: PREPARED BYt APPENDIX B OUAI.ITY 7zdg'/~
Ginna Station ASSURANCE Inservice Inspection Program REVIEW t For the 1980-1989 Interval APPROVED BY:
7/W/gz 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 Snubbers ISI 9.0 Records and Reports ISI 10.0 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 8.1 Safety Related Hydraulic Snubbers 8.2 Safety Related Mechanical Snubbers Attachment A Quality Groups A, B, and C Exemptions 8707~00049 870724 PDR ADOCV, 05000aay PDR,
12 ~ 52 C TITLEs DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection 'Program PAGE GINNA STATION For the 1980-1989 Interval 2 0F 27 INTRODUCTION Appendix B of this Quality Assurance Manual describes Ginna's Inservice Inspection Program for the 120 month inspec-tion 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 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 established.-
The inspection program provides for volumetric examination on all circumferential butt welds situated at design break loca-tions or at discontinuity locations where probable failure could occur. Surveillance of these welds can detect material
I V
QUALITY TITLEi'PPENDIX B DATE ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 3 pf 27 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.
The Inservice Inspection Program for snubbers is developed based on the guidance of Reference 13.
Identification is given in Section 10.0 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.
O. s t
'h I
II N
42 52C TITLE< DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 4 OP 27 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 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 secondinterval for Quality Group A compon'ents.
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'escribe 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 1.
4 O. r5.
TITLER DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 5 OF 27 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 ove'r 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 (greater than 20%) and no significant (greater than 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-1.1 shall be examined to the extent and frequency as required in Table IWB-2500 of Refer-ence l.
)
4
'I
,~ L 4, ~
I lg 'I Il
~ + '
p L'
I I
)I I
~
I I
4 ~
~
)
t P I I
I
)'"
lI
TITLEi DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 6 oF 27 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 interpreta-tion that examination in a leg of all previously defective tubes (greater than 20% detectable wall penetration) and up to a maximum of two hundred previously defect-free tubes (less than 20%
detectable wall penetration) 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.
~ ~
l 4
QUALITY TITLEi
'PPENDIX B DATE ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 7 OF 27
- 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 examination 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 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.
~ I . ~ . ~
4 4 ~
II 1
~'
TITLE) DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MMUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 8 DF 27 4.1.1.5 All indications which produce a response greater than or equal to 100% of the reference level shall be investigated to the extent that the operator can evaluate the shape, identity, and location of all such reflectors 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 sy'tem pressure test. in accordance with IWA-2200 of Reference 11.
Supports and hangers shall be visually inspected in accordance wtih IWD-2600 of Reference l.
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.
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 l. All reportable indi-cations shall be subject to comparison with previous data to aid in its characterization and in determining its origin.
5.2 Quality Group B Components 5.2.1 The evaluation of nondestructive examination re-sults shall be in accordance with Article IWC-3000 of Reference 1. All reportable indications shall be subject to comparison with previous data to aid in its characterization and in determining its origin.
5.3 Quality Group C Components
L TITLE DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 9 DP 27 5.3.1 The evaluation of the visual examination results shall be in accordance with Article IWA-5000 of ll for pressurefor hangers Reference 1 tests.
and supports and Reference 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 accept-able 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 indi'cated by eddy current, shall be repaired by pluggi.'ng.
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 ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 10 DF 27 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'egraded 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'.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 paragra hs:
h \
42 02C TITLE: DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 11 oF 27 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 accord-ance with Reference 12.
ISI 7.0 S stem Pressure Testin 7.1 General Requirements 7.1.1 System pressure test shall be conducted in accord-ance with Article IWA-5000 of Reference 1
O,S~~S>
4 l
I t I
6 aw r
r II 1
t i
W
TITLE DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice,Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 12 DP 27 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 leak it tested has been opened, the system shall be to the requirements of Article IWB-5000 of Reference 11. Temperature and pressure requirements of Figure 3.1-1, Section 3.1 of Ginna's "Technical Specifications" shall not be exceeded.
7.2.2 At or near the end of each inspection interval, a hydrostatic pressure test shall be performed on the reactor coolant system components. This test shall be conducted in accordance with the require-ments of Article IWB-5000 of Reference 11. Test pressures and temperatures shall be maintained for at least four hours prior to performing the visual examination. Section 3.1 of Ginna's "Technical Specification" shall not be exceeded.
7.3 Quality Group B Components 7.3.1 At or near 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 hours for insulated pipes. During each period, systems or portions of systems not required to operate during normal reactor operation shall be pressure tested in accordance with IWC 5221.
Inservice leakage tests may also be performed on other systems and components which are normally in service once each period.
TITLE DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 Inservice Inspection Program PAGE For the 1980-1989 Interval MANUAL'INNA STATION 13 oP 27 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 Snubbers 8.1 Each snubber listed in Tables 8.1 and 8.2 shall be demonstrated to be operable by performance of the inservice inspection program defined in Technical Specification 4.14.
ISI 9.0 Records and Re orts 9.1 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 10.0 Exem tions 10.1 Quality Groups A, B and C components exemptions are identified in Attachment A to this Appendix.
However, Paragraphs IWB-1220 and IWC-1220 of Reference 1 exempt certain components from exami-nations, where certain conditions are met. These exemptions will be applied to the components listed on Tables ISI-1.1 and 1.2 with the result that only those non-exempt components are listed herein.
H
/K' V
ql p~'
/
i
- 4 t S
'v
42 52C TITLE DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 14 DF 27 REFERENCES American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PVC)Section XI "Rules for Inservice Inspection of Nuclear Power Plant Components", 1974 Edition through Summer 1975 Addenda.
- 2. Code of Federal Regulations, Title 10, Part 50, dated January 1, 1978.
- 3. Nuclear Regulatory Commission, Regulatory Guide 1.26, Revision 1, dated February 1976 "Quality Group Classifi-cations and Standards for Water, Steam, and Radioactive Waste-Containing Components of Nuclear Power Plants".
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, B&PVC, Section XI, 1974 Edition through Summer 1976 Addenda.
- 9. USAS B31 1 0 1967 ~rPower Piping
- 10. ASME, B&PVC, Section Addenda.
III, 1974 Edition through Summer 1975 ASME, B&PVC Section XI, 1977 Edition through Summer 1978 Addenda.
- 12. Nuclear Regulatory Commission, Regulatory Guide 1.14, Revision 1, dated August 1975, "Reactor Coolant Pump Flywheel Integrity".
- 13. Letter dated March 23, 1981 from Darrell G. Eisenhut, Director, Division of Licensing, USNRC, regarding Technical Specification Revisions for Snubber Surveillance.
I
2 S0 ~ Sh I
TABLE ISI 1.1 QUALITY GROUP A COMPONENTS, PARTS, AND METHODS OF EXAHINATION EXAHINATION n<
CATEGORY ITEH TABLE COHPONENTS AND PARTS No. IWB-2500 TO BE EXAMINED METHOD Reactor Vessel B1.1 B-A Longitudinal and circumferential shall welds in Volumetric 0 M core region.
Bl.2 B-B Longitudinal and circurmferential welds in shell Volumetric SAG 8 V.
(other than those of Category B-A and B-C) and meridional and circumferential beam welds in ~Mg C)5 nI 4
bottom head and closure head (other than those O Ul of Category B-C). Mert5 l0 Q nl M B1.3 B-C Vessel-to-flange and head-to-flange circumferen- Volumetric IXI rt rt X In v-v ~
tial welds. MP OO tel Bl.4 B-D Primary nozzle-to-vessel welds and nozzle inside Volumetric tial welds.
B1.5 B-E Vessel penetrations, including control rod drive Visual (IWA-5000) and instrumentatio'n penetrations.
B1 ~ 6 B-F Nozzle-to-safe-end welds. Volumetric and 0 Surface n m
B6.10 B-G-1 Closure head nuts. Surface B6.20 B-G-1 Closure studs, in place. Volumetric 0 co B6.30 B-G-1 Closure studs, when removed. Volumetric and Surface
4 '1 V
TABLE ISI 1.1 (Cont'd)
COMPONENTS, PARTS., AND METHODS OF EXAMINATION EXAMINATION CATEGORY ITEM TABLE COMPONENTS AND PARTS No. IWB-2500 TO BE EXAMINED METHOD w Pj Reactor Vessel B6.40 B-G-1 Ligaments between stud holes. Volumetric B6.50 B"G-1 Closure Washers, bushings. Visual Q N 8 8 B7.10 B-G-2 Bolts, studs and nuts. Visual rt 0 8 0Q B8.10 B-H Integrally-welded attachments. Surface 8 Y.
B1.15 B-N"1 Vessel Interior. Visual c)NQW ON W B-N-3 Core-support structures. Visual MS rt5 B1.17 QAQPN ro rt rt X R Y-Y-B1.18 B-0 Control rod drive housings. Volumetric 00%
B1.19 B-F Exempted components. Visual (IWA-5000)
S 8 Pressurizer B2.1 B-B Longitudinal and circumferential welds. Volumetric B2.2 B-D Nozzle-to-vessel welds and nozzle-to-vessel Volumetric radiused section. O B2.3 B-E Heater penetrations. Visual '(IWA-5000)
B2.4 B-F Nozzle-to-safe-end welds. Volumetric and Surface CO
TABLE ISI 1.1 (Cont'd)
COMPON NTS, PARTS, AND METHODS OF EXAMINATION EXAMINATION CATEGORY ITEM TABLE COMPONENTS AND PARTS No. IWB-2500 TO BE EXAMINED METHOD 0 Pressurizer B6.60 B-G-l Bolts and studs, in place. Volumetric O M B6.70 B-G-l Bolts and studs, when removed. Volumetric and 8 S Surface g V.
SAQ B6.80 B-G-1 Bolting. Visual S Y.
Q) Mg B8.20 B-H Integra ly-welded attachments. Surface C>NQ W O Ul B2.10 B-P Exempt d components. Visual (IWA-5000) MSrt5
&OP M 00 rt rt Q B7.20 B-G-2 Bolts, studs, and nuts. Visual OO%
M Q Heat Exchangers and Steam Generators S 8 B3.1 B-B Longitudinal and circumferential welds', including Volumetric Tube sheet-to-head or shell welds on the pri-mary side.
B3.2 B-D Nozzle-to-head welds and nozzle inside radiused Volumetric section on the primary side.
B-F Nozzle-to-safe-end welds. m m B3.3 Volumetric and Surface B6.90 B-G-1 Bolts and studs, in place. Volumetric O oo
TABLE ISI 1.1 (Cont'd)
COMPONENTS, PARTS, AND METHODS OF EXAMINATION EXAMINATION CATEGORY ITEM TABLE COMPONENTS AND PARTS 0 No. IWB-2500 TO BE EXAMINED METHOD g Heat Exchangers and Steam Generators B6.100 B"G-1 Bolts and studs, when removed. Volumetric and Surface P N H
r m
8 N B6.110 B-G-1 Bolting. Visual SO&e r-B).30, B-H Integrally-welded attachments. Surface B8.40 ID MQ m5 Q <
ON B3.9 B-P Exempted components. Visual (IWA-5000) MN rt5 u)OWM B7,.30) B-G-2 Bolts, studs, and nuts. Visual cod rtN B7.40 OOW M Q Piping Pressure Boundary rt W 8 8 B4.1 B-F Safe-end to piping welds and safe-end in branch Volumetric and piping welds. Surface B6.150 B-G-1 Bolts and studs, in place. Volumetric B6.160 B-G-1 Bolts and studs, when removed. Volumetric and O Surface m B6.170 B-G-1 Bolting. Visual B-J O B4.5 Circumferential and longitudinal pipe welds. Volumetric n 00
~ ~,
TABI,E ISI 1.1 (Cont'd)
COMPONENTS, PARTS, AND METNODS OF EXAMINATION EXAMINATION CATEGORY PL ITEM TABLE COMPONENTS AND PARTS No. IWB-2500 TO BE EXAMINED METHOD 0 Piping Pressure Boundary B4.6 B"J Branch pipe connection welds exceeding six inch Volumetric diam ter. 0 R B4.7 B-J Branch pipe connection welds six inch diameter Surface and smaller. ~l N0Q B-J Socket. welds. Surface B4.8 J
AH)
C)Q jll W 4
B10.10 B-K-1 Integrally welded attachments. Surface ON M7D t+ 5 B11.10 B-K-2 Component supports. Visual &ASH M rt et R
& t-J V.
~
Visual (IWA-5000) H OOW B4.11 B-P Exempted components. Q B7.50 B-G-2 Bolts, s'uds and nuts. Visual Pump Pressure Boundary t
g B6.180 B-G-1 Bolts and studs, in place. Volumetric B6.190 B-G-1 Bolts and studs, when removed. Volumetric and O Surface m
B6.200 B-G-1 Bolting. Visual I
B10.20 B-K-1 Integrally-welded attachments. Surface O co B11.20 B-K-2 Component supports. Visual
(1 S 1
TABLE ISI 1.1 (Cont'd)
COHPCNENTS, PARTS, AND HETHODS OF EXAHINATION EXAHINATION CATEGORY O ITEH TABLE COHPONENTS AND PARTS pj No. IWB-2500 TO BE EXAHINED HETHOD 0 Pump Pressure Boundary B5.6 B-L-1 Pump casing welds. Volumetric Q Q m B5.8 B-P Exempted components. Visual B7.60 B-G-2 Bolts, studs, and nuts. Visual gr SAG
\
Reactor Coolant Pump Flywheel. Volumetric and 4) M g Surface C)5QM OU) W Valve Pressure Boundary YSrt5 C>0QM B6.210 B-G-1 Bolts and studs, in place. Volumetric e+
C) QQ r-r.
OOW MQ B6.220 B-G-1 Bolts and studs, when removed. Volumetric and Surface B6.230 B-G-1 Bolting. Visual B10.30 - B-K-1 IntegraLly welded attachments. Volumetric Bll.30 B-K-2 Component supports. Visual O B6.6 B-H-1 Valve-body welds.- Volumetric m B6.8 B-P Exempted components. Visual (IWA-5000)
O B7.70 B-G-2 Bolts, studs, and nuts. Visual M
TABLE ISI 1.2
(}UALITY GROUP B COHPONENTS, PARTS, AND METHODS OF EXAMINATION EXAMINATION CATEGORY ITEM TABLE COMPONENTS AND PARTS No. IWC-2520 TO BE EXAMINED METHOD 4
Pressure Vessels C1.1 C-A Circumferential butt welds. Volumetric C1. 2 C-B Nozzle-to-vessle welds. Volumetric C3.10 C-C Integrally-welded support attachments. Surface I
.C4.10 C-D Bolts and studs. Volumetric C3.20 C-E Component supports. Visual C3.30 C-E Support,s mechanical and hydraulic. Visual Piping
.C2. 1 C-F, C-G Circumferential butt welds. Volumetric C2.2 C-F, C-G Longitudinal weld joints in fittings. Volumetric C2.3 C-F) C-G Branch pipe-to-pipe weld joints. Volumetric C4.20 C-D Bolts and studs. Volumetric C3.40 C-E-1 Integrally welded support attachments. Surface C3.50 C-E-2 Component supports. Visual C3.60 Supports mechanical and hyraulic. Visual
~ ~
TABLE ISI 1.2 (Cont'd)
COhPONENTS, PARTS, AND METHODS OF EXAMINATION EXAMINATION CATEGORY H 0 g ITEM TABI.F. COMPONENTS AND PARTS IWC-2520 TO BE EXAMINED METHOD No.
Pumps Volumetric lxj Q C3.1 C-F$ C-G Pump casing welds. ON fa 8 0 C4.30 C-D Bolts and studs. Volumetric WY C3.20 C-E-1 Integrally welded support attachments. Surface SAQ S V-ID Hg C3.80 C-E-2 Component supports. Visual mN a <
O8 C3.90 Supports mechanical and hydraulic. Visual Me
&A rt5 P ~
cortrt C> Y. 8-Q Valves wQ 0 0 C4.1 C-F, C-G Valve body welds. Volumetric rt P4 C4.40 C-D Bolts and studs. Volumetric C3.100 C-E"1 Integra!ly welded support attachments. Surface RI C3.110 C-E-2 Component supports. Visual O
C3.120 Supports mechanical and hydraulic. Visual f
co
\ 42 ~ 5R C
'r Tl i E DATE QUALITY APPENDIX B ASSURANCE Ginna Station, 11/1/87 NANUAL Inservice Inspection Pr'ogram PAGE GINNA STATION For the 1980-1989 Interval 23 oF . 27 Table 8.1 Safet Related H draulic Snubbers Accessible or System Snubber Installed on Inaccessible Snubber No. and Anal sis Line Number SGA-1 "A" Steam Generator I SGA-2 "A" Steam Generator I SGA-3 uA" Steam Generator I SGA-4 "A" Steam Generator I SGA-5 "A" Steam Generator I SGA-6 "A" Steam Generator I SGA-7 "A" Steam Generator I SGA-8 "A" Steam Generator I SGB-1 "B" Steam Generator ~
I SGB-2 "B" Steam Generator I SGB-3 "B" Steam Generator I SGB-4 "B" Steam Generator I SGB-5 "B" Steam Generator I SGB-6 "B" Steam Generator I SGB-7 "B" Steam Generator I SGB-8 "B" Steam Generator I AFW-10 Standby Auxiliary Feedwater A AFW-13 Standby Auxiliary Feedwater'eedwater A AFW-25 Standby Auxiliary A AFW-26 Standby Auxiliary Feedwater A AFW-27 Standby Auxiliary Feedwater A AFW-28 Standby Auxiliary Feedwater A AFW-29 Standby Auxiliary Feedwater A AFW-31 Standby Auxiliary Feedwater A AFU-109 Auxiliary Feedwater - 500 FWU-3 Feedwater 100 A FWU-5 Feedwater 100 I FWU-21 Feedwater - 301 A FWU-44 Feedwater - 300 A N-601 Pressurizer Relief Discharge I N-602 Pressurizer Relief Discharge I N-604 Pressurizer Relief Discharge I N-605 Pressurizer Relief Discharge I N-607 Pressurizer Relief Discharge I N-608 Pressurizer Relief Discharge I N-615 Pressurizer Relief Discharge I N-616 Pressurizer Relief Discharge I MSU-8 Main Steam - 200
42 52C Tl E DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 24 DF 27 Table 8.1 (Continued)
Safet Related H draulic Snubbers Accessible. or System Snubber Installed on Inaccessible Snubber No. and Anal sis Line Number A or I PS-2 Pressurizer PORV Discharge I PS-4 Pressurizer PORV Discharge I PS-5 Pressurizer PORV Discharge I PS-6 Pressurizer PORV Discharge I PS-8 Pressurizer PORV Discharge I PS-9 Pressurizer PORV Discharge I PS-10 Pressurizer PORV Discharge I PS-11 Pressurizer PORV Discharge
42 ~ 52 C TITLE DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 25 oP 27 Table 8.2 Safet Related Mechanical Snubbers Accessible .or System Snubber Installed on Inaccessible Snubber No. and Anal sis Line Number AFU-3 Auxiliary Feedwater - 300 AFU-31 Auxiliary Feedwater - 100 AFU-34 Auxiliary Feedwater - 100 A AFU-52 Auxiliary Feedwater 100
- 200 A AFU-75 Auxiliary Feedwater A AFU-98 Auxiliary Feedwater - 400 A AFU-101 Auxiliary Feedwater - 400 A AFU-103 (East) Auxiliary Feedwater - 400 A AFV-103 (West) Auxiliary Feedwater 400 A AFU-111 Auxiliary Feedwater - 500 A AFU-123 Auxiliary Feedwater - 500 A AFU-124 Auxiliary Feedwater - 500 A BDU-16 Steam Generator Blowdown - 200 CCU-43 Component Cooling - 450 CCU-57 Component Cooling -'00 CCU-71 Component Cooling - 600 CVU-26 Chemical and Volume Control - 730 I CVU-46 Chemical and Volume Control - 300 I CVU-49 Chemical and Volume Control 700 I CVU-80 Chemical and Volume Control - 100 I CVU-103 Chemical and Volume Control - 500 I CVV-104 Chemical and Volume Control - 500 I CVU-186 Chemical and Volume Control - 250 I CVU-345 Chemical and Volume Control - 900 A CVV-351 Chemical and Volume Control 900 A CVU-372 Chemical and Volume Control 1000 A M-8 Feedwater 200 A FWU-12 Feedwater 200 A FWU-15 Feedwater 301 A FWU-17 Feedwater - 301 A FWU-18 Feedwater 301 A FWU-20 Feedwater 301 A FWU-23 Feedwater - 301 A M-24 Feedwater - 301 A FWU-26 (East) Feedwater " 301 A FWU-26 (West) Feedwater 301 A FWU-32 Feedwater - 300 A FWU-38 Feedwater 300 A M-39 Feedwater 300 A FWU-40 Feedwater 300 A
42 ~ 52 C TITLE DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 26 o" 27 Table 8.2 (Continued)
Safet Related Mechanical Snubbers Accessible or System Snubber Installed on Inaccessible Snubber No. and Anal sis Line Number FWV-42 Feedwater - 300 A FWU-47 Feedwater - 300 A FWU-48 Feedwater - 300 A FWU-51 Feedwater - 300 A FWU-52 Feedwater FWV-54 Feedwater - 300 300 A
A FWU-57 Feedwater - 300 A MSU-2 Main Steam 100 I MSU-3 Main Steam 100 .I MSU-7 (Top) Main Steam 200 I MSU-7 (Bottom) Main Steam 200 I MSU-12 Main Steam - 300 A MSU-13 (East) Main Steam 300 A MSU-13 (West) Main Steam 300 A MSU-15 (North) Hain Steam - 300 A MSU-15 (South) Main Steam - 300 A MSU-16 (North) Main Steam 300 A MSU-16 (South) Main Steam - 300 A MSU-18 (North) Hain Steam - 300 A MSU-18 (south) Main Steam - 300 A MSU-19 (North) Main Steam - 300 A MSU-19 (South) Main Steam - 300 A MSU-22 Main Steam 300 A MSU-25 Main Steam - 300 A MSU-26 (Top) Main Steam - 300 A MSU-26 (Bottom) Main Steam - 300 A MSU-27 Main Steam 300 A MSU-29 Main Steam 300 A MSU-31 Main Steam - 300 A MSU-32 Main Steam 300 A MSU-38 Main Steam - 300 A MSU-39 Main Steam - 300 MSU-40 Main Steam - 300 A MSU-44 Main Steam - 300 A MSU-55 Main Steam - 300, A MSU-57 Main Steam - 300 A MSU-58 Main Steam - 300 A MSV-60 Main Steam - 300 A MSU-72 Main Steam 120 A MSV-74 Main Steam 120 A MSU-75 Main Steam 120 A MSV-78 Main Steam 120 A MSU-80 Main Steam 120 A MSU-82 Main Steam 120 A
T E: DATE QUALITY APPENDIX B ASSURANCE Ginna Station 11/1/87 MANUAL Inservice Inspection Program PAGE GINNA STATION For the 1980-1989 Interval 27 oP 27 Table 8.2 (Continued)
Safet Related Mechanical Snubbers Accessible or System Snubber Installed on Inaccessible Snubber No. and Anal sis Line Number MSV-84 (East) Main Steam - 120 A MSU-84 (West' Main Steam - 120 A MSU-85 Main Steam - 120 A RHU-8 Residual Heat Removal 100 I RHU-30 Residual Heat Removal 2500 I RHU-33 Residual Heat Removal 2500 I RHU-36 Residual Heat Removal - 350 A RHU-51 Residual Heat Removal - 400 A RHU-53 Residual Heat Removal 400 . A RHU-61 Residual Heat Removal - 400 RHU-63 (North) Residual Heat Removal - 300 A RHU-63 (South) Residual Heat Removal - 300 A RHU-69 Residual Heat Removal - 300 A RHU-71 (North) Residual Heat Removal - 300 A RHU-71 (South) Residual Heat Removal - 300 A RHU-72 Residual Heat Removal 300 A RHU-75 Residual Heat Removal - 300 A RHU-92 Residual Heat Removal - 300 A RHU-109 Residual Heat Removal - 450 RHU-110 Residual Heat Removal - 450 A RHU-119 Residual Heat Removal - 450 A RHU-123 Residual Heat Removal - 450 A SIU-3 Safety Injection - 100 SIU-47 Safety Injection - 200 SIU-52 Safety Injection - 200 SWU-254 Service Water - 1850 A SWU-308 Service Water - 1400 A SWU-309 Service Water - 1400 A SWU-370 Service'Water - 1500 A
c l.
r,, r