ML18277A319
| ML18277A319 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/21/2018 |
| From: | Arizona Public Service Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18278A016 | List: |
| References | |
| 102-07800-MDD/NTA | |
| Download: ML18277A319 (100) | |
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SECTION 11.0 Terms and Definitions 212 of 213 3INT-ISI-2, Rev. 7
AHE Augmented High Energy ANII Authorized Nuclear Inservice Inspector APS Arizona Public Service Company, et al ASME American Society of Mechanical Engineers Aux Auxiliary HER Break Exclusion Region CE Combustion Engineering CEDM Control Element Drive Mechanism CL Cold Leg CRD Control Rod Drive CSP Containment Spray Pump DWG Drawing HL Hot Leg HPSI High Pressure Safety Injection ICI In Core Instrumentation lEB Inspection and Enforcement Bulletin INPO Institute for Nuclear Power Operations ISI Inservice Inspection LPSI Low Pressure Safety Injection NDE Nondestructive Examination NRC Nuclear Regulatory Commission PZR Pressurizer RCP Reactor Coolant Pump Recirc Recirculation RPV Reactor Pressure Vessel RVLMS Reactor Vessel Level Monitoring System SDCPDC Shutdown Cooling Heat Exchanger SD Shutdown SER (OE) Significant Event Report (NRC) SER (NRC) Safety Evaluation Report SG Steam Generator UFSAR Updated Final Safety Analysis Report 213 of 213 31NT-ISI-2, Rev. 7
Enclosure 3 Third Inspection Interval Inservice Inspection Program Summary Manual PVNGS Unit 3 3INT-ISI-3, Revision 5
PaloVerde o GENERATING STATION 3*^** Inspection Interval Inservice Inspection Program Summary Manual PVNGS Unit 3 Arizona Public Service Company PVNGS PO Box 52034 5801 S. Wintersburg Road Phoenix, AZ 85072-2034 Tonopah, AZ 85354 Cox, Jennifer DigiUtly signed by Cox. Jennifer Ahlstrom, Wiley D>>9nedb,Ahls.ron,,Wiley J(Z99422)
ON: cnsCox, Jennifer Y(Z06399)
Y^206399) Reason: I prepared this document. Reviewer: J(Z99422) DN: cn=Ahlstrom, Wiley J(Z99422)
Preparer: Date:20t8.08i)1 12:41:11-0700 Date: 2018.08.01 13:13:00-0700' Schrecker, Digiutly slated by Schrecker, Kannetfi Kenneth (XZ9998n Ogitiriy signwl by Stmttrni. Kmmn Schrecker, Kenneth D(Z9998l)
Dtt owSctVKter. rteraiMh DUMM1)
R>>n: Im agormlng tNi donmni D(Z99981)
Section Leader: i7<<>>ja oroir Department Leader: D<tr.20ia08O1 17:10:13 *0700 Hogstrom, OigiuHy signed by Hogstrom. Robert (YH24S0)
Robert CYH2450)
DN: cr>>=Hogstrom, Robert Cox, Matthew SO0S6MJ 2SS:7~"'
ANII (Concurrence): (VH2450) *07-00' Date: 2018.0801 1S2809 Regulatory Affairs (Concurrence): CM cn-Cn MiBhw SiaSM<<
o<<r>>iao>>eii iMoarw Digitally signed by Boyd.
Boyd,William',niL R(Z08404)
License Renewal (Concurrence): 00-Commercial Service Date: 01-08-1988 Program No: 3INT-ISI-3 Rev. 5 1 of 216 3INT-ISI-3, Rev. 5
TABLE OF CONTENTS Contents
SUMMARY
OF CHANGES.................................................................................................................................... 3 1.0
SUMMARY
................................................................................................................................................5 2.0 CODE APPLICABILITY............................................................................................................................ 6
3.0 DESCRIPTION
...........................................................................................................................................7 3.1. Scope...................................................................................................................................................... 7 3.2. System Boundaries.................................................................................................................................. 8 3.3. Accessibility............................................................................................................................................8 3.4. Examination Techniques......................................................................................................................... 9 3.5. Inspection Intervals................................................................................................................................. 9 3.6. Examination Categories.........................................................................................................................10 3.7. Evaluation and Repair............................................................................................................................10 3.8. System Pressure Tests............................................................................................................................10 3.9. Exemptions............................................................................................................................................ 10 3.10. Code Cases............................................................................................................................................ 11 3.11. Outage Plan Table................................................................................................................................. 14 3.12. References............................................................................................................................................. 15 4.0 ASME CLASS 1
SUMMARY
.................................................................................................................. 16 5.0 ASME CLASS 2
SUMMARY
..................................................................................................................39 6.0 ASME CLASS 3
SUMMARY
..................................................................................................................67 7.0 AUGMENTED
SUMMARY
....................................................................................................................74 8.0 REQUESTS FOR RELIEF........................................................................................................................86 9.0 BOUNDARY DRAWING LISTING........................................................................................................ 89 10.0 ZONE DRAWINGS..................................................................................................................................91 11.0 TERMS AND DEFINITIONS................................................................................................................215 2 of 216 3INT-ISI-3, Rev. 5
SUMMARY
OF CHANGES Revision 5
- 1. Section 1.0-
- a. Section 1.3 - Corrected the reference from 10 CFR 50.50 to 10 CFR 50.59 [ACT 4924953].
- 2. Section 2.0 -
- a. Section 2.2.3 - Updated words to match 10 CFR 50.55a.
- b. Section 2.2.4 - Updated words to match 10 CFR 50.55a [82 FR 32934]. The previous regulation words allowed a 1-mil wire. Note that the 1-mil wire was used for previous exams in accordance with 50.55a.
- c. Section 2.2.7 - Updated words to match 10 CFR 50.55a.
- d. Section 2.3 - Updated N-729 and N-770 revisions per 10 CFR 50.55a [AI 17-12366-013, Level 8].
- 3. Section 3.0-
- a. Section 3.1.2.2 - Updated N-729 revision per 10 CFR 50.55a [AI 17-12366-013, Level 8].
- b. Section 3.1.2.3 - Updated N-770 revision per 10 CFR 50.55a [AI 17-12366-013, Level 8].
- c. Section 3.5 - Added clarification about the actual 3^* Interval end date.
- d. Section 3.10.1 - N-534 was removed from the program. This Code Case is applicable to the Pressure Test Program, not the ISI Program, and thus, has not been used this interval by the ISI Program.
- e. Section 3.10.3.2 - Updated N-729 revision per 10 CFR 50.55a [AI 17-12366-013, Level 8].
- f. Section 3.10.3.3 - Updated N-770 revision per 10 CFR 50.55a [AI 17-12366-013, Level 8].
- g. Section 3.12- Added revision numbers to documents that didnt previously have one listed.
- 4. Section 4.0 -
- a. B3.120 - Updated NDE method and clarified note allowing VT in lieu of UT based on 10 CFR 50.55a(b)(2(xxi)(A) [AI 17-12366-013, Level 8].
- b. B3.140 - Updated NDE method and clarified note allowing VT in lieu of UT based on 10 CFR 50.55a(b)(2(xxi)(A) [AI 17-12366-013, Level 8].
- c. B7.70 - Corrected note reference from pump to valve.
- d. B9.21 - Updated f and 3'^ period sample sizes based on 3"* Interval Closeout Self-Assessment.
- e. B9.22 - Updated 3'"* period sample size based on 3** Interval Closeout Self-Assessment.
- f. B13.50 - Removed erroneous reference to Relief Request 44 [AI 18-00825-007, Level 3].
- g. B13.60 & B13.70 - Updated sample size based on Relief Request 44.
- h. Item B-O - Updated sample size to reflect 10% of the 32 peripheral welds (3.2, rounded up to 4) times 4 welds per CEDM, which equals 16. However, IWB-2412(b)(1) provides rules for re examination when welds are added during the first period. IWB-2412(b)(1), combined with the B-O allowance to defer till the end of the interval, made it acceptable to inspect only 8 welds during 3'^'* Interval, 3* period.
- i. Item B14.10 - Updated sample size and added reference to IWB-2412(b)(1).
- j. F 1.1 OB - Updated U* and 3'^ period sample sizes based on exams completed and 3 Interval Closeout Self-Assessment.
- k. F1.40B - Updated population size. The field previously listed the sample size. Clarified note to list total count versus sample size.
- l. FI .40C - Updated notes to match format of other notes related to multiple components.
- 5. Section 5.0-
- a. C3.20 - Updated U, 2"*, and 3'^'* period sample sizes based on exam completion and on the 3*
Interval Closeout Self-Assessment.
- b. C3.30 - Revised sample size based on Code requirements and exams completed per 3'^' Interval Closeout Self-Assessment; revised sample size justification per Footnote 5 of Code.
- c. C5.11 - Noted Class 2 DM welds under Zones 58, 59, 82, 83, 85, and 86 [AI 18-01203-005, Level 3].
- d. C5.21- Revised sample size based on Code requirements and exams completed per Interval Closeout Self-Assessment.
- e. FI .20B - Revised sample size based on Code requirements and exams completed per 3"** Interval Closeout Self-Assessment.
- 6. Section 6.0 -
- a. D1.20 - Updated total population; updated EC, EW, PC, and SP to reflect correct system counts.
- b. F1.30B - Updated U*, 2", 3^* period samples to reflect Code compliance and actual exam completion.
- 7. Section 7.0 -
- a. Updated index to reflect the correct revisions of N-729 and N-770 [AI I7-I2366-0I3, Level 8].
3 of 216 3INT-ISI-3, Rev. 5
- b. B15.205 - Updated cold leg instrument connection weld identification numbers.
- c. B15.215 - Updated N-770 Code Case revision [AI 17-12366-013, Level 8].
- d. N-729 - Updated N-729 Code Case revision [Al 17-12366-013, Level 8].
- e. B4.40 - Added notes about exam not being required until 3R25 per Relief Request 55 [AI 18-00987-004, Level 8],
- f. N-770 - Updated N-770 Code Case revision [AI 17-12366-013, Level 8],
- g. Inspection Item F - Changed to Item F-1[AI 17-12366-013, Level 8].
- h. Inspection Item B - Added note that more clearly ties Item B exams with B15.215 exams; revised system and line number for weld 14-18; added noted that UTs must be encoded [AI 17-12366-013, Level 8].
- 8. Section 8.0 -
- a. Updated status and applicability of Relief Request 52.
- b. Added Relief Requests 55 [18-00987-004, Level 8] through 59.
- 9. Section 10.0-
- a. Zone 20 - Relocated RC-28-H-1 based on plant walk downs.
- b. Zone 30 - Added info about WOs 4675843 (HV-203 replacement) and 4675857 (HV-205 replacement)
- c. Zone 54 - Added information about WO 4506710 and the welds replaced in 3R19.
- d. Zone 62 - Added more information about 3R18 Fukushima modification.
- e. Zone 63 - Added more information about 3R18 Fukushima modification.
- f. Zone 86 - Added a note to weld 75-1 to show that it is a dissimilar metal weld.
- g. Zone 111 - Added more information about 3R18 Fukushima modification.
- h. Zone 112 - Added more information about 3R18 Fukushima modification.
- i. Zone 113 - Added info about WO 4819939 (UV-616 replacement).
- j. Zone 126 - Added more information about 3R18 Fukushima modification. Removed weld numbers for tie in welds since they can be found on another zone.
- k. Zone 127 - Added more information about 3R18 Fukushima modification. Removed weld numbers for tie in welds since they can be found on another zone.
- l. Zone 128 - Added more information about 3R18 Fukushima modification.
- m. Zone 129 - Added more information about 3R18 Fukushima modification. Removed weld numbers for tie in welds since they can be found on another zone.
4 of 216 3INT-ISI-3, Rev. 5
1.0
SUMMARY
1.1 This document contains a detailed description of the 3"^ 10 Year Interval Inservice Inspection (ISI) Program for Palo Verde Nuclear Generating Station Unit 3. This program conforms to the requirements of 10 CFR 50.55a (g), PVNGS Technical Specifications, and the PVNGS UFSAR. Exceptions that are known as of this document preparation date are included in the Requests for Relief Section 8.0.
1.2 This revision was prepared to the 2001 Edition including the 2003 Addenda of ASME Section XI with the exceptions noted below:
1.2.1 Requests for relief from ASME Section XI requirements are included in Section 8.0. These Relief Requests are prepared in a format similar to that documented in the NEI White Paper Revision 1 dated June 2004, entitled: Standard Format for Requests from Commercial Reactor Licensees Pursuant to 10 CFR 50.55a.
1.2.2 The 2007 Edition thru the 2008 Addenda was utilized for Categories B-L-1, B-M-1, and C-G for pump and body welds requirements. (Ref. Letter 102-06454 and SER dated 09-18-2012.)
1.2.3 For clarification, this Interval 3 program was prepared, as was Interval 1 and 2 programs, utilizing 40 month periods.
1.2.4 To support future ISI Programs, reference to the Reactor Vessel Internals Aging Management Plan was added (Reference 3.12.3).
1.2.5 This program was updated to include MRP-192 examinations of mixing tee locations (Reference 3.12.4).
1.3 The ISI Program is utilizing risk informed break exclusion region (RI-BER) methodology (Reference 3.12.5 and 3.12.8) but does not implement risk informed inservice inspection methodology.
The EPRl methodology being implemented has a generic safety evaluation report (SER)
(Reference 3.12.8). The generic SER lists 10 site-specific requirements. These requirements are listed below, along with how Palo Verde is meeting each requirement:
Consistent with 10 CFR 50.59, ifmodification to the BER program may be made using the 10 CFR 50.59 process, the staff is not requesting any additional submittals... the staff expects the following list of retrievable onsite documentation... be maintained by licensees that implement a Rl-BER piping inspection program.
- 1. scope definition, (ISI Program Document)
- 2. segment definition, (ISI Program Document)
- 3. failure/damage mechanism assessment, (13-NS-C068)
- 4. consequence evaluation, (13-NS-C068)
- 5. PRA model runs for the RI-BER piping inspection program, (13-NS-C069)
- 6. risk evaluation,
- 8. change in risk evaluation, (13-NS-C069)
- 10. continual assessment forms as program changes in response to inspection results (PRA Model Control and 73DP-9XI03).
5 of 216 3INT-ISI-3, Rev. 5
1.4 The information presented is in a form consistent with the 1st and 2nd 10 Year Interval ISl Program, the applicable requirements of Standard Review Plan manual and procedures and the recommendations contained in NRC letter dated July 17, 1981, from Mr. R.L. Tedesco, NRC, to E. E. Van Brunt, Jr., APS, Guidance for Preparing Preservice and Inservice Inspection Programs and Relief Requests - Palo Verde Nuclear Generating Station Units 1, 2 and 3.
2.0 CODE APPLICABILITY 2.1 Based on paragraph 10 CFR 50.55a(b)(2) that was published 12 months prior to the start of the S"** 10 Year Interval (3-18-07), the 2001 Edition including the 2003 Addenda of ASME Section XI was referenced as the Code to utilize for preparation of this program.
2.2 Several exceptions to Section XI are documented in 10 CFR 50.55a; each of these exceptions was utilized during the preparation of this program.
2.2.1 10 CFR 50.55a(b)(2)(xviii)(A), the Level I and II nondestructive examination personnel shall be recertified on a 3 year interval in lieu of the 5 year interval in IWA-2314(a) and IWA-2314(b).
2.2.2 10 CFR 50.55a(b)(2)(xviii)(C), when qualifying VT-3 personnel per lWA-2317, the proficiency of the training must be demonstrated by initial qualification examination and subsequent examinations on a 3 year interval.
2.2.3 10 CFR 50.55a(b)(2)(xix), the 1997 Edition must be used for IWA-2240 alternative examination methods, a combination of methods, or newly developed techniques. The use of IWA-4520(c), allowing the substitution of alternative methods, a combination of methods, or newly developed techniques for the methods specified in the Construction Code, are not approved for use.
2.2.4 10 CFR 50.55a(b)(2)(xxi)(A), Items B3.120 and B3.140 (nozzle inner radius examinations) of the 1998 Edition must be utilized. A visual examination with magnification that has a resolution sensitivity to resolve 0.044 inch (1.1 mm) lower case characters without an ascender or descender (e.g., a, e, n, v), utilizing the allowable flaw length criteria in Table IWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(l)(ii) of this section, with a limiting assumption on the flaw aspect ratio (i.e., a/1 = 0.5),
may be performed instead of an ultrasonic examination.
2.2.5 10 CFR 50.55a(b)(2)(xxi)(B), must utilize the 1995 Edition for examination Item B7.80 per 50.55a [deleted from 10 CFR 50.55a on 12/5/2014]
2.2.6 10 CFR 50.55a(b)(2)(xxii), the provisions contained in IWA-2220 that allow use the ultrasonic examination method as a surface examination is prohibited.
2.2.7 10 CFR 50.55a(b)(2)(xxiv), the use of Appendix VIII and the supplements to Appendix VIII and Article 1-3000 of ASME Section XI of the 2002 Addenda through the 2006 Addenda is prohibited.
2.2.8 10 CFR 50.55a(g)(4)(iii), the surface examination requirements for HPSI systems. Items B9.20, B9.21 and B9.22 are not required to be performed.
2.3 ASME Code Cases N-729-4, N-722-1, and N-770-2 will be implemented with the applicable limitations and modifications as identified in 10 CFR 50.55a(g)(6)(ii)(D), (E), and (F).
2.4 If a code required examination was considered to be impractical during the preparation of this document because of plant design, geometry, accessibility or other conditions, a Request for Relief from that requirement was prepared and included in Section 8.0. If a code required examination is identified to be impractical during the course of an inspection and the code 6 of 216 3INT-ISI-3, Rev. 5
required percentages are not met, a request for relief will be prepared and submitted after each inspection period, and the final interval closeout no later than 12 months after expiration of the Interval.
2.5 This ISI Program implements the ASME Section XI 2001 Edition Appendix VIII (Performance Demonstration for Ultrasonic Examination Systems) in accordance with 10 CFR 50.55a. These examinations are conducted in accordance with the Performance Demonstration Initiative (PDI). The PDI Code Comparison document (Reference 3.12.2) explains the complex relationship of regulatory requirements, ASME requirements, code editions, and the PDI program.
3.0 DESCRIPTION
3.1. Scope 3.1.1. This Inservice Inspection Program Summary includes all applicable nondestructive examinations required by ASME Section XI as identified below:
3.1.1.1. Examination of ASME Class 1, 2, and 3 pressure retaining components and their supports are performed in accordance with TRM 5.0.500.8 (Reference 3.12.7).
3.1.1.2. Items that may generally be included in an Inservice Inspection Program, but are not included are listed in Section 3.1.3.
3.1.2 This program also Includes an augmented section that includes examinations for other items required to be examined as identified below.
3.1.2.1 Examinations of welds in Class 1 components fabricated with Alloy 600/82/182 materials in accordance with 10 CFR 50.55a and Code Case N-722-1.
3.1.2.2 Examination of the Reactor Vessel Closure Head in accordance with 10 CFR 50.55a and Code Case N-729-4.
3.1.2.3 Examination of welds in Class 1 piping and vessel nozzle butt welds fabricated with alloy 82/182 in accordance with 10 CFR 50.55a and Code Case N-770-2.
3.1.2.4 Examination of high energy line piping in accordance with UFSAR 6.6.1 (Reference 3.12.6) 3.1.2.5 Examination of the Reactor Coolant Pump Flywheels in accordance with PVNGS Technical Specifications Section ITS 5.5.7.
3.1.2.6 USNRC Circulars, Information Notices, Bulletins, or Orders 3.1.2.7 INPO or other industry operating experiences 3.1.2.8 Combustion Engineering or Westinghouse bulletins or notices 3.1.2.9 Special examinations to satisfy other commitments or concerns that are based on operating experiences, USNRC. These examinations are scheduled throughout this program and reference the applicable notification documents.
7 of 216 3INT-ISI-3, Rev. 5
3.1.3 Those items that may generally be included in an Inservice Inspection Program, but are not included are identified below:
3.1.3.1 Pressure testing of ASME Class 1,2, and 3 piping will be performed in accordance with the Pressure Testing Program.
3.1.3.2 The inservice examination of steam generator tubing will be performed in accordance with the PVNGS Technical Specifications Section T5.5.9 under the Steam Generator Degradation Management Program.
3.1.3.3 The inservice testing of snubbers will be performed in accordance with 10 CFR 50.55a under the Snubber Program.
3.1.3.4 The Examination Program for the ASME Subsections IWE and IWL will be performed in accordance with 10 CFR 50.55a and the PVNGS Technical Specifications under the IWE and IWL Programs.
3.1.3.5 Repair and replacements are performed under the Repair and Replacement Program (73DP-9ZZ17) 3.2. System Boundaries 3.2.1. A complete set of P&ID drawings indicating the Inservice Inspection boundary are maintained at the PVNGS site. These drawings illustrate the ASME Class 1, 2, and 3 systems; components; and boundaries scheduled for examinations. A referenced listing of these drawings is documented in Section 9.0.
3.2.2. ISI isometric (Zone Drawings) are included in Section 10.0 for ASME Class 1 and 2 components. These drawings are utilized for the planning and scheduling of specific ASME Class 1 and 2 examinations throughout the 10 Year Interval.
These also document the location and number of welds, components, and supports.
3.2.3. ASME Class 3 components that have equipment identification numbers (EQID) can be found on plant isometric drawings. Class 3 components that were supplied as part of a skid do not have EQlDs; these components do have Zone Drawings in Section 10.0.
3.3. Accessibility 3.3.1. The preservice examinations were performed with examination techniques, automated or manual, similar to those planned for use during Inservice Inspections. The examination limitations noted during the preservice examinations were documented in Requests for Relief submitted with the preservice examination program. There has also been a number of additional code limitations noted during the L* and 2""* 10 Year Intervals and Request for Relief submitted. If included in the required 3^ Interval examinations they will again be evaluated and relief requested. Note Section 8.0 identifies all the reliefs submitted during the preparation and implementation of the 3"^ Interval.
3.3.2. All items that are scheduled for examination will be examined to the extent practical. In addition, any code limitations that are noted during the examinations will be documented. If relief is required from any of these examinations, a Request for Relief will be submitted after the relief is discovered and prior to 12 months after the interval ends.
8 of 216 3INT-ISI-3, Rev. 5
3.4. Examination Techniques 3.4.1. The three types of examinations utilized to perform Inservice Inspections, along with the actual nondestructive examination technique, are identified in the legend below:
VT - Visual VT-1 (General Condition)
VT-2 (Leakage)
VT-3 (Mechanical and Structural Condition)
VE (Visual Examination)
S - Surface PT Liquid Penetrant MT Magnetic Particle ET Eddy Current VOL - Volumetric UT Ultrasonic RT Radiography 3.4.2. All the above nondestructive examination techniques will be performed using specific techniques and procedures that are identified in ASME Section XI, or alternative examinations that are demonstrated to be equivalent or superior to those identified. The provision for substitution of these alternative examination methods, combination of methods, or newly developed techniques will utilize the 1997 Addenda for IWA-2240. [10 CFR 50.55a(b)(2)(xix)]
3.5. Inspection Intervals The Inservice Inspection Program was prepared in accordance with Program B of ASME Section XI. The 1st, 2nd, and 3rd 10 Year Intervals and corresponding inspection periods are defined below:
First Inspection Interval: 01-08-88 to 01-10-98 Second Inspection Interval: 01-11-98 to 01-10-08 Third Inspection Interval: 01-11-08 to 01-10-18 Period One: 01-11-08 to 05-10-11 Period Two: 05-11-11 to 09-10-14 Period Three: 09-11-14 to 01-10-18*
It should be noted that the intervals/periods may change to allow for extended outage durations per IWA-2400 of ASME Section XI.
- The third interval, third period ended May 31, 2018, which is within the plus or minus one year interval allowance allowed by IWA-2430(d)(l).
9 of 216 3INT-ISI-3, Rev. 5
3.6. Examination Categories The examination categories of ASME Section XI were utilized to develop this program for all systems, components, and supports. The program summary tables contained in Sections 4.0 and 5.0 are organized by examination category for ASME Class 1 and 2 systems, respectively. For each examination category, these tables identify the system or identification, nondestructive examination method, total number of items, and required examination amount for each inspection period (by ASME item number). For ASME Class 3 systems, the examinations categories are identified in Section 6.0.
3.7. Evaluation and Repair 3.7.1. The evaluation of all examination results will be performed in accordance with ASME Section XI Articles IWx-3000. In addition, all applicable repairs and replacements will be performed in accordance with ASME Section XI Articles IWA-4000. Pressure tests will be performed on welded and mechanical joint repairs or replacements, in accordance with IWA-4000, IWx-5000, and 10 CFR 50.55a. Both the evaluations and repair or replacement will be performed in accordance with the 2001 Edition including the 2003 Addenda of ASME Section XI, or later editions and addenda of ASME Section XI referenced in 10 CFR 50.55a. Later editions and addenda will be documented with the NRC.
3.7.2. It should be noted that a relief was requested (Relief Request 36) to perform repair and replacement of all three PVNGS units to the 2001 Edition including the 2003 Addenda. This request was documented in conjunction with the relief to perform full structural weld metal overlays. (APS letter to the USNRC 102-05641 dated 2-8-2007).
3.7.3. All repairs and replacements will be documented in accordance with the Work Control program, and are maintained at Palo Verde for review.
3.8. System Pressure Tests 3.8.1. ASME Class 1, 2, and 3 components will be pressure tested per the requirements of IWB-5000, IWC-5000 and IWD-5000, in accordance with the Pressure Test Program, except where relief has been requested.
3.8.2. Pressure tests will also be performed on repairs and replacements per ASME Section XI, 10 CFR 50.55a, and the PVNGS Repair and Replacement program.
3.9. Exemptions 3.9.1. The exemption criteria identified in the 2001 Edition including the 2003 Addenda of ASME Section XI was utilized for all ASME Class 1, 2, and 3 components and systems. The only exception is that required by 10 CFR 50.55a for the ASME Class 1 piping exemptions. These are in accordance with the 1989 Edition of ASME XI.
3.9.2. A thorough review of all the systems and components was performed in accordance with the above exemptions and a complete set of color coded Inservice Inspection Exemption drawings was prepared at the beginning of the interval. These generic Interval 3 boundary drawings are available at the PVNGS site for review.
10 of 216 3INT-ISI-3. Rev. 5
3.10. Code Cases 3.10.1. The following Code Cases are accepted for use in Regulatory Guide 1.147 and may be utilized during Interval 3 where applicable:
3.10.1.1. N-460 Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1 3.10.1.2. N-526 Alternative Requirements for Successive Inspections of Class 1 and 2 Vessels,Section XI, Division 1 3.10.1.3. N-532-4 Alternative requirements to repair and replacement documentation 3.10.1.4. N-537 Location of Ultrasonic Depth-Sizing Flaws,Section XI, Division 1 3.10.1.5. N-566-2 Corrective Action for Leakage Identified at Bolted Connections,Section XI, Division 1 3.10.1.6. N-586-1 Alternative Additional Examination Requirements for Classes 1, 2, and 3 Piping, Components, and Supports,Section XI, Division 1 3.10.1.7. N-613-1 Ultrasonic Examination of Penetration Nozzles in Vessels, Examination Category B-D, Item Nos. B3.10 and B3.90, Reactor Nozzle-to-Vessel Welds, Figs. IWB-2500-7(a), (b), and (c).Section XI, Division 1 3.10.1.8. N-624 Successive Inspections,Section XI, Division 1 3.10.1.9. N-652-1 Alternative Requirements to Categorize B-G-1, B-G-2, and C-D Bolting Examination Methods and Selection Criteria,Section XI, Division 1 3.10.1.10.N-663 Alternative Requirements for Classes 1 and 2 Surface Examinations,Section XI, Division 1 11 of 216 3INT-ISI-3, Rev. 5
3.10.1.11.N-666 Weld Overlay of Class 1,2, and 3 Socket Welded Connections,Section XI, Division 1 3.10.1.12.N-685 Lighting Requirements for Surface Examination,Section XI, Division 1
3.10.1.13.N-695 Qualification Requirements for Dissimilar Metal Piping Welds,Section XI Division 1 3.10.1.14.N-700 Alternative Rules for Selection of Classes 1, 2, and 3 Vessel Welded Attachments for Examination,Section XI, Division 1 3.10.1.15.N-705 Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2 or 3 Vessels and Tanks,Section XI, Division 1
3.10.1.16.N-733 Mitigation of Flaws in NPS 2 (DN 50) and Smaller Nozzles and Nozzle Partial Penetration Welds in Vessels and Piping by Use of a Mechanical Connection Modification,Section XI, Division 1 3.10.1.17.N-753 Vision Tests,Section XI, Division 1 3.10.2. The following Code Cases are conditionally accepted for use in Regulatory Guide 1.147 may be utilized with the specified conditions during Interval 3 where applicable:
3.10.2.1. N-508-4 Rotation of Serviced Snubbers and Pressure Retaining Items for the Purpose of Testing,Section XI, Division 1 RG 1.147 documents the following condition:
When Section XI requirements are used to govern the examination and testing ofsnubbers and the ISl Code of Record is earlier than Section XI, 2006 Addenda,Footnote I shall not be applied.
3.10.2.2. N-513-3 Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping RG 1.147 documents the following condition:
The repair or replacement activity temporarily deferred under the provisions of this Code Case shall be performed during the next scheduled outage.
12 of 216 3INT-ISI-3, Rev. 5
3.10.2.3. N-561-2 Alternative Requirements for Wall Thickness Restoration of Class 2 and High Energy Class 3 Carbon Steel Piping,Section XI, Division 1 RG 1.147 documents the following conditions:
(1) Paragraph 5(b) : for repairs performed on a wet surface, the overlay is only acceptable until the next refueling outage.
(2) Paragraph 7(c): if the cause of the degradation has not been determined, the repair is only acceptable until the next refueling outage.
(3) The area where the weld overlay is to be applied must be examined using ultrasonic methods to demonstrate that no crack-like defects exist.
(4) Piping with wall thickness less than the diameter of the electrode shall be depressurized before welding.
3.10.2.4. N-562-2 Alternative Requirements for Wall Thickness Restoration of Class 3 Moderate Energy Carbon Steel Piping,Section XI, Division 1 RG 1.147 documents the following conditions; (1) Paragraph 5(b): for repairs performed on a wet surface, the overlay is only acceptable until the next refueling outage.
(2) Paragraph 7(c): if the cause of the degradation has not been determined, the repair is only acceptable until the next refueling outage.
(3) The area where the weld overlay is to be applied must be examined using ultrasonic methods to demonstrate that no crack-like defects exist.
(4) Piping with wall thickness less than the diameter of the electrode shall be depressurized before welding.
3.10.2.5. N-638-4 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique,Section XI, Division 1 RG 1.147 documents the following conditions:
(1) Demonstration for ultrasonic examination ofthe repaired volume is required using representative samples which contain construction type flaws.
(2) The provisions of 3(e)(2) or 3(e)(3) may only be used when it is impractical to use the interpass temperature measurement methods described in 3(e)(1), such as in situations where the weldment area is inaccessible (e.g., internal bore welding) or when there are extenuating radiological conditions.
13 of 216 3INT-ISI-3, Rev. 5
3.10.2.6. N-648-1 Alternative requirements for inner radius examinations of reactor vessel nozzles RG 1.147 documents the following condition; In lieu ofa UT examination, licensees may perform a VT-1 examination in accordance with the code of recordfor the Inservice Inspection Program utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio.
3.10.2.7. N-661-2 Alternative Requirements for Wall Thickness Restoration of Classes 2 and 3 Carbon Steel Piping for Raw Water Service,Section XI, Division 1 RG 1.147 documents the following conditions:
(1) Paragraph 4(b): for repairs performed on a wet surface, the overlay is only acceptable until the next refueling outage.
(2) Paragraph 7(c): if the cause ofthe degradation has not been determined, the repair is only acceptable until the next refueling outage.
(3) The area where the weld overlay is to be applied must be examined using ultrasonic methods to demonstrate that no crack-like defects exist.
(4) Piping with wall thickness less than the diameter of the electrode shall be depressurized before welding.
3.10.3. The following Code Cases are required to be utilized by 10 CFR 50.55a with additional specified conditions as noted in Section 2.3:
3.10.3.1. N-722-1 Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials 3.10.3.2. N-729-4 Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds 3.10.3.3. N-770-2 Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld filler Material With or Without Application of Listed Mitigation Activities (See Reference 3.12.1) 3.11. Outage Plan Table The outage plan table, controlled by procedure 73DP-9X103, identifies the components scheduled for examination including successive examinations from prior periods. The examination procedures and a listing of calibration blocks are also identified.
14 of 216 3INT-ISI-3, Rev. 5
3.12. References 3.12.1. SDOC NOO1-0604-00903 (Supplier Dwg No. PV23Q405), Design Report for Preemptive Weld Overlay Repairs Pressurizer and Hot Leg Dissimilar Metal Welds Palo Verde Nuclear Generating Station Units 1,2, and 3 For Arizona Public Service, Rev. 1, dated 05/25/2011.
3.12.2. EPRI 2012 Technical Report 1026510, Nondestructive Evaluation: Performance Demonstration Initiative (PDI) Comparisons to ASME Section XI, Appendix VIII2007 Edition with 2008 Addendum, and 10 CFR 50.55a, Year 2011, dated November 2012.
3.12.3. SDOC MN755-A00003, PWR Internals AMP for Palo Verde, Rev. 0, dated May 20,2013.
3.12.4. EPRI 2012 Technical Report 1024994, Materials Reliability Program; Assessment of Residual Heat Removal Mixing Tee Thermal Fatigue in PWR Plants, dated August 2012.
3.12.5. 13-NS-C069, Risk-Informed In-Service Inspection Break Exclusion Region (BER) Weld Selection Impact Assessment, Rev. 1, April 20, 2015.
3.12.6. UFSAR 6.6.1, Augmented Inservice Inspection to Protect Against Postulated Piping Failures, Rev. 19B, dated June 2018.
3.12.7. TRM 5.0.500.8, Inservice and Inspection Testing Programs, Rev. 66, May 15,2018.
3.12.8. ITS 5.5.7, Reactor Coolant Pump Flywheel Inspection Program, Rev. 66, May 15,2018.
3.12.9. EPRI Technical Report 1006937, Extension of the EPRI Risk-Informed Inservice Inspection (RI-ISI) Methodology to Break Exclusion Region (BER) Programs, Rev. 0-A, August 2002.
3.12.10. SDOC MN591-A00001, Degradation Mechanism Evaluation for Class 1, Class 2, and BER Program Piping Welds for Palo Verde Units 1,2, and 3, Rev. 1.
15 of 216 3INT-ISI-3. Rev. 5
SECTION 4.0 ASME CLASS 1 EXAMINATION
SUMMARY
16 of 216 3INT-ISI-3, Rev. 5
INDEX EXAM CATEGORIES B-A Pressure Retaining Welds in Reactor Vessel B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels B-D Full Penetration Welded Nozzles in Vessels B-F Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles B-G-1 Pressure Retaining Bolting, Greater Than 2 Inches in Diameter B-G-2 Pressure Retaining Bolting, 2 Inches and Less in Diameter B-J Pressure Retaining Welds in Piping B-K Welded Attachments for Vessels, Piping, Pumps and Valves B-L-1 & B-M-1 Pressure Retaining Welds in Pump and Valve Bodies B-L-2 & B-M-2 Pump Casings and Valve Bodies B-N-1 Interior of Reactor Vessel B-N-2 Welded Core Support Structures and Interior Attachments to Reactor Vessels B-N-3 Removable Core Support Structures B-0 Pressure Retaining Welds in Control Rod Housings B-P All Pressure Retaining Components B-Q Steam Generator Tubing F-A Class 1 Supports 17 of 216 3INT-ISI-3, Rev. 5
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SECTION 5.0 ASME CLASS 2 EXAMINATION
SUMMARY
39 of 216 3INT-ISI-3, Rev. 5
INDEX EXAM CATEGORY C-A Pressure Retaining Welds in Pressure Vessels C-B Pressure Retaining Nozzle Welds in Vessels C-C Welded Attachments for Vessels, Piping, Pumps, and Valves C-D Pressure Retaining Bolting Greater than 2 Inch in Diameter C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping C-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel Piping C-G Pressure Retaining Welds in Pumps and Valves C-H All Pressure Retaining Components F-A Class 2 Supports 40 of 216 3INT-ISI-3, Rev. 5
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