ML17248A526
| ML17248A526 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/30/2017 |
| From: | Cox J Arizona Public Service Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17248A520 | List: |
| References | |
| 102-07551-MDD/MSC 3INT-ISI-3, Rev. 4 | |
| Download: ML17248A526 (210) | |
Text
Enclosure 3 Third Inspection Interval Inservice Inspection Program Summary Manual PVNGS Unit 3 3INT-ISI-3, Revision 4
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?Sr^'^" Cox, Jennifer DtgioHr U^mO by Cm MnoKtr V(206Wa ON: cimCod. Jtnnihr Y(Z06399)
DN: cn=Cox, JenniFer Y[Z06399)
Reason; I prepared this document. Y(Z06399) Weasoo I am ttgnlt^ ter HMie Bannln per Mkcert (Mr 3017.0SJ0174754 OroO Preparer: Date: 201 7.0S.30 17:46:43 -07W Reviewer; Jackson, Keith. Bolf, Boris Digitally signed by Boir, Boris B(Z99978}
DM cnsBolf, Boris B(Z99978)
UZ53519) B(Z99978) Reason: I am approving this document as Acting DL for Tim Gaffney Section Leader: Department Leader: Date: 2017,05.31 12:19:46 07W Hogstrom, Otgiully ttgned by Hogstrom.
Dl lorenzo, Signally signed by Dllorenzo.
Robert ON:cn=Hogitrom.Rol>>rt Robert (YH24S0)
MiChdl Michael D1Z998381 DN:cnsOllorenzo.
CXZ998381 Michael ANII (Concurrence): (^^2450) Regulatory Affairs (Concurrence):D(Z99838) a...:iou.o5ji Boyd, William Digitally signed by Boyd, William R(Z08404)
License Renewal (Concurrence): ^(^08404) DN: cn^Boyd, William R(Z08404)
Date: 2017.06.01 10:15J0-0r00-Commercial Service Date; 01-08-1988 Program No: 3INT-ISI-3 Rev. 4 1 of217 3INT-ISI-3, Rev, 4
- 0. AHE5.61 - Updated Exam Amounts, Inspection Periods, and Remarks based on the implementation of a Risk-Informed BER Program (UFSAR 6.6.1); moved remaining second period exams to third period. (ACT 4424891 was not fully implemented last revision)
- p. AHE5.81 - Moved scope from C5.81 to Section 7.0 (Augmented Summary); updated Exam Amounts, Inspection Periods, and Remarks based on the implementation of a Risk-Informed BER Program (UFSAR 6.6.1); moved remaining second period exams to third period. (ACT 4424891 was not fully implemented last revision)
- q. Flywheel - Added a note stating that exams are due before the end of the interval; deleted extra information that is found in Section 1.0
- 11. Section 8.0 - Reformatted and added all 3"* Interval Relief Requests (ACT 4614532).
- 12. Section 10.0 - Made the following changes:
- a. Changed engineering study and SDOC numbers to represent the numbers in SWMS (not noted in red)
- b. Zone 1 - Noted pad weld repair on BMI nozzle 3 per DMWO 4463878 (ACT 4468971)
- d. Zone 6 - Updated Zone cross-references; added ISO drawing reference
- e. Zone 21- Updated location of 3SI240H015 and 3SI240H016 (ACT 4459488)
- f. Zone 22-Added 3SI193H009
- g. Zone 28 - Updated location of 3RC018H009; updated line sizes
- h. Zone 39 - Updated location of 3SI248H036 (ACT 4459488)
- 1. Zone 51 - UV-169 replacement resulted in two replaced welds (WO 3779483)
- j. Zone 52 - UV-183 replacement resulted in two replaced welds (WO 3779490)
- k. Zone 55 - FAC replacement resulted in seven replaced welds (WO 3596293)
- l. Zones 62 & 63 - Added welds due to Fukushima modification (ACT 4448436)
- m. Zone 79- Moved weld 81-12 closer to V-158 to match 03-P-SIF-0202.
- n. Zone 80 - Updated weld numbers for annubar modification to make them consistent with a historical ISI change document (IPCA 07-003)
- o. Zone 82 - Added 3SI078H005 and its welded attachment
- p. Zone 85 - Added a welded attachment to 3S1123H007
- q. Zone 90 - UV-676 incorrectly Indicated that the valve was weld on the line when it is actually flanged (ACT 4459488)
- r. Zone 93 - UV-674 incorrectly indicated that the valve was weld on the line when it is actually flanged
- s. Zone 101 - Updated location of SI 194H022 (ACT 4459488)
- u. Zone 107 - Corrected weld number in table to indicate socket weld. V426 replacement resulted in two replaced welds (WO 4469753)
V. Zones 111 & 112 - Added welds due to Fukushima modification (ACT 4448436)
- w. Zones 116 & 117 - Added component numbers for discharge head studs; added VTD reference X. Zones 122 through 125 - Added DG U-bolt locations
- y. Zones 126 through 129 - Added welds due to Fukushima modification (ACT 4448436)
- 13. Section 11.0 - Cleaned up the acronyms based on what is in the program manual 6of217 3INT-ISI-3, Rev. 4
1.0
SUMMARY
1.1 This document contains a detailed description of the 3"* 10 Year Interval Inservice Inspection (ISl) 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 NEl 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 ISl Program is utilizing risk informed break exclusion region (RI-BER) methodology (Reference 3.12.5 and 3.12.9) but does not implement risk informed inservice inspection methodology.
The EPRl methodology being implemented has a generic safety evaluation report (SER)
(Reference 3.12.9). 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 50.50, if modification 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 ofretrievable onsite documentation... be maintained by licensees that implement a RI-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. raJ:eva/Ma//on, (13-NS-C069)
- 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).
7 of 217 3INT-ISI-3, Rev. 4
1.4 The information presented is in a form consistent with the 1st and 2nd 10 Year Interval ISI 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 3'^'* 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 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 IWA-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.
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. An enhanced visual examination with a resolution sensitivity to detect a 1-mil wire or crack may be performed in place of an ultrasonic examination. A visual examination with enhanced magnification that has a resolution sensitivity to detect a 1 -mil width wire or crack, utilizing the allowable flaw length in Table IWB-3512-1, ASME Section XI, 2004 Edition with a limiting assumption on the flaw aspect ratio (i.e.,
a/l=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 Appendix 1 Article 1-3000 of ASME Section XI 2001 Edition will be used. In addition, paragraphs 10 CFR 50.55a(b)(2)(xiv, xv and xvi) are required.
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-729-1, N-722-1, and N-770-1 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 required percentages are not met, a request for relief will be prepared and submitted after 8 of 217 3INT-ISI-3, Rev. 4
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-729-1.
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-770-1.
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 industiy 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.
9 of 217 3INT-ISI-3, Rev. 4
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. ISl 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 EQIDs; 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 P' 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.
10 of 217 3INT-ISI-3, Rev. 4
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 toOl-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.
11 of2l7 3INT-ISI-3, Rev. 4
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-4000,1 Wx-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.
12 of 217 31NT-ISI-3, Rev. 4
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-534
^ Alternative Requirements for Pneumatic Pressure Testing,Section XI, Division 1 3.10.1.5. N-537 Location of Ultrasonic Depth-Sizing Flaws,Section XI, Division 1 3.10.1.6. N-566-2 Corrective Action for Leakage Identified at Bolted Connections,Section XI, Division 1 3.10.1.7. N-586-1 Alternative Additional Examination Requirements for Classes 1, 2, and 3 Piping, Components, and Supports,Section XI, Division 1 3.10.1.8. 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 3.10.1.9. N-624 Successive Inspections,Section XI, Division 1 3.10.1.10.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 3.10.1.1 l.N-663 Alternative Requirements for Classes 1 and 2 Surface Examinations,Section XI, Division 1 13of217 3INT-ISI-3, Rev, 4
3.10.1.12.N-666 Weld Overlay of Class 1,2, and 3 Socket Welded Connections,Section XI, Division 1 3.10.1.13.N-685 Lighting Requirements for Surface Examination,Section XI, Division 1
3.10.1.14.N-695 Qualification Requirements for Dissimilar Metal Piping Welds,Section XI Division 1 3.10.1.15.N-700 Alternative Rules for Selection of Classes 1,2, and 3 Vessel Welded Attachments for Examination,Section XI, Division 1 3.10.1.16.N-705 Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2 or 3 Vessels and Tanks,Section XI, Division 1
3.10.1.17.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 3.10.1.18.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 ISI Code ofRecord 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.
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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 ofthe 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 ofthe 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 of the 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.
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 ofaUT examination, licensees may perform a VT-1 examination in accordance with the code ofrecordfor the Inservice 15 of 217 3INT-ISI-3, Rev. 4
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 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.
3.10.3. 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-729-1 Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds 3.10.3.3. N-770-1 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-9XI03, identifies the components scheduled for examination Including successive examinations from prior periods. The examination procedures and a listing of calibration blocks are also identified.
16 of 217 3INT-1SI-3, Rev. 4
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 Vlll 2007 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.
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.
3.12.6. UFSAR 6.6.1, Augmented Inservice Inspection to Protect Against Postulated Piping Failures.
3.12.7. TRM 5.0.500.8, Inservice and Inspection Testing Programs.
3.12.8. ITS 5.5.7, Reactor Coolant Pump Flywheel Inspection Program.
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. MN591-A00001, Degradation Mechanism Evaluation for Class 1, Class 2, and BER Program Piping Welds for Palo Verde Units 1, 2, and 3 17of217 3INT-ISI-3, Rev. 4
SECTION 4.0 ASME CLASS 1 EXAMINATION
SUMMARY
18of217 3INT-ISI-3, Rev. 4
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-O Pressure Retaining Welds in Control Rod Flousings B-P All Pressure Retaining Components B-Q Steam Generator Tubing F-A Class 1 Supports 19 of 217 3INT-ISI-3, Rev. 4
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SUMMARY
69 of 217 3INT-ISI-3, Rev. 4
INDEX EXAM CATEGORY D-A Welded Attachments for Vessels, Piping, Pumps and Valves D-B All Pressure Retaining Components F-A Class 3 Supports 70 of 217 3INT-ISI-3, Rev. 4
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SUMMARY
76 of 217 3INT-ISI-3, Rev. 4
INDEX EXAM CATEGORY N-722-1 PWR Components Containing Alloy 600/82/182 N-729-1 PWR Reactor Vessel Upper Head N-770-1 PWR Pressure Retaining Dissimilar Metal Piping and Vessel Nozzle Butt Welds containing Alloy 82/182 B-J Pressure Retaining Welds in Piping AUGMENTED HIGH ENERGY C-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel Piping AUGMENTED FLYWHEEL NA Reactor Coolant Pump Flywheel Examinations 77 of 217 3INT-ISI-3, Rev. 4
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RELIEF REQUEST HISTORY - Interval 3 Relief Description Status Applicability Request Reactor Head Penetration Repair APPROVED Unit 1, Unit 2, Unit 3: 2"*' and 3'^
18 Intervals Embedded ID Flaw on CEDM and APPROVED Unit 1, Unit 2, Unit 3 2"*' and 3^"
20 Reactor head Vent nozzle Intervals penetrations Embedded OD Flaw on CEDM and APPROVED Unit 1, Unit 2, Unit 3 2" and 3^
21 Reactor head Vent nozzle Intervals penetrations Code Case 1361-2, "Socket Welds, APPROVED Unit 1, Unit 2, Unit 3 for rest of 30 Section III," for pressurizer heater plant life.
sleeves Alternative Repair For Reactor APPROVED Unit 1, Unit 2, Unit 3 2nd, 3rd, 31 Coolant System Hot-Leg Alloy 600 and 4th Intervals Small-Bore Nozzles Alternatives To Temperature APPROVED Unit 3 33 Requirements For A Portion Of The Pressurizer Base Metal 36 Full Structural Weld Metal Overlay APPROVED Unit 1 and Unit 3 3' Interval Similar & Dissimilar Metal Welding APPROVED Unit 1 and Unit 3 for the 2" and 37 GTAW Temper Bead hold time 3^'^ Interval. Unit 2 for the before starting NDE remainder of the 3"* Interval.
Alternative Repair Method For APPROVED Unit 1, SIT 1A only. Approved 39 Safety Injection Tanks until end of operating license (June 1,2025)
Extended Reactor Vessel APPROVED Unit 1 extended until 2016, Unit 40 Examinations to meet PWROG 2 until 2027, and Unit 3 until Program 2028 Use Appendix I Of ASME Code APPROVED Unit l.Unit2, Unit3,3'"
Case N-729-1 For Reactor Pressure Interval or until reactor vessel 41 Vessel Head Inspections head replacement, whichever is first.
10CFR 50.55a(g)(6)(ii)(D)(3) APPROVED Unit3 3R14(2009 Spring 42 Requirement For Demonstrated refueling outage)
Volumetric Leak Path Assessment Extended Reactor Vessel APPROVED Unit 2 extended until 2027, and 44 Examinations Unit 3 until 2028 Ultrasonic Examination in lieu of APPROVED Unit 1. Unit 2, Unit 3, 3'"
48 Radiography for Section III Interval Alternative to Flaw APPROVED Unit 3 prior to U3C18 51 Removal and Characterization in Bottom Mounted Instrumentation Request for Approval of an SUBMITTED Unit 3 through licensed Alternative to Flaw operating life.
52 Removal, Flaw Characterization and Successive Examinations Alternative to Flaw Removal in APPROVED Unit 3 end of3R19 53 RCP 2A suction nozzle Alternative to Flaw Removal in APPROVED Unit 3, end of 3'" Inteval 54 RCP 2A suction nozzle 89 of 217 3INT-ISI-3, Rev. 4
SECTION 9.0 ISI BOUNDARY DRAWINGS 90 of 217 3INT-ISI-3, Rev. 4
BOUNDARY DRAWING INDEX Drawing No. Drawing Title Code Class 03-M-AFP-001 Auxiliary - Feedwater System 2&3 03-M-CHP-001 Chemical and Volume Control System 1&2 03-M-CHP-002 Chemical and Volume Control System 2&3 03-M-CHP-003 Chemical and Volume Control System 2 03-M-CLP-001 Containment Integrated and Local Leak Rate Test 2 03-M-CPP-001 Containment Purge System 2 03-M-CTP-001 Condensate Purge System 2 03-M-DFP-001 Diesel Fuel Oil & Transfer System 3 03-M-DGP-001 Diesel Generator System 3 03-M-DWP-002 Demineralized Water System 2 03-M-ECP-001 Essential Chilled Water System 3 03-M-EWP-001 Essential Cooling Water System 3 03-M-FPP-006 Fire Protection System 2 03-M-GAP-001 Service Gas Supply System (N2 and H2) 2&3 03-N-GRP-001 Gaseous Radwaste System 2 03-M-HCP-001 HVAC Containment Building 2 03-M-HPP-001 Containment Hydrogen Control 2 03-M-1AP-002 Instrument and Service Air System 2 03-M-IAP-003 Instrument and Service Air System 2 03-M-NCP-002 Nuclear Cooling Water System 3 03-M-NCP-003 Nuclear Cooling Water System 2 03-M-PCP-001 Fuel Pool Cooling & Cleanup System 2&3 03-M-RCP-001 Reactor Coolant System 1&2 03-M-RCP-002 Reactor Coolant System 1 &2 03-M-RDP-001 Radioactive Waste Drain System 2 03-M-SGP-001 Main Steam System 2&3 03-M-SGP-002 Main Steam System 2 03-M-SIP-001 Safety Injection and Shutdown Cooling System 2 03-M-SIP-002 Safety Injection and Shutdown Cooling System 1 &2 03-M-SIP-003 Safety Injection and Shutdown Cooling System 2 03-M-SPP-001 Essential Spray Pond System 3 03-M-SPP-002 Essential Spray Pond System 3 03-N-SSP-001 Nuclear Sampling System 2 03-M-WCP-001 Normal Chilled Water System 2 13-M-ZZP-OOl Symbols and Legend N/A 13-M-ZZP-002 Symbols and Legend N/A 91 of 217 3INT-ISI-3, Rev. 4
SECTION 10.0 ZONE DRAWINGS 92 of 217 3INT-ISI-3, Rev. 4
ZONE DRAWING INDEX Drawing No. Drawing Title Code Class Zone 1 Reactor Vessel Zone 2 Closure Head Zone 3 Steam Generator 1 Zone 4 Steam Generator 2 Zone 5 Pressurizer Zone 6 RCS Primary Piping Zone 16 Reactor Coolant Pump 1A Zone 17 Reactor Coolant Pump IB Zone 18 Reactor Coolant Pump 2A Zone 19 Reactor Coolant Pump 2B Zone 20 Pressurizer Surge Line Zone 21 Shutdown Cooling Loop 1 Zone 22 Shutdown Cooling Loop 2 Zone 23 Safety Injection lA Zone 24 Safety Injection 1B Zone 25 Safety Injection 2A Zone 26 Safety Injection 2B Zone 27 Pressurizer Spray lA Zone 28 Pressurizer Spray IB Zone 29 Combined Pressurizer Spray Zone 30 Aux. Pressurizer Spray Zone 31 Pressurizer Safeties Zone 32 Drain Line 1A Zone 33 Drain Line IB Zone 34 Drain Line 2A Zone 35 Drain Line 2B Zone 36 Letdown Line Zone 37 Charging Line Zone 38 Drain Line Loop 1 Zone 39 HPSI Long Term Recirc 1 Zone 40 HPSI Long Term Recirc 2 Zone 41 Steam Generator 1 2 Zone 42 Steam Generator 2 2 Zone 43 Main Steam SG1 East 2 Zone 44 Main Steam SGI West 2 Zone 45 Main Steam SG2 East 2 Zone 46 Main Steam SG2 West 2 Zone 47 Main Steam SGI West 2 Zone 48 Main Steam SG 1 East 2 Zone 49 Main Steam SG2 East 2 Zone 50 Main Steam SG2 West 2 Zone 51 Atmospheric Dump No. 1 2 Zone 52 Atmospheric Dump No. 2 2 Zone 53 Steam to Aux Feedwater System 2 Zone 54 Feedwater SG No. 1 2 Zone 55 Feedwater SG No. 2 2 Zone 56 Feedwater SG No. 1 2 Zone 57 Feedwater SG No. 2 2 Zone 58 Aux & Downcomer Feedwater SG 1 2 Zone 59 Aux & Downcomer Feedwater SG 2 2 Zone 60 Downcomer Feedwater SG 1 2 Zone 61 Downcomer Feedwater SG 2 2 Zone 62 Aux Feedwater SG 1 2 Zone 63 Aux Feedwater SG 2 2 93 of 217 3INT-1SI-3, Rev. 4
ZONE DRAWING INDEX (Continued)
Drawing No. Drawing Title Code Class Zone 64 Blowdown SG 1 2 Zone 65 Blowdown SG 2 2 Zone 66 Blowdown SG 1 2 Zone 67 Blowdown SG 2 2 Zone 68 Regenerative Heat Exchanger 2 Zone 69 Letdown Heat Exchanger 2 Zone 70 LPSi Pump Room A Suction 2 Zone 71 LPSl Pump Room A Discharge 2 Zone 72 LPSI Pump A 2 Zone 73 LPSI Pump Room B Suction 2 Zone 74 LPSI Pump Room B Discharge 2 Zone 75 LPSI Pump B 2 Zone 76 Containment Spray Pump Room A Suction 2 Zone 77 Containment Spray Pump Room A Discharge 2 Zone 78 Containment Spray Pump A 2 Zone 79 Containment Spray Pump Room B Suction 2 Zone 80 Containment Spray Pump Room B Discharge 2 Zone 81 Containment Spray Pump B 2 Zone 82 Shutdown Cooling Heat Exchange Room A 2 Zone 83 Shutdown Cooling Heat Exchange Room A 2 Zone 84 Shutdown Cooling Heat Exchanger A 2 Zone 85 Shutdown Cooling Heat Exchanger Room B 2 Zone 86 Shutdown Cooling Heat Exchanger Room B 2 Zone 87 Shutdown Cooling Heat Exchanger B 2 Zone 88 East Wrap 2 Zone 89 East Wrap 2 Zone 90 East Wrap 2 Zone 91 West Wrap 2 Zone 92 West Wrap 2 Zone 93 West Wrap 2 Zone 94 A Train Misc. Pipe Chases & 88' Pipe Tunnel 2 Zone 95 B Train Misc. Pipe Chases & 88' Pipe Tunnel 2 Zone 96 Containment LPSI Header to Loop 1A 2 Zone 97 Containment LPSI Header to Loop IB 2 Zone 98 Containment LPSI Header to Loop 2A 2 Zone 99 Containment LPSI Header to Loop 2B 2 Zone 100 Containment LPSI Train A Suction 2 Zone 101 Containment LPSI Train B Suction 2 Zone 102 SI Pumps Train A Suction 2 Zone 103 Refueling Water Suction Train A 2 Zone 104 SI Pumps Train B Suction 2 Zone 105 Refueling Water Suction Train B 2 Zone 106 HPSI Pump Room A Discharge 2 Zone 107 HPSl Pump Room B Discharge 2 Zone 108 HPSI Discharge 88 Pipe Chase 2 Zone 109 HPSI Discharge 88 Pipe Chase 2 Zone 110 HPSI Discharge West Wrap 2 Zone 111 HPSI Discharge West Wrap 2 Zone 112 HPSI Discharge East Wrap 2 Zone 113 HPSI Discharge East Wrap 2 Zone 114 Containment HPSI Header Loop lA & IB 2 Zone 115 Containment HPSI Header Loop 2A & 2B 2 Zone 116 HPSI Pump A 2 Zone 117 HPSI Pump B 2 Zone 118 HPSI Long Term 2 Zone 119 HPSI Long Term 2 Zone 120 Containment Spray A 2 Zone 121 Containment Spray B 2 94 of 217 3INT-ISI-3, Rev. 4
ZONE DRAWING INDEX (Continued)
Drawing No. Drawing Title Code Class Zone 122 DG A Jacket Water 3 Zone 123 DG A Lube Oil 3 Zone 124 DG B Jacket Water 3 Zone 125 DG B Lube Oil 3 Zone 126 AF Alternate Supply 2 Zone 127 AF Primary 2 Zone 128 RCS Primary Discharge 2 Zone 129 RCS Alternate Discharge 2 95 of 217 3INT-ISI-3, Rev. 4
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SECTION 11.0 TERMS AND DEFINITIONS 216 of 217 3INT-ISI-3, Rev. 4
AHE Augmented High Energy ANII Authorized Nuclear Inservice Inspector APS Arizona Public Service Company, et al ASME American Society of Mechanical Engineers Aux Auxiliary BER 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 Recife Recirculation RFO Refueling Outage RPV Reactor Pressure Vessel RVLMS Reactor Vessel Level Monitoring System SDCHX 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 217 of 217 3INT-ISI-3, Rev. 4