ML18277A297

Third 10-Year Interval Inservice Inspection Program Update, Part 1 of 7

ML18277A297
Person / Time
Site:	Palo Verde
Issue date:	09/21/2018
From:	Dilorenzo M Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML18278A016	List: ML18277A297 ML18277A303 ML18277A310 ML18277A312 ML18277A319 ML18277A321 ML18277A323
References
102-07800-MDD/NTA
Download: ML18277A297 (100)

Text

10 CFR 50.55a Qaps Michael D. DiLorenzo Department Leader Nuclear Regulatory Affairs 102-07800-MDD/NTA September 21, 2018 Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 U. S. Nuclear Regulatory Commission Mail station 7636 ATTN: Document Control Desk Tel 623.393.3495 Washington, DC 20555-0001 Reference 1: Arizona Public Service Company (APS) Letter Number 102-05831, Third Ten-Year Interval Inservice Inspection Program Update and Relief Request 38, dated March 14, 2008 [Agencywide Documents Access and Management System (ADAMS) Accession Number ML080920639]

Reference 2: APS Letter Number 102-06420, Revised Third 10 Year Interval Inservice Inspection Plans, dated October 4, 2011 (ADAMS Accession Number ML11287A014)

Reference 3: APS Letter Number 102-07551, Third 10-Year Interval Inservice Inspection Program Update, dated August 31, 2017 (ADAMS Accession Number ML17248A521)

Reference 4: APS Letter Number 102-07612, Third 10-Year Interval Inservice Inspection Program Update - Unit 1, dated November 14, 2017 (ADAMS Accession Number ML17319A216)

Subject:

Palo Verde Nuclear Generating Station Units 1, 2, and 3 Renewed License Nos. NPF-41, NPF-51, NPF-74 Docket Nos. STN 50-528/529/530 Third 10-Year Interval Inservice Inspection Program Update

Dear Sirs:

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 50.55a(g)(5),

APS is required to update the Palo Verde Nuclear Generating Station (PVNGS) Inservice Inspection (ISI) program once every 120 months. APS submitted the third interval ISI programs for PVNGS Units 1, 2, and 3 in Reference 1, and subsequently submitted the revised programs in References 2, 3, and 4. APS recently revised the PVNGS Units 1, 2, and 3 ISI program documents. These are being submitted pursuant to paragraph IWA-1400(c) of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code and are enclosed for information.

The ISI program complies with the latest edition and addenda of the ASME Section XI Code incorporated by reference in 10 CFR 50.55a 12 months prior to the start of the interval per 10 CFR 50.55a(g)(4)(ii). The 2001 Edition with the 2003 Addenda of ASME Section XI is the Code that is used for the third 10-year interval ISI programs.

A member of the STARS Alliance LLC Callaway

• Diablo Canyon

• Palo Verde

• Wolf Creek

102-07800-MDD/NTA ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Third 10-Year Interval Inservice Inspection Program Update Page 2 At PVNGS, each unit has a separate ISI program that has been implemented prior to its first required examination of the third interval. Notable changes in this revision to each unit's program include the addition of approved Code Cases, additional inspection scope related to installed Fukushima modifications, revised sections to maintain consistency with the updated plant design basis, and various administrative clarifications. The changes have been reviewed, consistent with Code requirement IWA-2110, by the Authorized Nuclear Inservice Inspector (Hartford Steam Boiler, Global Inspection and Engineering Services) and considered satisfactory.

Enclosures 1, 2, and 3 contain the revised third 10-year interval ISI program for PVNGS Units 1, 2, and 3, respectively.

No new commitments are being made in this submittal.

If you have any questions about this submittal, please contact Matthew S. Cox at (623) 393-5753.

Sincerely, Dilorenzo, Michael W signed by Dllorenzo, Michael pj/yQQp O Q\ i^i'i- cn=Dilorenzo, Michael D(Z99838)

\J\L.'y'yODO} Date:2018.09.21 16:04:13-07'00' MDD/NTA : Third Inspection Interval, Inservice Inspection Program Summary Manual, PVNGS Unit 1, 3INT-ISI-1, Revision 7 : Third Inspection Interval, Inservice Inspection Program Summary Manual, PVNGS Unit 2, 3INT-ISI-2, Revision 7 ; Third Inspection Interval, Inservice Inspection Program Summary Manual, PVNGS Unit 3, 3INT-ISI-3, Revision 5 cc: K. M. Kennedy NRC Region IV Regional Administrator M. D. Orenak NRC NRR Project Manager for PVNGS C. A. Peabody NRC Senior Resident Inspector for PVNGS

Enclosure 1 Third Inspection Interval Inservice Inspection Program Summary Manual PVNGS Unit 1 3INT-ISI-1, Revision 7

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.................................................................................................................................. 15 3.12. References..............................................................................................................................................16 4.0 ASME CLASS 1

SUMMARY

...................................................................................................................17 5.0 ASME CLASS 2

SUMMARY

.................................................................................................................. 40 6.0 ASME CLASS 3

SUMMARY

.................................................................................................................. 71 7.0 AUGMENTED

SUMMARY

.................................................................................................................... 78 8.0 REQUESTS FOR RELIEF........................................................................................................................ 89 9.0 BOUNDARY DRAWING LISTING........................................................................................................ 92 10.0 ZONE DRAWINGS..................................................................................................................................94 11.0 TERMS AND DEFINITIONS..................................................................................................................218 2 of 219 3INT-ISI-1, Rev. 7

SUMMARY

OF CHANGES Revision 7 1.0 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].

c. Section 2.2.7 - Updated words to match 10 CFR 50.55a.

2.0 Section 3.0 -

a. Section 3.5 - Added clarification about the actual 3'^'* Interval end date.

b. Section 3.10.1 - Deleted N-666 from Section 3.10.1 and added N-666-1 to Section 3.10.2 [AI18-00786-002, Level 8]. N-534 was removed fi-om 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.

Section 3.10.2 - Deleted N-666 from Section 3.10.1 and added N-666-1 to Section 3.10.2 [AI 18-00786-002, Level 8].

d. Section 3.10.1.3 - Revised reference toN-532-4 toN-532-5 in accordance 73DP-9ZZ17.

e. Section 3.10.2.5 - Updated N-638-4 to N-638-6 [AI 18-00786-002, Level 8].

f. Section 3.12 - Added revision numbers to documents that didnt previously have one listed.

3.0 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 17-12366-011, 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 17-12366-011, Level 8].

c. B6.20 - Changed inspection requirements from 3'* period to 1^ period based on the 3"* Interval Closeout Self-Assessment.

d. B7.70 - Added note regarding Code footnote that exam are limited to when disassembled and one connection among a group.

e. B7.80 - Added 10 CFR 50.55a reference to use 1995 Code; added note bolting set counts.

f B 13.70 - Clarified that exam was performed in 1R20; deleted note to Relief Request 40 since it applies to UT exams (different ASME Item No.).

F1.40B - Corrected population size; clarified note to list total count versus sample size.

F1.40C - Clarified note to list total count versus sample size.

4.0 Section 5.0-

a. C3.20 - Updated population based on removing welded attachment SI-107-H-13-W from Zone 109 [AI 17-14553-001, Level 8].

i. Zone 109 - Removed welded attachment SI-107-H-13-W from Zone 109 [AI 17-14553-001, Level 8].

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.ll - Noted Class 2 DM welds under Zones 58, 59, 82, 83, 85, and 86 [AI 18-01203-003, Level

d. C5.51 - Adjusted 3' period sample based on number of exams completed [AI 17-15035-001, Level 8].

5.0 Section 6.0 -

a. D 1.20 - Updated period inspection requirements based on the 3'* Interval Closeout Self-Assessment; although the total sample size was reduced from the previous program revision, the updated sample size (31) exceeds the Code requirements (245 10% = 25).

6.0 Section 7.0 -

a. B15.215 - Updated N-770 Code Case revision [AI 17-12366-011, Level 8].

b. B4.40 - Updated NDE method; Added notes about exam not being required until 1R25 per Relief Request 55 [AI 18-00987-002, Level 8].

c. Inspection Item B - Added note that more clearly ties Item B exams with B 15.215 exams; added noted that UTs must be encoded [AI 17-12366-011, Level 8].

7.0 Section 8.0 -

a. Added Relief Requests 55 [AI 18-00987-002, Level 8], 56,57 [ACT 4980448], 58, and 59.

8.0 Section 10.0-

a. Zone 20 - Added detailsto weld overlay work orders.

b. Zone 21 - Added details to weld overlayand UV-651 replacement work orders.

c. Zone 22 - Added details to weld overlay workorder.

d. Zone 29 - Added details to weld overlay workorder.

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e. Zone 30- Added details for 1R15 replacement of V-431 and IRl 8 replacements of HV-203 and HV-205.

f. Zone 31 - Added details to weld overlay work orders.

g. Zone 37 - Added details for 1R15 V-433 replacement.

h. Zone 51 - Reformatted information for 1R17 UV-169 replacement.

i. Zone 52 - Reformatted information for 1R17 UV-183 replacement.

j. Zone 55 - Added info and updated weld numbers for 1R16 FAC replacement.

k. Zone 58 - Reformatted Information for 1R17, 1R18, and 1R19 FAC replacements.

l. Zone 60 - Added details for 1R14 V-642 replacement.

m. Zone 62 - Added details for 1R18 Fukushima mod.

n. Zone 63 - Added details for IRl 8 Fukushima mod.

o. Zone 86 - Added a note to weld 75-1 to show that it is a dissimilar metal weld.

p. Zone 90 - Updated outage and added details for 1R15 UV-676 replacement.

q. Zone 93 - Updated outage and added details for 1R15 UV-674 replacement.

r. Zone 109 - Removed the welded attachment SI-107-H-13-W [AI 17-14553-001, Level 8]

s. Zone 111 - Added more information about 1R18 Fukushima modification.

t. Zone 112 - Added more information about 1R18 Fukushima modification.

u. Zone 126 - Reformatted 1R18 Fukushima modification information. Removed weld numbers for tie in welds since they can be found on another zone.

V. Zone 127 - Reformatted IRl8 Fukushima modification information. Removed weld numbers for tie in welds since they can be found on another zone,

w. Zone 128 - Reformatted IRl8 Fukushima modification information.

X. Zone 129 - Reformatted IRl8 Fukushima modification information. Removed weld numbers for tie in welds since they can be found on another zone.

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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 1. 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 EPRI 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, if modification to the BER program is 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 RI-BER piping inspection program.

1. scope definition (defined in the Augmented Summary of the ISI Program Summary Manuals),

2. segment definition (defined in the Augmented Summary of the ISI Program Summary Manuals),

3. failure/damage mechanism assessment (described in 13-NS-C068),

4. consequence evaluation (described in 13-NS-C068),

5. PRA model runs for the RI-BER piping inspection program (described in 13-NS-C069),

6. risk evaluation (described in 13-NS-C069),

7. element and NDE method selection (described in the Augmented Summary of the ISI Program Summary Manuals),

8. change in risk evaluation (described in 13-NS-C069),

9. PRA quality review (described in 70DP-0RA03, Probabilistic Risk Assessment Model Control) and 5 of 219 3INT-ISI-1,Rev.7

10. continual assessment forms as program changes in response to inspection results (described in 70DP-0RA03, Probabilistic Risk Assessment Model Control, and 73DP-9XI03, ASME Section XI Inservice Inspection).

1.4. The information presented is in a form consistent with the 1* and 2"** 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 (7-18-08), 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. 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).

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2.4 If a code required examination was considered to be impractical during the preparation of this document because of plant design, geometiy, 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 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 7 of 219 3INT-ISI-1,Rev. 7

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.

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 imder 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 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 1 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 219 3INT-ISI-1,Rev.7

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 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 1^, 2"'*, and S'"* 10 Year Intervals and corresponding inspection periods are defined below:

First Inspection Interval: 01/28/86 to 07/17/98 Second Inspection Interval: 07/18/98 to 07/17/08 Third Inspection Interval: 07/18/08 to 07/17/18 Period One: 07/18/08 to 11/17/11 Period Two: 11/18/11 to 03/17/15 Period Three: 03/18/15 to 07/17/18*

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 will end May 31,2019, which is within the plus or minus one year interval allowance allowed by lWA-2430(d)(l).

9 of 219 3INT-ISI-1,Rev. 7

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 categoiy 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.

10of219 3INT-ISI-1, Rev. 7

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-532-5 Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000,Section XI, Division 1 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 of219 3INT-ISI-1, Rev. 7

3.10.1.11.N-685 Lighting Requirements for Surface Examination,Section XI, Division 1

3.10.1.12.N-695 Qualification Requirements for Dissimilar Metal Piping Welds,Section XI Division 1 3.10.1.I3.N-700 Alternative Rules for Selection of Classes 1,2, and 3 Vessel Welded Attachments for Examination,Section XI, Division I 3.10.1.14.N-705 Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2 or 3 Vessels and Tanks,Section XI, Division 1

3.10.1.15.N-706-1 Alternative Examination Requirements of Table IWB-2500-1 and Table IWC-2500-1 for PWR Stainless Steel Residual and Regenerative Heat Exchangers,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 ISI Code ofRecord is earlier than Section XI, 2006 Addenda,Footnote 1 shall not be applied.

12 of 219 3lNT-ISl-l,Rev.7

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 ofthis Code Case shall be performed during the next scheduled outage.

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): ifthe 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 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.

N-638-6 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique,Section XI, Division 1 RG 1.147 documents the following condition; Demonstration for ultrasonic examination of the repaired volume is required using representative samples which contain construction type flaws. (Note: the above condition is identical to the condition on the use of Code Case N 638-4, RG 1.147, Rev. 17) 13 of 219 31NT-ISI-1, Rev. 7

3.10.2.5. 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 ofrecordfor the Inservice Inspection Program utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio.

3.10.2.6. 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.

3.10.2.7. N-666-1 Weld Overlay of Class 1,2, and 3 Socket Welded Connections,Section XI, Division 1 RG 1.147 documents the following condition:

A surface examination (magnetic particle or liquid penetrant) must be performed after installation of the weld overlay on Class I and 2 piping socket welds. Fabrication defects, ifdetected, must be dispositioned using the surface examination acceptance criteria of the Construction Code identified in the Repair/Replacement Plan.

(Note: Code Case N-666 was unconditionally approved in Rev. 17, RG 1.147.)

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 14 of 219 3INT-1SI-1, Rev. 7

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.

15 of 219 3INT-IS1-1, Rev. 7

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. EPRI2012 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.

16 of 219 3INT-ISI-1,Rev.7

SECTION 4.0 ASME CLASS 1 EXAMINATION

SUMMARY

17 of 219 3INT-ISI-1, Rev. 7

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-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 N-733 Mitigation of Flaws in Small Nozzles by Mechanical Connection Modification 18 of 219 3INT-ISI-1, Rev. 7

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40 of 219 3INT-ISI-1, Rev. 7

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 41 of 219 3INT-ISI-1,Rev. 7

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SUMMARY

71 of219 3INT-ISI-1, Rev. 7

INDEX EXAM CATEGORY D-A Welded Attachments for Vessels, Piping, Pumps and Valves D-B All Pressure Retaining Components F-A Class 3 Supports 72 of 219 3INT-ISI-1,Rev.7

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78 of 219 3INT-ISI-1, Rev. 7

INDEX EXAM CATEGORY N-722-1 PWR Components Containing Alloy 600/82/182 N-729-4 PWR Reactor Vessel Upper Head N-770-2 PWR Pressure Retaining Dissimilar Metal Piping and Vessel Nozzle Butt Welds containing Alloy 82/182 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 79 of 219 3INT-ISI-1,Rev. 7

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SECTION 8.0 REQUESTS FOR RELIEF 89 of 219 3INT-1SI-1, Rev. 7

RELIEF REQUEST HISTORY - Interval 3 Relief Status Applicability Description 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.Unit 2, Unit 3,3^

CaseN-729-1 For Reactor Pressure Interval or until reactor vessel 41 Vessel Head Inspections head replacement, whichever is first.

10 CFR 50.55a(g)(6)(ii)(D)(3) APPROVED Unit 3 3R14 (2009 Spring 42 Requirement For Demonstrated refueling outage)

Volumetric Leak Path Assessment Extended Reactor Vessel APPROVED Unit 2 extended until 2027, and 44 Unit 3 until 2028 Examinations Ultrasonic Examination in lieu of APPROVED Unit l.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 APPROVED Unit 3, end of 3'" Interval Alternative to Flaw 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' Interval 54 RCP 2A suction nozzle Reactor Vessel Head Volumetric APPROVED Units 1, 2, and 3, 4* Interval 55 Exam Inspection Extension from 10 to 15 Years Extension of 3^ Interval in Unit 2 APPROVED Unit 2 - 3"^ Interval Extension 56 and use of 2013 Edition for Units 1, Units 1,2, and 3-4" Interval 2, and 3 use of 2013 Edition 57 N-729-4 Alternative APPROVED Unit 1, 3^ Interval 90 of 219 3INT-ISI-1,Rev. 7

RELIEF REQUEST HISTORY - Interval 3 Relief Description Status Applicability Request Unit 2 3^ Interval 10 CFR SUBMITTED Unit 2,3^ Interval 58 50.55a(gX5)(iii) Impractical Request 59 Unit 2 Interval B13.50 Relief SUBMITTED Unit 2,3^ Interval 91 of 219 3INT-ISI-1,Rev.7

SECTION 9.0 ISI BOUNDARY DRAWINGS 92 of 219 31NT-ISI-1,Rev.7

BOUNDARY DRAWING INDEX Drawing No. Drawing Title Code Class Ol-M-AFP-001 Auxiliary - Feedwater System 2&3 Ol-M-CHP-001 Chemical and Volume Control System 1 &2 Ol-M-CHP-002 Chemical and Volume Control System 2&3 Ol-M-CHP-003 Chemical and Volume Control System 2 Ol-M-CLP-001 Containment Integrated and Local Leak Rate Test 2 Ol-M-CPP-001 Containment Purge System 2 Ol-M-CTP-001 Condensate Purge System 2 Ol-M-DFP-001 Diesel Fuel Oil & Transfer System 3 Ol-M-DGP-001 Diesel Generator System 3 Ol-M-DWP-002 Demineralized Water System 2 Ol-M-ECP-001 Essential Chilled Water System 3 Ol-M-EWP-001 Essential Cooling Water System 3 Ol-M-FPP-006 Fire Protection System 2 Ol-M-GAP-001 Service Gas Supply System (N2 and H2) 2&3 Ol-N-GRP-001 Gaseous Radwaste System 2 Ol-M-HCP-001 HVAC Containment Building 2 Ol-M-HPP-001 Containment Hydrogen Control 2 Ol-M-IAP-002 Instrument and Service Air System 2 Ol-M-IAP-003 Instrument and Service Air System 2 Ol-M-NCP-002 Nuclear Cooling Water System 3 Ol-M-NCP-003 Nuclear Cooling Water System 2 Ol-M-PCP-001 Fuel Pool Cooling & Cleanup System 2&3 Ol-M-RCP-001 Reactor Coolant System 1 &2 Ol-M-RCP-002 Reactor Coolant System 1&2 Ol-M-RDP-001 Radioactive Waste Drain System 2 Ol-M-SGP-001 Main Steam System 2&3 Ol-M-SGP-002 Main Steam System 2 Ol-M-SIP-001 Safety Injection and Shutdown Cooling System 2 Ol-M-SIP-002 Safety Injection and Shutdown Cooling System 1 &2 Ol-M-SIP-003 Safety Injection and Shutdown Cooling System 2 Ol-M-SPP-001 Essential Spray Pond System 3 Ol-M-SPP-002 Essential Spray Pond System 3 Ol-N-SSP-001 Nuclear Sampling System 2 Ol-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 93 of 219 3INT-ISI-1,Rev.7

SECTION 10.0 ZONE DRAWINGS 94 of 219 3INT-1SI-1, Rev. 7

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 IB 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 lA 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 SGI 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 SGI 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 95 of 219 3INT-ISI-1,Rev.7

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 LPSl Pump Room A Suction 2 Zone 71 LPSl Pump Room A Discharge 2 Zone 72 LPSl Pump A 2 Zone 73 LPSl Pump Room B Suction 2 Zone 74 LPSl Pump Room B Discharge 2 Zone 75 LPSl 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 LPSl Header to Loop 1A 2 Zone 97 Containment LPSl Header to Loop IB 2 Zone 98 Containment LPSl Header to Loop 2A 2 Zone 99 Containment LPSl Header to Loop 2B 2 Zone 100 Containment LPSl Train A Suction 2 Zone 101 Containment LPSl 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 HPSl Pump Room A Discharge 2 Zone 107 HPSl Pump Room B Discharge 2 Zone 108 HPSl Discharge 88 Pipe Chase 2 Zone 109 HPSl Discharge 88 Pipe Chase 2 Zone 110 HPSl Discharge West Wrap 2 Zone 111 HPSl Discharge West Wrap 2 Zone 112 HPSl Discharge East Wrap 2 Zone 113 HPSl Discharge East Wrap 2 Zone 114 Containment HPSl Header Loop 1A & IB 2 Zone 115 Containment HPSl Header Loop 2A & 2B 2 Zone 116 HPSl Pump A 2 Zone 117 HPSl Pump B 2 Zone 118 HPSl Long Term 2 Zone 119 HPSl Long Term 2 Zone 120 Containment Spray A 2 Zone 121 Containment Spray B 2 96 of 219 3INT-ISI-1, Rev. 7

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 97 of 219 3INT-ISI-1, Rev. 7

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