Text

Rev 0 to Inservice Insp Program Summary Manual
	ML17300A261
Person / Time
Site:	Palo Verde
Issue date:	05/29/1986
From:	Mary Anderson; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	;
Shared Package
ML17300A260	List: ML17300A258; ML17300A261;
References
	ISI-2, TAC-62797, NUDOCS 8607230141
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8607230141 860717 PDR ADOCK 05000529 G

PDR INSERVICE INSPECTION PROGRAM

SUMMARY

MANUAL PALO VERDE NUCLEAR GENERATING STATION ARIZONA PUBLIC SERVICE COMPANY P.

O. Box 52034

Phoenix, Arizona 85072'VNGS 4 Miles South Wintersburg, Arizona 85343 PREPARED BY:

DATE:

REVIEWED BY:

DATE:

APPROVAL BY ENGINEERING MANAGER.

ANII CONCURRENCE:

DATE:

PLANT REVIEW BOARD APPROVAL:

-/

DATE:

COiMRCIAL SERVICE DATE:

8/86"

""'anticipated PROGRAM NO:

ISI-2 REVISION NO: 0

gABLE OF CONTENTS

'PAGE 1.0 Summary

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2.0 Code Applicability..................

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3.0 Descrxption...........................................

1-2 3.1 3.2 3.3 3.4 3

5 3.6 37

. 3.8 3.9 3.10 Scope

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System Boundaries Accessibility...............

Examination Techniques Inspection Intervals Examination Categories Evaluation and. Repair.......

System Pressure Tests Augmented. High Energy Piping Exemptions

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1-3 1-3 1-3 1-3 1-4

.1-4 1-4 1-4 3-5 4.0 ASME Class 1 Examination Summary......................

4-1 5.0 ASME Class 2 Examination Summary.....................

5-1 6.0 ASME Class 3 Examination Summary.......

..6-1 7.0 Augmented High Energy Piping...........................7-1 8.0 9.0.

RHR, ECCS, and CHR Piping.......

Requests for Relief.............

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RECORD OF REVISIONS Pape No Revision No COVER 0

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l-l through 1-5 0

4-1 and 4-2 0

TABLE l-l through 1-10 0

TABL'E 1-12 through 1-16 0

TABLE 1-IWF 0

TABLE 1-RCP

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5-1 and 5-2 0

TABLE 2-1 through 2-7;-::;-,';,;:,!:

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TABLE 3-1 0

TABLE 3-IVF 0

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8-1 TABLE 2-CFR 9-1 through 9-5 10-1 and 10-2 0

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PALO VERDE NUCLEAR GENERATING STATION UNIT XI INSERVICE INSPECTION PROGRAM

SUMMARY

1.0

SUMMARY

This document contains a detailed description of the Xnservice

~ Inspection Program for Palo Verde, Nuclear Generating Station, Unit II.

This program conforms to the requirements of 10CFRSO, Section 50.55a(g) and the PVNGS Technical Specific'ations.

In

addition, the information is presented in a form consistent with applicable requirements of Standard Review Plan Sections 5.2.4 and 6.6, and the recommendations" contained'in NRC'etter'ated July 17,

1981, from Mr. R. L. Tedesco, Assistant Director for Licensing, Division of Licensing; subject:

Guidance for Preparing Preservice and Inservice Inspection Programs and Relief Requests-Palo Verde Nuclear Generating Units 1, 2 and 3.

2.0 CODE APPLICABILITY Based on paragraph 10CFR50, 55a(b)(2) that was published 12 months prior to the scheduled date (12-9-85) of issuance of the operating

license, the 1980 Edition through and including the tinter 1981 Addenda of ASME Section XX was utilized to prepare this program.

In addition, and in accordance with paragraph 10CFR50 55a(b)

(2)(iv)(A), the extent of Class 2 piping welds for the PVNGS Safety Injection System (RHR,

ECCS, and CHR systems) was determined in accordance with the 1974 Edition through and including the Summer 1975 Addenda of ASME Section XI.

This program will be updated for each inspection interval to conform with the requirements of the latest edition and addenda of the ASME Section XI Code referenced in paragraph (b) of 10CFR50, Section 50.55a.

When a code required examination is considered to be impractical, because of plant design or other conditions, a request for relief from that requirement will be prepared and included in the program at the beginning of that inspection interval (Section 9.0), If a code required examination is identified to be impractical during the course of an inspection, a request for relief will be prepared and submitted with the next revision to the program.

1-1

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3.0 DESCRIPTION

3.1 SCOPE 3.1.1 This Inservice Inspection Program Summary includes all applicable nondestructive examinations as required by ASi'1E Section XI and those identified in the PVNGS Tech-nical specifications as identified below:

1.

Examination of ASHE Class 1,2 and 3 pressure retaining components and their supports.

2 ~

Examination of the Reactor Coolant Pump Flywheels in accordance with PVNGS'echnical Specifications Section 3/4.4.9.

3.

Augmented high energy piping examinations in accordance with PVNGS FSAR Section 6.6.8.

Augmented examinations of CHR, RHR, and ECCS piping in accordance with 10CFR50.55a.

5..

Special examinations to satisfy other commitments or concerns that are based on operating experiences, USNRC-Circulars,=-Information.-Notices,,or, Bulletins, Combustion Engineering bulletins, INPO Reports, and etc.

These examinations are scheduled throughout this program and reference the applicable notification documents.

3.1.2 Those items that would generally be included in an Inser-vice Inspection

program, but are not included are indentified below:

1.

The inservice testing of snubbers will be performed in accordance with the PVNGS Technical Specifications Section 3/4.7.9.

Note:

Request for Relief Pl in Section 9.0.

2.

The pump and valve testing program is contained and submitted under a separate cover.

3.2 SYSTEM BOUNDARIES A complete set of Inservice Inspection Boundary drawings was in-cluded in Section 10.0 of the Unit 1 Program submittal (Letter 4ANPP-33266-EEVB/KLi~l dated 8-26-85).

Please refer to these draw-ings for definition of the ASi~jE Class 1,

2 and 3 systems, compo-nents and boundaries scheduled for examinations and pressure testing.

1-2

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3.3 ACCESSIBILITY The preservice examinations were performed with examination tech-

niques, both automated and manual, similar to those planned for use for Inservice Inspection.

The examination limitations noted during the preservice examinations were documented in requests for relief submitted with the preservice examination program.

There have been no additional limitations noted during the formu-lation of this program.

All items that are scheduled for examination will be examined to the extent practical.

In addition, any limitations that are noted during the examinations will be documented in the summary reports that are prepared after each outage.

The three (3) 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 ;.2.(Structural Condition)...

VT 4 (Operability)

S Surface VOL Volumetric PT Liquid Penetrant Iff Magnetic Particle ET Eddy Current UT Ultrasonic RT Radiographic All the above nondestructive examination methods will be performed using specific techniques and procedures that are identified in AS<'iE Section XI, or alternative examinations that are demonstrated to be equivalent or superior 'to those identified.

3.5 INSPECTION INTERVALS The Inservice Inspection Program was prepared in accordance with Program B of ASi~iE Section XI.

The initial 10 year inspection interval and corresponding inspection periods are defined below (from the anticipated commercial service date of 8/31/86):

First Inspection Interval:

8-31-86 to 8-30-96 Period One:

8-31-86 to 12-30-89 Period Two:

12-31-89 to 4-30-93 Period Three:

5-1-93 to 8-31-96 1 3

0

3.6 EXAMINATIONCATEGORIES 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 Section 4.0 and 5.0 are organized by examin" ation category for ASME Class 1 and 2 systems respectively.

For each examination category, these tables identify the sy'tem, line number or serial number, nondestructive examination method, total number of items, the required examination amount for each inspection period, and the running percentage.

For ASME Class 3 systems, the examination categories are identified in Section 6.0.

3.7 EVALUATIONAND REPAIR The evaluation of all examination results will be performed in accordance with ASHE Section XI Articles IWA and IWB-3000:

In addition, all applicable repairs and replacements will be performed in accordance with ASHE Section XI Articles IWA, IWB, IWC, IWD and IWF-4000 and 7000.

Both the evaluation and repair or replacement will be performed in accordance with the 1980 Edition through and including the Winter 1981 Addenda of ASHE Section XI, or later editions and addenda of ASME Section XI referenced in 10CFR50; These will also be summarized in the report prepared after each refueling outage in accordance with ASHE Section XI.

3.8 - SYS'VM.PRESSURE TESTS System pressure tests will be performed in accordance with ASME Section XI and as identified in Sections 4.0, 5.0, and 6.0 for ASHE Class 1,

2 and 3 respectively.

These tables also identify the type of pressure

test, the test frequency, any applicable requests for relief, and references the appropriate ASHE Section XI Article for each of the ASME Code Classes.

3.9 AUGMENTED HIGH ENERGY PIPING Based on the PVNGS FSAR, an augmented examination is required for protection against postulated pipe failures.

This augmented examination program eludes the following high energy piping systems located between the contain ment penetration and the main steam support structure wall:

Main Steam Feedwater Steam Generator Blowdown Downcomer Feedwater The summary tables in Section 7.0 identifies each

system, along with the required examination

amounts, and frequencies.

As shown by this a volumetric examination of all longitudinal and and circumferential weids is scheduled.

These welds will be examined to the maximum extent practi-cal.

Any limitations to the examinations will be included and documented in the summary report prepared in accordance with ASME Section XI after each refueling outage.

1-4

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3. 10 EXPTIONS The exemption criteria identified in the 1980 Edition through and including the Winter 1981 Addenda of ASIDE Section XI was utilized for all ASHE Class 1,

2 and 3 components and systems.

This includes the pVNGS Safety Injection System (RHR,

ECCS, and CHR systems) piping":.and components, even though 10CFR50.55a requires the 1974 Edition through and including the Summer 1975 Addenda be utilized. It was concluded after a detailed review that the exemption criteria identified in the Winter 1981 Addenda w'as more conservative in every case than those identified in the Summer 1975 Addenda, and more examinations would therefore be performed on Safety Injection systems piping and compo-nents.

r E

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 Boundary drawings was prepared.

These

.drawings are maintained at the PVNGS site for review.

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SECTION 4.0 ASHE CLASS I EXAMINATION SK &1ARY 4-1

INDEX TABLE EXAM CATEGORY 1-2 B-A, B-B, Pressure retaining welds in reactor vessel Pressure retaining welds in vessels other than reactor vessels 1-3 B-D, Full penetration welds of nozzles in vessels Inspection Program B

1-4 B-E Pressure retaining partial penetration welds in vessels 1-5 B-F Pressure retaining dissimilar metal welds 1-6 B-G-l, Pressure retaining bolting, greater than 2 in. in diameter 1-7 B-G-2, Pressure retaining bolting, 2 in. and less in diameter 1-8 B-H, Integral attachments for vessels 1-,9 1-10 B-J, B-K-l, Pressure retaining welds in piping Integral attachments for piping, pumps and valves'-12 B-L-1 & B-M-l, B-'L-2 6 B-M-2, Pressure retaining welds in pump casings and valve bodies and Pump casings and valve bodies 1-13 B-N-l, B-N-2, B-N-3, Interior of reactor vessel Integrally welded core support structures and interior attachments to reactor vessels Removable core support structures 1-14 1-15 1-16 B-O, B-P$

B-Q, Pressure retaining welds in control rod housings All pressure retaining components Steam generator tubing 1-IHF F-A, F-B, F-Cs Plate and shell type supports Linear type supports Component standard support 1-RCP N/A, Reactor coolant pump flywheel examinations Reg.

Guide 1.14 4-2

i

PALO VERDE NUCLEAR GENERATING STATION t0 YEAR INTERVALEXAMINATION

SUMMARY

ANPP ASME CLASS 1 1-1 TABLE~

PAGE OF ASME ITEM NO.

8100 ZONEiCOMPONENT OR SYSTEM EXAM (:ATFGORY B-A'RESSURF.

RFTAItl I NG WELDS IN REACTOR VESSEL IDENTIFICATION DESCRIPTION, LINE NO., OR SEAIAI. NO.

NDE METHOD TOTAL.

ITEMS I EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF AEOUESTS 110 111 112 120 121 SHELI WELOS C I RCllthfERENT I AL 1-Reactor Vessel LotIG I TUD I NAL 1-Reactor Vessel HEAD WELOS 0 I IICUMFERFNTI AL Butt Welds Butt Welds None SN 79173 SN 79173 Vo I Vot I

9 II 0

0 3

0 0

9 One Two Three One Two Three 0

0 100 0

0 100 AUTOtlATEO FXAN CORE BARREL RFMOVEO AUTOMATEO EXAI~ COng F. oVOQ 122 tlFIII I) I ONAI l-lteacl.or Vesse I

Bottom Head 2-Closure Itead Butt Wold SN 79173 Butt Wold Stl 79173 Vo I Vo I l.

I I

1 0

0 1

33%

33K 34/,

One Two Three One Two Three 0

0 100 33 66 100 AUTOMATED FxAN coiIE

[IAIIRLI R ~FNO V~F.O EXAMINE Ettr IRr.

ACrESSIBI F IEtjGTH L'XANI NE F.N r IIIF ACCESS I BI.E LEtlGTH 130 SHELL-To-FLANGE WELD 1-Reactor Vessel Butt Wold Stl 79173 Vo I 0

100/%k One Two Three 50 50 100

+EXAM FROM FLANGE NA1'ING SURFACE.

""AUTOMATED EXAtl CORE BARRFL RENOVFD pv419 Orco Acv,3/66

ANPP PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION

SUMMARY

ASME CLASS 1

TABLE PAGE OF ASME ITEM NO.

ZONEiCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENO., OR SERIAL NO.

NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 1IIO 150 151 IIEAO-TO-FLANGE WEI.O 2-ClosIIre llcad RF.PAIR WF.I.I)S nr,I.TI.INF. REI:ION Butt Weld None SN 79173

'lj/oI, S 33%

33%

3I4 One Two Three 33 66 100 PYI19-OTCO Rev. 3/86

0

PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMII'IATION

SUMMARY

ANPP ASME CLASS 1 1-2 TABLE PAGE OF ASME ITEM NO.

B200 ZONEiCOMPONENT OR SYSTEM FXAII CATEGORY B-B PRFSSURE RFTAIttING WEI I)S Itt VESSEI S 01IIER TIIAN REACTOR VESSELS IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.

NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 210 211 212 220 221 222 PRESSURI7ER SHELI-TO IIEAD WELDS CIRCUHFERENTIAL AND I.OtIG I TUO I NAI 5-Pressurizer Shel I

I.o Bottom Head 5-P res sur I ze r Shell to Top Head III:AO WELDS C I RCUHFFREttT I AL t'IERIDIONAL Butt Weld Butt Veld None tlone Hone SN 79373 SH 79373 Vo I Vol 33%%d 33%

34%%d 33'5 33%%d 34%%d One Two Three One Two Three 33 66 100 33 66 100 "1

FOOT Hl H.

OF EACH LONG WELD THAT I,NTER-SFCTS THE SCHEDULED CIRC WELDS WILL BE EXAHINED.

230 231 STEAth GEtlERATORS IIF.AD WF.LOS CI RCUHFFRENT I AL 3-Steam Generator 1

4-Steam Generator 2

Butt Welds Butt Welds Stl 79273-1 Vo I SH 79273-2 Vol 1

12<<k Ono Two Three Ono Two Three 25 50 100 25 50 100

<<<<STAY-CYLINDER EXAIIS

""STAY" CYLINDER EXAHS 232 HERIOIOtlAL 3-Steam Generator 1

Butt Welds SN 79273-1 Vo I One Two Three 66 83 100 4-Steam Generator 2

Butt Wetds SN 79273-2 Vol One Two Three 83 100 PV<>947CO aev, 3i86

i I

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A lV P P PALO VERDE NUCLEAR GENI=RATINGSTATION 10 YEAR INTERVALEXAMII1IATION

SUMMARY

ASME CLASS 1 1-2 TABLE PAGE OF ASME ITEM NO.

ZONEiCOMPONENT OR SYSTEM IDENT'ICATION DESCRIPTION, LINE NO., OR SERtAL NO.

NDE METHOD TOTAL--

ITEMS; EXAMINATION AMOUNT INSPE CTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 2IIO 250 251 252 253 260 TUBESIIEFT TO IIEAD 3-Steam Generator 1

II-Steam Generator 2

HEAT EXCIIAttGERS HEAD HEI.()S CI RCUIIFEREtITIAL HER I D I 0ttAI I.OtIG I IIIDI HAL

-TUBFSIIEET-TO-SIIELL

~OR Ilt~AD vELvS 1 UBESIIEET-TO-SIIELL Butt ldelds Butt 6telds ttone Hono Hone Hone Hone Stt 79273-1 Vo I Stt 79273-2 Vol 1

0 0

1 One Two Three One Two Three 50 50 100 50 100 "STAY-CYLIHDER EXAIlS PV41947 CO Rcv. 3/86

'l 0

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ANPP PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMIIiATION

SUMMARY

ASME CLASS 1 1-3 TABLE PAGE OF ASME ITEM NO.

ZONENCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.

NDE METHOD

TOTAL, ITEMS,-,

EXAMINATI0 N AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS B300 TXAN. GATEGONY 0-O'IILL PENETIIATIOII wEi ns or No7zLEs iN VESSFLS-INSPECTION PROGRAM 8 390 8E 3100 3110 8:

3120 3130 8c 31IIO REACTOR VESSEL II077I.F-To-VFSSFL wr.l.ns ANO N077I.F,INS I I)E RADIUS SECTION 1-Reactor Vessel PRESSURIZER tloZ7LE-To-VESSEL wELns ANn NozzLE ltlsinE RAnlus SECTION 5-P res sur I ze r STFAl'I GENFRATORS NOZZLE-To-VESSEL wt:I.ns ANn tl07ZI E I tISIOE RADIUS SECT ION 3-Steam Generator I

II-Steam Generator 2

Outlets-2 I n I e ts-II Surge-1 Spray-1 Safeties-4 Inlet-1 Out I el.-2 In I et-. 1 Outlet.-2 SN 79173 Stl-79373 SN 79273-1 SN 79273-2 Vo I Vol Vo I Vo I 3

~

2 0

Ilk 2

2 2

One Two 1hree One Two Three One Two Three One Two Three 33 33 100 33 66 100 33 66 100 33 66 100

+AUTOIIATEn EXANS FROM SIIELL SIDE WITII CORE BARREL REMOVEn REQUEST FOR RELIEF

//2 REQUEST FOR RELIEF //2 pvl19-Oleo aev 8/86

ANPP PALO VERDE NUCLEAR GENI"=RATINGSTATION 10 YEAR INTERVALEXAMINATION

SUMMARY

ASME CLASS 1 1-3 TABLE PAGE OF ASME ITEM NO.

ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.

NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS 3150 3160 IIEAT EXCIIANGERS NO7ZLE-TO-VESSEL WELDS AIID N07ZLE INSIDE RADIUS SECTION None None Hone PV419 07CO Aev 3(86

0

PALO VERDE NUCLEAR GENI=RATINGSTATION 10 YEAR INTERVALEXAMINATION

SUMMARY

AMP P ASME CLASS 1 1-4 TABLE PAGE 1

ASME ITEM NO.

8400 410 411 412 ZONEE COMPONENT OR SYSTEM EXAll EAT fGGllY G-E PllfffllGE IlflAl'illllC PARTIAl. PENETRATIOtl WFLOS Itl VESSELS PARTIAL PENETRATION WEI.DS VFSSEI. tlOZZI.ES CntlTROL Rnn nRIVE NOIZLES Reactor Vessel Closnrc Ilead IDENTIFICATION tlone CEBH tlozz I <~~947Co aev. 3T86~~

0

~~ANPP PALO VERDE NUCLEAR GENI=RATING STATION 10 YEAR INTERVALEXAMINATION~~

~~SUMMARY~~
ASME CLASS 1 1-5 TABLE PAGE OF ASME ITEM NO.
ZotlES COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS
EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 8500 FKAH CATEGORY~8-F'RESSURF. BETA I tl I tlG DISSIIIILAR HfTAL WELOS 510 520 530 5>>0 550 560 570 580 REACTOR VESSFL NQtllNAI, PI Pf SIZE ~4 IN.
NOZ7LE TO SAFE EIID BUTT WFLDS tlOtlltlAI. Pl PF. SIZF. <4 Ills NOZZLE TO SAFF.
END BUI'T WFLDS III)77sI,E TO SAFE END SOCKI.:T WFLDS PRFSSIJBI7ER IIOtlltlAL PIPE SIZf 4
III, tilt/7IE 1(l St!Sf fttf SIITT Wft.ltf 20-Snrge 29-Spray<<
31-Safeties (4) tlOtlltlAI. P I PE SI7F. C4 Itl,tl077LE TO SAFf EtlD BUTT WELDS tIOZZLE TO SAFE fND SOCKET WELDS STEAN GENERATOR NOMINAL PI PF. SIZE <<4 IN. NO/7LE TO SAFE END BUTT WELDS tlOHItlAI P I PE S I ZE %4 Ill. tlOZZLE TO SAFE Etll) BUTT WEEDS tlone tlone None Bnt twe I d S 8<<ttwolds Bnttwolds Nono tlone None tlone RC-28-1?"
RC-18->>"
RC-1-6" RC-3-6" BC-5"6" RC-7-6" S, Vo I 6i I
One Two Tl)ree 33 66 100
<l I ti.
0 I SS I HI LAB HF.TAI. BUC I WEI.DS 20- PZB Surge 21-SD Cooling 1
22-SD Cooling 2 23-Safety In,j lA 2h-Safety In.j 10 25-Safety Inj 2A 26-Safety Inj 20 Iti,DISS I tel I.AR t'IETAL BUTT WELDS 27-PZR Spray lA 28-PZR Spray 10 32-Dra in 1A 33-Dra in 10 3II-Drain 2A 36-Letdown 37-Charging" Dl SSlt1II.AB tlETAL SOCKET WELDS None None Hone None Buttweld Buttweld Buttweld Buttweld Buttweld Buttweld Buttweld But twe Id 0<<ttwc Id But twe I d 0<<ttweld Buttweld Buttweld Buttweld None BC-28-12" BC-51-16" BC-68-16" S I-207-III" S I -223-1II" S I-160- Ill" S I -179-1II" RC-62-3" BC-18-3" RC-60-2" RC-58-2" BC-96-2<<
BC-91-2" Cll-5-3" S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S
S S
S S
S S
1 1
1 1
1 11:
1 1
1 1
1 1 '
Three One Two One Two Ttlree 1hree One Two One Two Two Three Two 28 100 6II I TEHS 05. 130 8c 05.1IIO SYStEHS COt4-BltiED FOR PERCENTAGE
<<BT SUPPLE-HEHTAL EXAH FOR TIIEBH*L SLEEVE INTEGRITY (NOTE IEIH 82-09).
pve l947co Rev. 3r86
0 0
PALO VERDE NUCLEAR GENI":RATINGSTATION 10 YEAR INTERVALEXAMIIIATION
~~SUMMARY~~
ANPP ASME CLASS 1 TABLE PAGE 1-6 OF ASME ITEM NO.
ZONEUCOMPONENT OR SYSTEM IDENTIFICATION APaSCI)IPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS 8600 FXAH CATE(iORV B-G-l.
PRESSURF RFTAItlltlG BOL1ING GREATER THAtl P IN.
IN OIAHFTER 610 620 630 640 650 REACTOR VESSEL CLOSURE Hl:AD NUTS 2-Closure Head CLOSURE STUDS III PLACE RFHOVEO 2-Closure Head THREADS IN FLANGE 1-Reactor Vessel CI,OSURE UASIIERS IIIITSIIIUl'S 1-Reactor Vessel Nuts None<<
Studs F lang(.
L I gatling'(I I.s Washers 7.237" x
~~7. 91" 7.380" x 76.37" SN 79173 7.50"x1.27" S~~
S,Vol Vo I VT-1 54 E
L 54 54 54>>
18 18 18 18 18 18 0
0 54 18 18 18 One Two Tt)ree One Two Three One Two Three One Two
'Three 33 66 100 33 66 100 0
0 100 33 66 100 "STUDS WII.L l3E RFHOVED rOR EXAwlttn-TION 660 670 680 PRI'SSUR I 7.F.R l3I)LTS ANI) STllt)S rl AtlGr. SURrACE WHEN S
COtlNECflON DISAS-Sf:tll3l ED
~~SilrS, IIIISIIIUCS ARO UASII EBS None None None PVEE9 Oleo nev 9.'86~~
~~A N>>S>>4 PALO VERDE NUCLEAR GENI=RATING STATION 10 YEAR INTERVALEXAMINATION~~
~~SUMMARY~~
ASME CLASS I 1 "6 TABLE PAGE ASME ITEM NO.
ZONEUCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENOOR SERIAL NO.
NDE METHOD TOTAL ITEMS,'XAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS 690 6100 6110 6120 6130 6140 6150 6 I60 6170 6180 STFAH GFIILRATORS Noi.Ts At(t) sriil)s F IAhtlfil, SIIRFACF WIIFN COtltlF(;T I ntl 0 I SAS-SF( ILII L'0 IIUIS 33USlllliGS AWO WA>>31FIIU III.AT EKCIIAttfSERS 8() L1 S AN I) STUDS rLANGr. s(it(FACE W-EN C()tlttECTION DISAS-SI:(hi)l En IliILS iiUSliiSGS ASO WASIII'.SS P I P I IIG R()I)s ANn sTUns FtIAt(GE. SURFACE~WHEN Cntltlf CT I Otl D I SAS-Sl'tlBI.F.I)
IIUI'S, l3USIIISGS AliO WAStlSRS PUHrS Rol TS ANn STUnS>>>>
16-Reactor Coolant Pump 1A 17-Reactor Coolant Pump 18 18-React.or Coolant Pump 2A 19-Reactor Coolant P>>Imp 28 ttone tto>>>>e tlone ttone tlone None tlone ttone tlone F lang>>) Studs F lang>>. Studs F I a ngi) Studs F langi) Studs 4.33" x 32.87" 4.33" x 32.87" 4 33" x 32.87" t>>.33" x 32.87" Volt>>
Vol" Vol" I
16:
16 5
5 6
5 5
6 5
5 6
5 5
6 One Two Three One Two Three One Two Tt>>ree Ono Two Three 31 62 100 31 62 100 31 62 100 31 62 100 "A SUPPLE-HENTAL VT-1 EXAIC WILL BE PCRFOIIHED 100$
PER REFUELlt(G OUTAGE (SEE IEIN 80-27)
A SUPPLE-HENTAL SURFACE EXAH WILL BE PER-FORHED WIIEtl REMOVED
( SEE IEB 82-02)
>>'Ve>>9 01CO>>>>OV 3480
E PALO VERDE NUCLEAR GENI:RATING STATION 10 YEAR INTERVALEXAMlliATION
~~SUMMARY~~
ANPP ASME CLASS 1 1-6 TABLE PAGE OF ASME ITEM NO.
ZONENCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENO., OR SERIAL NO.
NDE METHOD
TOTAL, ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS 6190 6200 6210 6220 6230 FLAIICE SUIIFACE UIIEN COIIIIIICFIOI( OISSAS-SEtRBLED 16, 17, 10 and 19-Reactor Coolant Pumps 1A, 10,2A tl: 20 NUTS BUSH I ttGS AND WASHERS">>
16-Reactor Coolant Pump lA 17-Reactor Coolant Pump 1 l3 18-Reactor Coolant P<<mp 2A 19-Reactor Coolant Pump 2B VALVES BOLTS AND STUDS FI.Atv:E SIIIIFACE WHEN COtltlECt ION OISA-SSFtll.EO HUTS~BUSHINGS AND WASHERS Flange Surface Nuts 8:
Clamping Ring ttuts 8:
Clamping Ring Nuts 8:
Clamping Ring Nuts 8:
Clamping Ring ttone ttone None CASlttG SN lA - 1255 IB -
1257 2A " 1256 2B - 12j8 Il.528"x 7.203" II 520"x 7.203" II.520>>x 7.203" II 528 "x 7.283" VT"1 VT-1 V1-1 VT-1 VT-1 16 per Pum 16; 16 16 One Two Three One Two Three Onc Two Three One Two 1Iiree One Two Three 31 62 100 31 62 100 31 62 100 31 62 100
>>100'g EXAM WHEN DIS-ASSEIIBLED THERE ARE.
NO BI/SIII NGS IN TIIE PUHP FLANGES kk TIIE CLAHI' NG RlttG WILL BE FXANIttED (THFRE AttE NO WASIIFttS)
0
PALO VERDE NUCLEAR GENI=RATING STATION 10 YEAR INTERVALEXAMIIIATION
~~SUMMARY~~
ANPP ASME CLASS 0 1-7 TABLE PAGE OF II ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OA SEAIALNO.
NDE METHOD TOTAL ITEMS; EXAMINATION AMOUNT INSPECTION PERIOD RUNNING AEMAAKSAND RELIEF AEOUESTS B700 EXAH.
CATFGORY B-G-2 Plt[ SSUIIE ltf:tAIt[ING BOLT I t[Ci P.
I N AN[)
LESS IN OIAHFTE[t 710 720 730 7<<0 750 Rf:ACTOR VFSSEI BOI.TS S7UOS AND NUIT S PRFSSURtZCR B()I.TS STUOS AtID HHITS 5-PZR Hanway STFA[4 GEtlFRATORS BOI.TS STUOS AtiO vivt s 3-Steam Generator 1
Cold Leg and Ilot Leg Hanways 4-Steam Generator 2
Cold Leg and Hot Leg tlanways HEAT EXCHAt(GERS P I PING BOITS STUDS ANO HUTS 31-PZR Safeties 37-Ct[arging Line None Studs 8c tluts Studs IL Nuts Studs 8c tluts None F I aflge Flange Flange Flange Flange 1.5"x14.5"
~~1. 5"xi[I.5" 1.5"x1<<.5" RC-1-6" RC-3-6" RC-5-6" RC-7-6" Cll-5-3" VT-1 VT-1 VT-1 VT-1 VT-1 I~~
<<20
'airs
<<<<0 Pa irs
>>I[0 Pairs i
20 20 20
<<0
<<0 I[0
<<0
<<0
<<0 1
0 0
One Two Throe One Two Three One Two Three One Two Three One Two Three 100 100 100 100 100 100 100 100 100 25 50 100 100 100 100 "SUPPLE-tel;t[TEI) BY SURFACE EXAtlS WHEN REHOVEO (SEE IEB 82-02)
PV41941CO Rev 3(86
f~
PALO VERDE NUCLEAR GENI:"RATINGSTATION 10 YEAR INTERVALEXAMII3IATION
~~SUMMARY~~
ANPP ASME CLASS 1 1-7 TABLE PAGE OF ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO. ~ OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION
~
PERIOD RUNNING REMARKS AND RELIEF REQUESTS 760 770 P (IMPS BOI.TS STUDS AND NUTS 16-Reactor Coolant Pump 1A Seal Cover Bolting 17-Reactor Coolant Pump 10 Sea I Cover Bolting 18-Reactor Coolant Pump 2A Sea I Cover Bolting 19-Reactor Coolant Pump 20 Seal Cover Bolting VAIYES IIOI.'ls STUDS AND NUTS 21-SD Cool ing Loop 1
22-SD Cooling Loop 2 23-Sl Loop lA 2<<-Sl Loop 1B 25-SI Loop 2A Sea I Cover Studs 8c Nuts Sca I Cover Studs 8c Nuts Sea I Cover Studs 8c Nuts Sea I Cover Studs 8c Nuts UV-651 UV"653 UV-65c!
UV-65<<
V-235 UV-63<<
V-237 V-5<<2 V-2>>5 UV-6<<4 V-2>>7 V-5<<3 V-215 UV-61li V-217 V-5<<0 F 5" x ST 27N 1.5" x S.27" 1.5" x 8.27" RC-051-16" SI"2<<0-16" RC-068-16" S I -193-16" S I -207-1<<"
SI-207-l<<N SI-207-14" SI-203-12" SI-223-1<<N S I -223-1<<"
S I -223-1<<"
S I -221-12" S I -160-1<<"
S I -160-1>>"
S I -160" 1<<"
S I -156-12" VT-1 VT-1 VT"1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 16 16 c
16
'6 C
2 c
4 One Two Three One Two Three One Two Three One Two Three One Two Three One Two Three One Two Three One Two Three One Two Three 31 62 100 31 62 100 31 62 100 31 62 100 50 50 100 jc 0 100 100 25 75 100 2 r5 7 c5 100 25 50 100 PVAI9.01CO Aev, 3>66
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANpp ASME CLASS 1 TABLE PAGE 1-7 OF ASME ITEM NO.
ZONEvCOMPONENT OR SYSTEM I DENT IFICATI0 N DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 770 CONTINUFD 26-SI Loop 28 27-PZR Spray Loop 1A 28-PZR Spray Loop 18 29 Combined PZR Spray 31-PZR Safeties 32-Drain Line Loop 1A 33-Dra in Line Loop 18 34-Dra in Line Loop 2A 35-Drain Line Loop 28 36-Letdown Line 37-Charging Line V-225 UV"624 V-227 V-5>>1 V-2<<0 PV-100E V-2>>3 V-2>>1 PV-100F V-2>>2 V-2>>>>
PSV-200 PSV-201 PSV-202 PSV-203 V-334 V-234 V-335 V-235 V-333 V-233 V 332 V-232 UV 515 UV"516 V->>33 PDV-2>>0 S I-179-1>>ff S I -179-1<<ff S I -179-14ff S I-175" 12ff RC-62-3ff RC-62-3ff RC" 16-3ff RC-17-3ff RC-17-3ff RC" 18-3ff RC-18->>ff RC-1-6ff RC-3-6ff RC-5-6ff RC"7-6ff RC-60-2ff RC-60-2ff RC-58-2ff RC-58-2ff RC"96-2ff RC-96-2ff RC-89-2ff RC-89-2ff RC-91-2ff CII-I-2ff CII 5 3ff CII-5-3" VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT"1 VT-1 VT-1 VT-1 VT-1 I
>>I k
I 3'
One Two Three One Two Three One Two Three One Two Three One Two Throe One Two Three One Two Three One Two Three One Two Three One Two Three One Two Three 25 75 100 0
33 100 66 100 0
0 100 25 50 100 100 100 100 0
100 100 0
100 100 0
0 100 0
0 100 50 50 100 pve1941co Aev 3/66
~,
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
AN pp ASME CLASS t 1 "7 TASLE PAGE OF ASME ITEM NO.
770 780 ZONEQCOMPONENT OR SYSTEM CONT I tillED 38-Loop 1 Drain 39-tlPSI Snpply Loop 1
IIO-IIPS I Supp ly l.oop 2 CRD iIOIISitII:S lj[>LlS S I'Ill)S AMO NUTS 2-RVLHS Locations IDENTIFICATION V-215 V-216 V-523 V-522 V-533 V-532 Ha rmon C I amps DESCRIPTION, LINE NO., OR SERIAL NO.
RC-70-2 BC"70-2" S I -2II8-3" S I -2II8-3" SI-199-3" S I "199-3" CEDH 92 CEDING 96 NDE METHOD VT-1 VT-1 VT-1 VT-1
~~TOTAL, ITEMS; 2~~
I EXAMINATION AMOUNT 1
0 1
1 1
0 0
1 1
1 0
1 INSPECTION PERIOD One Two Three One Two Three One Two Three
,One Two Three RUNNING 50 50 100 50 100 100 0
50 100 50 50 100 REMARKS AND RELIEF REQUESTS PV41947CO ASV. 3F66
tt l
I l
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
AN PP ASME CLASS 1 TABLE PAGE 1-8 OF ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTIOH, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL
~~ITEMS, EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 0800 rxntl,raTI c;oi(y II-II.~~
i tl I t (ii(ni-nl in( il="
tent't(1S I OI( Vl!ISI:I.S 810 820 830 8(IO RFA(:TO(t Vt:SSf(,
I tl I I'(>RA( I Y wLI.DFD A( IAC(llll'NI S Pi(ESSIII( I 7ER I tj(EIii(nLiYwr(.OrO A1'ACII!N:t(1 S 5-Pressurizer STFAN GFt(FRATORS It(lECI(nt.(.Y WU.UF,O A1'ACI(NI'tlTS 3-Steam Generator 1
II-Steam Generator 2
IlfAT FXCIInt(GERS I tl I'EGRAI,I.Y Wf.(.OEO ATTACIINEtITS Nono Support Skirt Support Skirt Support Skirt tlono SN 79373 SN 79273-1 SN 79273-2 S or Vol S or Vo I S or Vo I 33%
33%%u
~~3llg, 33/kk 3 It%%~~
33/k One Two Three One Two Three Ono Two Three 33 66 100 33k 100k 66 k "NULTIPLF.
VESSFI,S, EXnt'IINA-TIONS 1'OTAL 100/
SUPPORT SKIRT WELD IN 1
STEAN GEt(ERATOR.
pv41s-Oleo Aev 3/8G
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
4 ASME CLASS 'f 1-9 PAGE OF ASME ITEM NO.
ZONEE COMPONENT OA SYSTEM IDENTIFICATION DESCAIPTION, LINENO. ~ OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD AUNNING REMARKS AND RELIEF REQUESTS 8900 EXAM CnTEGORY B-,le PBFSSIIIIF. BE'I'AltlltlG WELOS IN PIPING 910 911 912 tIONINAL PI PF. SIZE&I I ti.
ci I RCIIIII'FnFIITI AL ANO "eoiii'iiiii>iHA~EEcoo 6-RCS Primary Piping 20-PZR Surge Line 21-SD Cool ing Loop 1
22-SD Cooling Loop 2 23-Sl Loop 1A HL 1
HL 2 CL 1A to RCP CL 18 to flCP CL 2A to RCP CL 28 to RCP CL 1A to RPV CL 18 to RPV CL 2A to RPV CL 28 To RPV Butt Welds Butt Welds Butt Wclds Butt Welds RC-32-II2"ID RC-63-II?." I 0 RC-33-30" IO RC-30-30"IO RC-73-30"IO RC-8II-30" I D RC-3II-30" I 0 RC-31"30"ID RC-79-30"ID RC-93"30"ID RC-28-12" RC"51-16" S I -2IIO-16" RC-68-16" SI-193-16" SI-207-1II" SI-203-1?"
S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I 62, I
19 One Two Three One Two Three One Two Three One Two Three One Two Three 11 21 35 9
9 27 10 21 32 10 21 37 17 17 28
<<THE LESSOR oF 12" on 1
PIPE Olht'IF.-
TER I.ENGTH FROID sciico-ULFD Clilc WELD ItlTER-SECTIOtl /ILL BE ExhtllhgD AUTOMATED EXAM OF NOZZLE To EXTENSION AND FXIEN-SION To PIPE WELDS PVEE9-OICO Aev. 3/86
0 i
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 1 1-9 TABLE PAGE OF ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO. ~ OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS 911 912 920 921 922 CONTINUED 24-SI Loop 18 25-Sl Loop 2A 26-Sl Loop 28 28 Ec 29-PZR Spray Loop 18 and Combined 31-PZR Safoties 36-Letdown Line Delay Coil tiONltlAL PI PE SIZE (4 IN.
C I IICI)thFFRFNl'IAl, Atil)
>>IOIICITupitIAI. WFU)S 27-PZR Spray Loop 1A 28-PZR Spray Loop 18 Butt Welds Butt Welds Butt Welds Butt Welds Bott Welds Butt Welds Bott Welds Butt Welds SI-223"14" S I "221-12" S I -160-14>>
S I -156-12>>
S I -179-14" S I-175-12" RC-18-4" RC-1-6" RC"3-6" RC-5-6" RC-7-6" RC-91-16" RC-62-3>>
RC-16-3" RC"17-3" RC-18-3" S,Vol S, Vo I S, Vo I S,Vol S, Vo I S, Vo I
.S 18 22 18 15 12 36 36 One Two Three One T'wo Three One Two Three One Two Three One Two Three One Two Three One Two Three One Two Three 0
16 26 9
23 28 11 17 28 13 20 33 6
25 42 0
25 25 8
16 26 11 19 28
<<TIIE LESSER OF 12" OR 1
PIPC DIAN" ETER LENCTII FROM SCIICD" ULED CIRC WELD INTER-SECl'ION W I L L BE EX-AMI tiED PVl )9-0)CO Bev 3/86
0
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
AN pp ASME CLASS t TABLE PAGE OF ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS I
EXAMINATION AMOUNT INSPECTION PERIOD RUNNING RELIARKSAND RELIEF REQUESTS 921 922 CONTINUED 30-Aux P7R Spray 3?.-,Drain Line Loop IA 33-Drain Line Loop 10 3>>-Drain Line I.oop ?A 35-Drain Line Loop 28 36-Letdown Line 37-Charging Line 38-Drain Line Loop 1
39-HPSI Supply Loop 1
>>0-HPSI Supply Loop 2 Butt Welds Butt Wolds Butt Welds Bute Welds Bute Welds Butt Welds Butt Welds Butt Welds Butt Molds Butt Welds CII-521-2" RC-60-2" RC-58-2" RC-96-2" RC-89"2 RC-91-2" Cll-5-3" RC-70-2" Sl-2>>8-3" S I -199-3" I
11 I 5
70 i 60 25' 0'0 One Two Three One Two Three One 1wo Three One Two Three One Two 1hree One Two Three One Two Three One Two Three One Two Three One Two Three 18 36 36
>>0
>>0
>>0 0
>>0
>>0 0
0
>>0 0
0
>>0 6
1>>
26 8
18 28 0
25 25-6 1>>
25 12 20 28 PY419.0 TCD aov 3/86
l
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 1 1 "9 TABLE PAGE 0"
ASME ITEM NO.
930 931 932 ZONE0COMPONENT OR SYSTEM BRAtICII P I PE CONNFC-I I Otl WLI.DS tIOI'lltlAI. P I PF.
SIZF. K ll I tl.
6-RCS Primary Piping NOVI tIAL P I PL. SIZE II I tl.
6-RCS Primary Piping 21-SD Cooling Loop 1
22-SD Cooling Loop 2 IDENTIFICATION Snrge SD Cool ing 1
SD Cooling 2
SI 1A Sl 10 SI IC SI 1D Dra in 1A PZR Spray IA Dra in 10 PZR Spray 10 Dra in 2A Cha rg ing Letdown 2>> Dra in 3>>
HPSI 3>>
HPSI DESCAIPTION, LIIIENO., OR SERIAL NO.
RC-28-li2>>ID RC-32-ll2>>ID RC-63-II2>>ID RC-30-30>>ID RC-31-30>>ID RC-79-30>>ID RC-93-30>> ID RC-33-30>>ID RC-3II-30>>iD RC-30-30>> ID RC-3 1-30>> I D RC-73-30>>ID RC-79-3(l>>10 RC-8II-30>>ID RC-0~>
1-16'C-068-16>>
NDE METHOD S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I TOTAL ITEMS 1
1 1
1 1
1 EXAMINATION AMOUNT 1
0 0
1 1
I 1
INSPECTION PERIOD Three One Three Two Three One Two Three One Two Ttiree One Two Three RUNNING I II 29 71 I12 REMARKS AND AELIEF AEQUESTS I TEH 09. 31, SYSTEMS COtl0 I tlED FOR PERCENT-AGE IlEH 09.32, SYST Et IS COHBINED FOR PERCENT-AGE 9IIO 36-Letdown Line SOCKET WEI.DS 32-Drain Line l.oop 1A 2>> Delay Coil Socket Wolds RC-091-16>>
RC-060-2>>
3" One Two Three One Two Three 36 33 33 33 PV41947co Acv 3/86
~,
0,
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 1 TABLE PAGE 1-9 OF ASME ITEM NO.
ZONEvCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENO. ~ OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 9IIO Cctil I t{IIFD 33-Drain Line Loop 10 3II-Drain Line Loop 2A 35-Drain Linc Loop 28 38-Drain Line Loop 1
Socket Welds Socket We ids Socket Welds Socket Welds BC-058-2" BC-096-2" BC-089-2" BC-070"2" One Two Three One Two Three One Two Threo One Two Three 0
33 33 0
33 33 0
0 33 33 33 33 PV4 l9-OICO Aev 9I66
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CI ASS t 1-10 TABLE PAGE OF ASME ITEM NO.
ZONEGCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS 8100 EXAM EATEGOEY E-X-1'FIEE11AL AYEAan1EEEE FOR P I P I NG~P~UNIES AND VALVES 1010 1020 1030 P I I I IIG INTFGRAI.LY WELDED A1 TAClltlftlTS 22-SD Cooling Loop 2 2II"SI I.oop 10 25-SI Loop 2A 26-Sl Loop 20 36-Letdown Line PIIIZPS I tl rFGRAI.I.Y WFLDED AfI AClltlFtlTS VAI VFE."E I tllfGIIAI.IEY WELDED AI I ACIIIIf~tt'I S Lugs Stanchion Stanch) on Stanchion Lugs None tlonc S I "193-16ff SI-223-1ttff S I -160-111 ff S I -179-1tlff RC-091-16" S
Two Three Three One One Two 100 33 66 ITEM 010. 10 COt IB I tIED FOR PFRCENT" AGE PV419417CO RGV 318El
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ASME CLASS 1 1-12 TABLE PAGE OF 1
2 ASME ITEM NO.
ZONEECOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF AEOUESTS 8120 1210 1220 1230 12(IO rxnM CATE B-i.-1 0-II-I 'RESSURE ftl I A I N I N(F wrtll)s I II I'I)i<P cns I tiGs n iD vni;yrE i)o'i)'if.s;:xwc
(:n) f, 0" lF-7 l3-0-7.'III'll cnsFINGS ntiD vnl,vE l)DDIEs P IIII PS P(iiii'ns INC WFI,DS 16-RC P<<mp 1A 17-RC IFomp 10 18-RC P(m)p 2A 19-flC-P<<mp 20 16-RC P<<mp In 17-RC Pomp 10 18-RC Pump 2n 19-RC-Pomp 20 PUMP CASINGS 16-RC IFomp 1n 17-RC Pomp 18 18-RC Pomp 2n 19-RC-Pump 28 VALVES VALVES~NOMINAL PIPE SIFTS (~II It.
VALVF.
BODY WELDS
~~VALVES, NOMINAI.~~
P I PE S I 7F E II IN. VALVE BODY WLLDS Borg Warner Gate Valves Utilizing Forged Construction Circ Casing We I ds Outlet Nozzle to Casing We I ds Internal Surfaces tlone UV-651 UV-6r53 UV-657 UV-65(i UV-63(l UV-6(III UV-61(I UV-62(I 1255 i257 1256 1258 12r55
-1257 1256 1258 1255 1257 1256 1258 RC-r51-16 SI-2IIO-16" RC-68-16" S I "193-16" S I -207-III" S I -223-1(I" S I -160- III" S I -179" 1II" Vo I Vol VT-3 Vol Examine the Wold in 1
Pomp Examine the Weld in 1
Pump Examine the interne I Surfaces in 1
Pump Examine the Weld in 1
Va lve 100 100 100 100 "l3Y TIIE END Of 1 IIE IIITERVAL PV41947CO AEV SF86
0'
wow PALO VERDE NUCLEAR GENERATING STAT N
10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 1 1-12 TABLE PAGE 0"
ASME ITEM NO.
ZONEDCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OA SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD AUNNING AEMAAKSAND RELIEF REOUESTS 12>>0 1250 COIIT INUED Borg Warner Check Valve Utilizing Forged Construction Dresser Prcssure Safety Valves Utilizing forged Construction VAI,VE OOOV EXCEED-tttt'l It( XPllltlliL P I PE Sl Zf; Borg Warner Cate Valves Utilizing Forged Construrtion Borg Warner Chock Va I ves Uti I izing Cast Construction Dresser Pressure Safety Valves Utilizing Forged Construction V-2>>>>
PSV-200 PSV-201 PSV-202 PSV-203 UV-651 UV-653 UV-65?.
UV-65ll UV-63>>
UV-6II>>
UV-61>
V-235 V-237 V-5>>2 V-2>>5 V-2>>7 V-5>>3 V-215 V-217 V-5<<0 V"225 V-227 V-5>>1 PSV-200 PSV"201 PSV-202 PSV-203 AC-18->>"
AC-I"6" IIC-3-6" IIC-5-6" IIC-7-6" AC-51-16" S I -2>>0-16)"
AC l6" S I -193-16" S I -?07-1>>"
S I -223-1>>"
S I -160-1>>"
S I -179-ll S I -207-1>>"
S I -207" 1>>"
SI"203-12" S1-223-1>>"
SI-223-1>>"
S I -221-12" SI-160-1>>"
S I -160-1>>"
S I -156-12" SI-179-1>>"
S I -179-1>>"
S i -175-12" RC-1-6" AC-3-6" TIC-5-6" TIC-7 6n Vo I Vol VT-3 VT-3 VT-3 12, Examine the Weld in 1
Va lve Examine the Intcrna I Surl'aces of 1 va lve Examine the Interna I Surfaces of 1 va Ive Examine the Into ma I Surfaces of 1
Va lve 100 100 100 "BY TIIE LNtD Ol TIIE I N T F.IIVAL 100 PV419.0)CO ACV 3I86
e 0,
A rt> p p PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ASME CLASS 1 1-13 TABLE PAGE OF ASME ITEM NO.
ZONERCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS 8130 EXllll CATFOORV R-R-I' IIII',IIIOR OF REACTOR Vl:SSEI.~B-N-2 I III-FGRAI.n WELDFD CORF:
SUPPORT STlfUC-1UIIFS Atll) INIFRIOR ATTACIIHLNIS 10 RFR-At:IOII VIS SSI I S II-lt-3 IlTIIDVAIII.I:COIIF. SOP-PORI STRUCTURES 1310 RFACTOR VESSEL VESSEL ItlTERIOR 1-Reactor Vessel Examine thc acc areas al>ovo an>i roactor rore tl>
acccssiblc for t ion by rernova I ner>ts d>>ring no fueling outages
>ss iblc below the
>t is made
.xamina-of compo-mal re-VT-3 Acces sible Areas 33K 33%
3rl'$
>>One
>>Two "Three 33 66 100 "EXAHIIIEET 1ST REI ULFL~
ING OUIAGE, AtlD SUBSE-QUF.NTLY AT 3-YEAR INTERVALS 1320 1321 1322 1330 1331 1332 Illf FflIOR ATTAC>ltlEtlfS C()IIF SUPPORr S1RUC-TUIIF I Nl'fR I OR ATTACIINENTS WI TH I If BELTLI tlE RF.(R I Otl I tlTER I OR ATTACIIIAEtITS BE-Y()IID BFLlLI thE RnF.(: ION CORE SUPPORT STRUC1URE N/A N/A None Examine the acc.ssible welds and surro >nding Examine the acc ssible core support st ucture VT-3 VT-3 Acces sible Welds Acces sible Sur-faces 1001o 100%%d 100 100 "BY THE EtlD OF THE ItlTERVAL rt>tc>9 0>CO r>CV 3386
~
i 0
PALO VERDE NUCLEAR GENI=RATING STATION 10 YEAR INTERVALEXAMIIIATION
~~SUMMARY~~
AhrPP ASME Cl ASS 't 1 - III TABLE PAGE OF ASME ITEM NO.
ZONEvCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS B1IIOO 1II 10 EXAII CATEGORY B-0 PRF,.'iSIIRF. RF,'TAIN)NO Wi;I.I)S Iii COIITROL Ron tloUSIN(is RFvACTOR VFSSEL WELns IN CRD HOUslNG 2-Reactor Vessel Closure tlead CEDING Housings 2-React;or Vessel Closure Head CEDN Housings 2-Reactor Vessel Closure tlead CEDII Housings 2-Reactor Vessel Closure Head CEDE Ho<<sings Lower Housing Wetds Upper Housing We Ids Tube Housing Lower Weld 1ube Housing Upper Weld Housings
//66 - //97 Housings
//66 " //97 Housings<<>>
//66 - //97 Ilous lngs
//66 - 497 Vo I Vo I Vol Vol
%97
%97
%97
%97 One Two Threo Ono Two Three One Two Three One Two Three 3
6 11 ITEN BIII.10 CotRB I IIED FOR PEltCEtlTAGE "32 PERIPH-ERAL (126 1OTAL WELDS>
""INCLUDES 2 RVLIIS TRAII-HUBS lvV4l9 Orce AuV 3/86
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 1 1-15 TABLE PAGE OF 1
1 ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENO., OR SERIAL NO.
NDE METHOD TOTAL.
ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS B150 EKAhIINATION CATFGORY O"P ALI, PRESSURE
~ -D RETA I II I NG CuhIPONFNTS 1510 1520 1530 15IIO 1550 1560 1570 1511 15? 1 1531 15II1 1551 1561 1571 SYSTEM LFAKAGE TEST Reactor Vessel Pressurizer Steam Generators Heat Exchangers Piping Pumps Va Ives SYSTFH IIYORO-TFST ReacLor Vessel Pressurizer Sl.earn Generators llcat Exchangcrs Piping Pumps Valves Press< rc Rota ir.ing Oounda ry Pressure Retaining Oounda ry VT-2 VT-2 Entire Pres-sure retain-ing boundary I'hlA"5000 I'WO-5000 Entire Pres-sure retain-ing boundary IMA 5000 IWO-5000 100 100
+ EACII REFUELING OUTAGF.
""BY TIIE END OF TIIE INTERVAL PV419-07CO AE~. 3:86
0'
AN PP PALO VERDE NUCLEAR GENI=RATING STATION 10 YEAR INTERVALEXAMIIIATIONSUhlMARY ASME CLASS 1 1-16 TABLE PAGE OF ASME ITEM NO.
ZONE+COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 8160 EXAMINATION CATfGORY l3-q, STLAN GENFRATOR TUB I ttG 1610 1620 N/A Per ASNE Section XI and 10CFR50, AII Eddy Current Exam-inations of Steam Generator Tubing wiII be perl'ormed in accordance with PVttGS Technica I
Specifications PVtlg PlCO Rev 3186
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMIhlATION
~~SUMMARY~~
ANPP ASME Ct ASS 't 1-IWF TABLE PAGE DF ASME ITEM NO.
ZONEGCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS F110 F120 F130 F1IIO F210 F220 F230 F2<<0 F310 F320 F330 F340 f350 EXAII CATEGORY E-A'LATF AND SIIELL TYPE SUPPORTS and EXAM CATFGORY F-R.
I.IIIEAR TYPE SUPPORTS and EXAI> CATEGORY F-CD Cni'll ntII-tIr STAtIDARII SUPPnit I' 1-Reactor Vessel 3-Steam Generator 1
4-Steam Generator 2
Support Columns Support Skirt Support Skirt SN 79173 SN 79273-1 SN 79273-2 VT-3 VT-3 VT-3 1
1 2
Ono Two Three One Two Three One Two Three 25 50 100 100 100 100 100 100 REQUEST FOR RELIEF //1 8e
//3
+INCLUDES EXAM ITEMS IDEttflFIED AS APPLi-.
CABLE.
Ee>>NDE METIIOD INCI.UDES VT-tl EXAMS, WIIERE APPLI-CABLE.
5-Pressurizer 16-Reactor Coolant Pump 1A 17-Reactor Coolant Pump 10 18-Reactor Coolant Pump 2A 19-Reactor Coolant Pump 20 Support Skirt Vertical and Lal.cra I Sup-ports Vertical and La tera I Sup-ports Vertical and La tera I Sup-ports Vertical and Latera I Sup-ports SN 79373 SN-1110-lA SN-1110-10 SN 1110-2A SN 1110-20 VT-3 VT-3 VT-3 VT-3 VT"3 10 10 10 10 One Two Three One Two Three One Two Three One Two Three One Two Three 100 20 60 100 20 60 100 40 60 100 40 60 100 Pve19 Oleo nev 3!66
~,
0
PALO VERDE NUCLEAR GENI:-RATING STATION 10 YEAR INTERVALEXAMIIIATION
~~SUMMARY~~
'NPP ASME CLASS 1 TABLE PAGE 1-IWF QF ASME ITEM NO.
ZONE0COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO. ~ OR SERIAL NO.
NDE METHOD TOTAL; ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS F110 F120 F130 F1<<0 F210 F220 F230 F2<<0 F310 F320 F330 f3<<0 F350 CONTINUED 20-PZR Surge Line 21-SD Cooling Loop 1
22-SD Cooling Loop 2 23-SI l.oop 1A 2<<-Sl Loop 18 25-SI Loop 2A 26-Sl Loop 28 27-PZR Spray Loop 1A 28-PZR Spray Loop 18 29-PZR Spray Loop 18 and Combined 30-Aux PZR Spray Supports Supports Supports
( 1-810. 10)
Supports Supports
( I-810. 10)
Supports
( 1-810. 10 )
Suppo rt.s
( 1-810. 10)
Supports Supports Supports Supports RC-28-12" RC 51-16 SI-2<<0-16" RC-68-16" SI-193-16" S I -207-1<<"
SI-203-12" S 1-223-1 II" S I -221-12" S I -160" 1<<"
SI-156-12" S I -179-1>>"
S I -175-12" RC-62-3" RC-16"3" RC"17-3" RC-18 3n RC-18-<<"
RC-18->>"
CII-521-2"
'T-3 VT-3 VT-3 VT=3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 22 13 l
28 28 5
9 11 8
9 8
11 One Two Three One Two Three One Two Three One Two Three One 1wo Throo One 1 we Three One Two Three One Two Three One Two Three One Two Three One Two Three 29 58 100 32 6<<
100 31 69 100 295t 100 25 50 100 29 71 100 33 67 100 32 68 100 33 61 100
<<0 100 100 100 PV4 l9.0TCD aev sv86
~
L PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMltlATION
~~SUMMARY~~
ANPP ASME CLASS 1 1-IWF TABLE PAGE OF ASME ITEM NO.
F110 F120 F130 F140 F210 F220 F230 F240 F310 F320 F330 F340 F350 ZONE+COMPONENT OA SYSTEM COIITINUFD 32-Drain Line Loop IA 33-Drain Line Loop 18 34-Drain Line Loop 2A 35-Drain Line Loop 28 36-Letdown Line 37-Charging Line 38-Dra in Line Loop 1
39-IIPSI Supply Loop 1
40-IIPS I Supp ly Loop 2 IDENTIFICATION Supports Supports Supports Supports Supports
( 2-810. 10 )
Supports Supports Supports Supports DESCRIPTION, LINE NO., OA SERIAL NO.
RC-60-2" RC-58-2" RC-96-2" RC-89-2" RC-91-2" CII-001-2" Cll-5-3" RC"70-2" SI 248 30 SI-199-3" NDE METHOD VT-3 VT-3 Vl-3 VT-3 VT-3 VT-3 Vf-3 Vi-3 VT-3 TOTAL ITEMS 2
2 1
32 43 14 EXAMINATION AMOUNT 11 10 11 14 14 15 INSPECTION PERIOD One Two Three One Two 1hree One Two Three One
'wo Three One Two Three One Two Three One Two Three One Two Three One Two Three RUNNING 100 100 100 100 100 100 100 100 34 66 100 33 65 100 0
0 100 29 62 100 33 77 100 REMARKS AND RELIEF REQUESTS Snubbers:
IWF-5000 AII inservice testing requirements will be performed in ccordance with PVNGS Technical pecifications.
REQUEST FOR RELIEF //1.
pv419 Oleo Iree 3186
~
I
~
PALO VERDE NUCLEAR GENI:RATING STATION 10 YEAR INTERVALEXAMIIIATION
~~SUMMARY~~
AN PP ASME CLASS 1 1-RCP TABLE PAGE OF 1
ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS N/A RCAI:TOn COOI.ANT PUHP F LYITIII;~FI.
f.XAHI NA-I lOIIS IIFG GO IOE I. Ili 16, 17, 18 and 19 Reactor Coolant PumPS IA, IB, 2A 8G 2B Flywhoels F lyvhee I s Vo I <<
"S, Vo I One Two Three 100 100 100 REFERENCE PVNGS TECII SPEC II ~ II.9
<<AN ULTRA" SONIC EXAH-INATIOH WI.LL BE PERFORHED OF TIIE AREAS OF HIGIIER STRESS CON-CEHTRATIOH AT TIIE BORE AND KEYWAYS.
<<<<A SURFACE EXAH OF AI.L EXPOSED SUR-FACES AND A COHPLETE ULTRASONIC EXAH TO TIIE EXTENT PRACTICAL WILL BE PER-FORHED.
PV41941CO Rev,3/86
~
j
-SECTION 5.0 ASME CLASS 2 EXAMINATION.
~~SUMMARY~~
5-1
0
INDEX TABLE EXAI'1 CATEGORY 2-1 '-A, 2-2 C-B, 2-3 C-C, Pressure retaining welds in pressure vessels Pressure retaining nozzle welds in vessels Integral attachments for vessels,
~~piping, pumps, and valves 2-4 C-D, Pressure retaining bolting exceeding 2 in.,~~
in diameter 2-5 2-6 2-7 C-F, C-G, C-H, Pressure retaining welds in piping Pressure retainin welds in oumps and valves All pressure retaining components 2-INF F-A, F-B,
---F-C 1
Plate and shell type supports Linear type supports
~
.- Component standard-supports 5-2
0
~,
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMlhlATION
~~SUMMARY~~
ANPP ASME CLASS 2
'2-1 TABLE PAGE ASME ITEM NO.
ZONE+COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS C100 fXAth,CATE(>ORY~C-A PRESSUIIE RCTAINItlG WFI.DS IN PRESSURF.
VESSFLS 110 120 130 STFAtl GENERATORS SHELL CIRCUthffREN-TTAt. TELOS 41-Steam Generator 1
42-Steam Generator 2
HEAD CIRCUIRFEREN-TIAL WELDS 41-Steam Generator 1
42-Steam Generator 2
TURESHEET-TO-SHELL WFLD Shell.to Conical Welds Shell to Conical Welds Head to Sholl Weld Head to Shell Weld SH-79273-1 SH-79273-2 SN-79273-1 SN"79273-2 Vo I Vol Vol Vo I 0
0 0
0 50%
0 0
0 0
50%
One Two Three One Two Three One Two Three One Two Three MULTIPLE VESSELS:
PERCEHTAGE COMBINED 50 "50%
EACH WELD 100 kk50%
EACH WELD 50 100 41-Steam Generator 1
42-Steam Generator 2
Outside Shell and Stay Cylinder Outside Shell and Stay Cylinder SN-79273-1 SH-79273-2 Vol Vol 2
50%%uk 0
0 0
50%k 1kk One Two Three One Two Three 25 50 100 "OUTSIDE SHELL WELDS
""STAY CYLINDER EXAM Pv41941CE Rev.3/96
0
ANPP PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMlhlATION
~~SUMMARY~~
ASME CLASS 2 TABLE PAGE 2-1 OF ASME ITEM NO.
ZONEQ COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT tNSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS 110 120 RF.('>>F.NFRAT I VF. HF.AT EXCIIAtIGER SHEI.I. C I RCUI6FEREN-T I AI. WEI.OS 68-Regonorative Heat Exchangor HEAO CiRCIIHFFREN-T IAI. WF.I.OS Butt Welds SN-79313 Vol One Two Three 33 66 100 SINGLE VESSEL 130 68-Regenerative Heat Exchanger TUBESHEET-TO-SHELL WEI l)S Head to Stir. I I Stt-79313 Vol One Two Three 50 50 100 68-Regenerative Heat Excttangor LETOOWtl HEAT FXCHANGER Butt Welds SN-79313 Vol 0
2 2
One Two Three 0
50 100 SINGLE VESSEL 110 120 130 SHELL CIRCUNFEREti-1'IAL WEI.OS 69-Letdown Iieet Exchanger HEAD CIRCUIIFEREN-TIAI WFIOS 7 I)BESHEET-TO-SHFI.I WEI.I) 69-Letdown Heat Exchanger Shel I to f lange tlone Butt Wold SN-N2373 Stl-N2373 Vo I Vol 50%
0 50%
50%
0 50%
Ono Two Three Ono Two Three 50 50 100 50 50 100 PV41647CE Rev. 3/86
0, 0
~,
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMII'IATION
~~SUMMARY~~
ANPP ASME CLASS 2 2"1 TABLE PAGE OF ASME ITEM NO.
ZONE+COMPONENT OA SYSTEM IDENTIFICATION DESCRIPTION, LINE NO. ~ OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING AEMAAKSAND RELIEF REQUESTS SIIUTDOWN COOL I tlG HEAT EXCHANGFRS HULTIPLE VESSELS:
PERCF tiTAGE CONBltlEO 110 120 130 SIIFI.I C I RCUHFEREtt-TIAL WELDS 7II-SD Cool ing iieet Exchanger 1
75-SO Cooiing Heat.
Exchanger 2
tlEAD CIRCUI'IFEREN-T I AL WF.I.DS TUBFSHEET-TO-SHELL WF.LD 7II-SD Cooling Heat Excllanger 1
75-SO Cool ing Hear Exchanger 2
Shel I to F lan<le She I to Flan<le None Butt Wold Butt Weld Stl-S183II3 Sti-S183II II SN-S183II3 Sti SI83IIII Vol Vo I Vol Vo I 0
50%
0 0
0 50%
0 50%
0 0
0 50%
One TWO Three Ono Two Three One Two Ttlree One Two Three 50 50 100 50 50 100 PVll947CE Bcv. 3186
0 4
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 2 2-2 TABLE PAGE OF ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE No., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATI0 N AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS C200 EXAI4 OATEOOAY 0-S'IIESSIIIIT.
IIFTAISIIAO NOZ7LE WELOS IN VESSELS 210 220 221 222 tiOZZLES IN VESSELS 1/2 I N riot I I tiAI THICKNESS iiOZZLFES WI TROUT RF.lrirnltr,tiIG PLATE Itl VI:SEF.LS ) 1//P I II NOMItiAL THICKNESS
'IOZZI.E-TO-Sill:LL (OR IIFAI)I WF I,OS ANI) ti07ZLF I tiS IOE RAI)IUs sEG1lorI 41-Steam Generator 1
42-Steam Generator 2
74-SD Cooling Heat Exchanger 1
75-SD Cooling Heat Exchanger 2
Hone Nozzle to Vessel Welds Nozzle to Vessel Wolds tiozz I e to Shell We ids tiozzle to Shell Welds SN-79273-1 SN-79273-2 SN-S18343 SN-S18344 S, Vo I S,Vol S, Vo I S,Vol One Two Three One Two Three One Two Three One Two Three 29 100 57 50 100 INSIDE RADIUS OH PIPING'WLY GREATER T I IAti 1 2" EA, 0 I AIIETER.i REQUEST FOR RELIEF
//2 MULTIPLE VESSELS:
PERCEtiTAGE COMBItiED MULTIPLE VESSEI.S PERCEtiTAGE COMBINED PV41941CE Rev. 3/86
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
AN PP ASME CLASS 2 2-2 TABLE PAGE OF ASME ITEM NO.
ZONEe COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 230 231 232 IIOZ7LFS WI TII RE I H-F()IIC INC> PI,ATE IN VCSSCLS W 1/2 IN Net 1 I HAI. 1 II I CKNESS REINFORCING PLATE WI-I.DS TO HOZZI E AtlD Vf SSEL NOZZLE-TO-SIIELL
/OR HEADI Wl'.LDS INSIDE OF VESSEL ACCESSIBLE ItISIDE OF VESSEL ItlACCESSIBLE None Hone Hone PV41901CE Rev. 3/86
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
A IEI P P ASME Cl ASS 2 2-3 TABLE PAGE OF "
ASME ITEM NO.
ZONESCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REOUESTS C300 EXAII CATEGORY C-C' I IITE(iRAL A~TTACIIIILNTS Soil vEEEIris i'liioo Plltll'S Alii) VALVES 310 PRESSURF.
VESSFI S INTFCRAII.Y WELDED ATTACIIIIENTS 41-Steam Generator 1
4?-Steam Generator 1
68-Regcne ra t ive Ilea t Exchanger 2-Snubber Lugs 2-Snubber Lugs 2-Supports SH-79273"1 SH-79273-2 SH-79313 Ono Two Three Ono Two Three One Two Three 50 100 50 100 HULTIPLE VESSEI'>SI PERCENTAGE COFIIIIHED SINGLE VESSEL 320 PIPING IN1FC;RALIY WELDED ATTACIIHEHTS 43-Hain Steam SG-1 90 Inside Cont 44-Hain Steam SG-1 2704 Inside Cont 45-Hain Steam SG-2 270'nside Cont ll6-Hain Steam SG-2 90'nside Cont 51-Atmospheric Dump SG-I Attachmonts Attachments Attachments Attachments Attacltments SG"36 SG-33 SG-42 SG-45 SG"59 SG-70 One Two Three One Two Three One Two Three One TWo Three One Two Three 16 33 100 60 100 60 80 100 40 100 50 100 100 pve1947CE Aev. 8/86
~
i 0
I
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATIONSUMI'AARY ANPP ASME CLASS 2 2-3 TABLE PAGE 2
OF ASME ITEM NO.
ZONEc COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 320 CONTtNUFD 52-Atmospheric Dump SG-2 53-Stcam to Aux Feedwater System 5II-Feedwater sG-1 Insido Cont.
55-Feedwater SG-2 Insldo Cont.
62-Aux. Fecdwatcr S/0-1 6II-BIowdown SG-1 Inside Corrt.
65-Blowdown SG-2 Inside Cont.
70-LPSI Pump Suction I.oop 1
71-LPSI Prrmp Suction Loop 2 72-LPSI Prrmp Discharge Loop 1
7II-SD Cool ing Ilx Outlet Loop 1
Attachments Attaclrmonts Attachments Attactrmcnts Attactrrnents Attachments Attachments Attachments Atl.actrmcnts Attachments Attachments SG-6II SG-103 SG-61 SG-63 SG-002 SG-005 Af-018 SG-39 SG-II8 S I -2II1 SI-369 SI-239 Sl-2 S I -19rl SI-67 SI-78 S I -70 SI-87 SI-90 One Two Three One Two Three One Two Threo Orre Two Ilrroe Onc 1wo three One Two Three One Two Three One Two Ttrree One Two Three Orre Two Three One Two Three 100 100 100 100 100 r50 50 100 100 50 75 100 29 71 100 50 100 100 50 50 100 r50 50 100 25 75 100 pv419%rcE Rcv. 3/86
~
i
PAI 0 VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 2 2-3 TABLE II PAGE OF ASME ITEM NO.
ZONE+COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 320 CONTINUED 75-SD Cooling ltx Outlet: Loop 2 76-LPSI Ileader 1A Attachments Attachments SI "72 Sl-70 SI-202 3
One Two Tltroe One Two Three 33 33 100 67 67
-100 79-LPSI Ileader 20 80-Containment Spray Pump Suction Loop 1
82-Cont.ainment Spray Discharge Loop 1
83-Containmcnt Spray Discharge Loop 2 8II-Conta inment Sump Suction l.oop 1
85-Containment Sump Suction Loop 2 Attachments Attachments Attachments Attachments Attachment Attachment S I -17ll SI-9 SI-79 S I-119 SI-7 Sl-30 One Two Tttree One Two lhreo One Two Three One Two Throe Ono Two Three One Two Three 100 100 100 IOO 100 50 100 100 100 100 100 330 PUNPS It)if:GRALLYWELDED ATTACIINEIITS 72-LPSI Pump Loop 1
73-LPSI Pump Loop 2 Attachment Lugs Attachment Lugs SN 0876-IIO Sti 0876-II1 One Two Three One Two Three 66 100 100 33 100 PV41947CE Rev. 3/86
0
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASl'JIE CLASS 2 2-3 TABLE PAGE OF ASME ITEM NO.
ZONEeCOMPONENT OA SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD AUNNING REMAAKSAND RELIEF REQUESTS 330 Continued 80-Containment Spray Pump Loop 1
81-Containment Spray Pump Loop 2 Attachment Lugs Attachment Lugs SN 0876-II2 SN 0876-II3 One Two Three One Two Throe 66 100 100 33 100 3IIO VAI.VI-S I tITI:I:AhtI,Y WELDED AT IIACIifhI;IITS None pVe 1 9.07 CE Aev. 3/66
0
~
I
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 2 2-4 TABLE PAGE OF ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS C400 EXAW CATEGORV C-D PRESSURE RETAItIING BOLTlttc EXCEFDING 2
IN.
IN DIAtIETER 410 420 430 4>>0 PRFSSURE VFSSELS BOLTS AtID STUDS PPIiP I IIII BOLTS AND STUDS PUMPS ROI.TS AND STUDS VAI,VFS ROL'I S Atil) STUDS
<<7-Ha in Steam SG-1 270 HSSS 48-fla in Steam SG-1 90O HSSS 49-Hain Steam SG-2 270 HSSS 50-Hain Steam SG-2 90 HSSS 56-feedwater SG-1 IISSS 57-Feedwater SG-2 IISSS Nolle Hone tione Bonnet Bolts Bonnet Bolts Bonnet Bolts Bonnet Bolts Bonnet Bolts Bonnet Bolts UV-170 UV-180 UV-171 UV-181 UV-132 UV-174 UV-137 UV-177 Vol Vol Vol Vo I Vo I Vol Vol Vol 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 One One Three Three Two Two Three Three (25)
(25)
( 100)
(100)
(50)
(50)
( 100)
( 1001 I TF.H CIIIIO COHBIHED fOR PElt-CEHTAGE PVCl947CE Rev. 3/86
0,
~,
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 2 2-5 TABLE PAGE 1
OF I
ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATI0 N AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS C500 510 511 512 I xntlltlATION CATFGORY C-I'RESSUIIE Rf-J TAIN IN(l WFI OS Itl
~~PIPIIIr, PIPING WELDS K 1/2 IN.~~
OR LFSS NOIIINAL WAI.I,Tll I CKIIF.SS C I RCUIIfFREtIT I AL AND
<<LONG I 1 Iio I NAI. WELOS 53-Steam to Aux.
Feedwa te r 58-Aux. and Down-comer Feedwal.er SG-1 Inside Cont 59-Aux.
and Oown-comer Feedwater SG-2 Inside Cont Butt Welds Butt Welds Butt Welds SG-81-6" SG-83-6" SG-8-6" SG-8-8" SG-11-6" SG-11-8" Skkk S
$<<kk S
1 II 15 3
23 3
2II kk kk One Two Three One Two Three ll 12 12 ll 22 AIIR, CHR, Ec ECCS SYSTEMS ARE SCHED-ULED PER 10CFR50 RFQUIAE-MEHTS AHD ARE IDEN-TIFIED It)
TABLE'-CFR "2.5T Mltl.
FAOM FACH SCHCDULEO CIRC.
WELD INTCRSCC-TION WILL OE EXAMINED k"AFQUIRC-IIENTS IDENTIFIED IH TAOI.E 2-AHE
<< <<<<AII AUGMENTED VOL EXAII-I tIATION WILL BE PERFORMED EACH PERIOD (SEE IEO 79-13 AND SER 83-OI)
PvciNPCE Rcv. 3/86
~,
~
I
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP I
ASME CLASS 2 2"5 TABLE PAGE 0"
ASME ITEM NO.
ZONEe COMPONENT OR SYSTEM IDENTIFICATION DESCRIPT(ON, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 520 521 522 PIPING WELDS 1/2 I tl.
tlOtlI NAL wnLI. TrlicKtrr.ss C I RCIIHFFRLNI I Al AND
<<l OIIGITUDitlAI WFi.ns ll3-Hain Steam SG-'I 90'nside Cont.
lilt-Ha in Steam SG-1 270'nside Cont.
II5-Hain Stcam SG-2 270'nside Cont.
II6-Hain Stcam SG-2 90'nside Cont.
ll7-Hain Steam SG-1 270 IISSS II8-Hain Steam SG-1 90 HSSS ll9-Hain Steam SG-2 270 HSSS 50-Hain Steam SG-2 90 HSSS 51-Atmosphere Dump SG-I 52-Atmosphere Dump SG-2 Butt Welds Butt Welds Butt Wclds Butt Wclds Butt Welds Butt Welds Butt Welds Butt Wclds Butt Welds Butt Welds SG-36-28<<
SG 33 28<<
SG-II2-28" SG-II5-28" SG"206-28" SG-206-12" SG-2I)6-6" SG-207-28" SG"207-12" SG-207-6" SG-208-28" SG-208"12" SG-208-6" SG"209-28" SG-209-12" SG-209-6" SG-59-12" SG-70-12" SG-8II"12" SG" 103" 12" S, Yo I S, Yo I S,Vol S,Vo I S,Vol S, Vo I S, Vo I S, Vo I S,Vol S,Vol S,Vol S, Vo I S, Yo I S,Vol S, Vo I S, Vo I S, Vo I
',Vol S,Vol S, Vo I 20
'8 20 5
~
2 5;
5' 2"
5,-'
2 5
11 13 13 11-3 0
2 0
2 3
2.2 1
One Two Three One Two Three Ono Two Ttlroe One Two Three 17
.17 28 15 20 30 ll 28 10 20 25
+2.5T HIN.
FROH EACII SCiiEDULED CIRC.
WELD ItlTERSEC-TION WILL BE EXAHIIIED
<<REQUIRE-t4ENTS IDEtlTI F I ED IN TABLE 2-AIIE pv4r94rrcE aev. 3/86
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 2 TABLE PAGE 2-5 3
PF4 ASME ITEM NO.
ZONE+COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 521 522 CONTINUEO 5>>-Feedwater SG-1 Inside Cont.
55-Feedwater SG-2 Inside Cont.
56-Feedwater SG-1 NSSS Butt Wolds Butt Welds Butt Welds SG-2-2>>"
SG-2-16" SG-2-1>>"
SG I6" SG-13-1>>"
SG-5-24" SG-5-16" SG-j-1>>"
SG" 1>>-16" SG-I>>- I>>"
SG-201-2>>"
SG-202-2>>"
S, Vo I S,Vol S, Vo I S, Vo I S, Vo I S, Vo I S,Vol S,Vol S,Vol S,vol S,Vol S,Vol 30 4
10 4
11 30 3
10 3
10 One Two Three One Two Tt>ree 8
17 27 9
18 27
~ 57-Feedwater SG-2 I'ISSS 58-Aux.
and Down-comer Feedwater SG-1 inside Cont 59-Aux. and Down-comer Feedwater SG-2 Inside Cont 60-Oowncomer F'eed-water SG-1 MSSS Butt Welds Butt Welds Butt Welds Butt Welds SG-20>>-2>>"
SG-205-2>>"
SG-8-6" SG-11-6" AF-6-6" SG"200-8" S,Vol S,Vol S, Vo I S, Vo I S,Vol S,Vol S, Vo I 1
1>>kk One Two three One Two Three 20 20 33 15 31 38 "REQUIRE-tIQITS IOLNTIFIEO It( TABLE 2-AIIE kklttCLUDES 1 OISSIHI-IAR WELD 61-Downcomer Feed-water SG-2 HSSS Butt Welds SG-203-8" S, Vo I 62-Aux.
Feedwa ter SG-1 HSSS Butt Welds AF-4-6
'AF-18-6" S,Vol S, Vo I 7
13 One Two Three 5
15 30 PVls947CE Rov. 9/86
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 2 TABLE PAGE 2-5 OF ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO. ~ OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 521 522 CONTINUED 63-Aux.
Feedwa te r SG"2 HSSS 64-Olowdown SG-1 Inside Cont 65-Olowdown SG-2 Insido Cont 66-Blowdown SG-I HSSS Butt Welds Butt Welds Butt Welds Butt Welds AF-6-6" Al-16-6" SG-39-6" SG-53-6" SG-48-6" SC-52-6" SG-39-6" S,Vol S,Vol S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I 13 3
37 14 34 14 Ono Two Threo One 1wo Three One Two Threo 6
19 31 4
12 20 8
15 23
<<REQUIRE4 HENTS IDFNTIFIED It] TABLE 2-AIIE 67-Blowdown SG-2 HSSS Butt Welds SC-48-6" S,Vol 530 531 532 P I PF.
BRANCll COttttEC-T ION~SR I N, NOI'llttAL PIPE SIZE C I RCUHFFRFtt1 I AI. Att0
<<<<LONGITUDINAL WFLOS 47-Hain Steam SG-1 270 HSSS 48-fdain Steam SG-1 90 HSSS 49-Hain Steam SG-2 270 HSSS 50-Hain Steam SG-2 9() o I,ISSS Sweepolets Sweepo I e ts Sweepolets Sweepolets SG-206-28 SG-207-28 SG-208-28 SG-209-28 5T Hl tt.
FROID I.Acti SCIIED-ULFD BRANCil WELD IIITER-SECTIOII WILL BE EXAfh I tl ED
<<REQUIRE-HFNTS IDENTIFIED I ti TABLE 2-AIIE PVel947CE Rev. 3/86
~,
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
AN PP ASME CLASS 2 2-6 TABLE PAGE OF ASME ITEM NO.
ZONENCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS C600 EXAM CATEGGIIY C-G PRFGRIIRP.
RFTAINIIIG WELDS IN PUMPS AND VAI.VES 610 620 PUIIPS PUHP CASItlG WFLDS VALVI.S VALVE BODY WELDS
~~Dresser, 6" x 10",~~
Pressure Sarety Hain Sl.earn Valves Bo rg Wa me r, 16" Gate Valves LPSI Pump Suction Borg Warner, 6"
Gate valves SD Cooling Ilx Outlet tlone Zone II7'oneII8 Zone II9 Zone 50 Zone 70 Zone 71 Zone 7II Zone 75 SG-206-28" SG-207-28" SG-208-28" SG-209"28" S I -2III-16" S I -191I-16" S I -131-6" Sl-l31-6" Examine the wold in 1 va lve Examine the weld In 1 va lve Examine the wold in 1
va lve 100 100 100
+BY TIIE EtlD OF TIIE I NTEI~Q VAI..
PV41947CE Rev. 3/86
e
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMl AVIATION
~~SUMMARY~~
A AI P P ASME CLASS 2 2-7 TABLE PAGE ASME ITEM NO.
ZONEUCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENO., OR SERIAL NO.
NDE METHOD TOTAL.
ITEMS; EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS C700 EXAM rATEOOUY C-M.
Al.L Flit:SOMME RfTAIII I NG COhIPO-NENTS 710 730 750 770 720 7/IO 760 780 EYSTEII FUMO~TIOIIA 1ES1S Pressure Vessels Piping Pumps Va Ives SYSTEH IIYDRO-TESTS Pressure Vessels Piping Pumps Valves Pressure Reta ning Bounda ry Pressure Reta ining Boundary VT-2 VT-2 Ent i re Pres-sure reta in-ing boundary IWA-5000 IWC-5000 Entire Pres-sure retain-ing boundary IWA"5000 IWC-5000 100 100 "EACII INSPECTION PERIOD S
<<EACII INSPECTION INTERVAL PT/41947CE acv. 3/86
0, 0
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
AN PP ASME CLASS 2 2" I WF TABLE PAGE 1
PF ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS F110 F120 F130 r1IIO F210 F220 F230 F2IIO F310 F320 f330 f3IIO f350 EXAII CATEGORY F-A'L(ITE At(tl Et(EEL TYPE SIIPPORI'S and EX(lll TAI'FGOIIY F-G'l((TA(l IYPF. SGI'PORTS and fxntc cnfrGDRY F-c.
l I
CtiiCI OtILIIT SrArIDARD SUPPOIITS UI-Steam Generator 1
ll2-S team Gene ra to r 2 ll3-Ha in S team SG-1 90'I Inside Cont IIH-Main Steam SG-1 270 Inside Cont 45-Hain Steam SG-2 270'nside Cont II6-Hain Steam SG-2 90 Inside Cont.
II7-tea in Steam SG-1 270 HSSS ll8-Hain Steam SG-1 90 IEISSS ll9-Main steam sG-2 270 HSSS 2-Snubbcrs 2-Snnbbers SUPP(3 rts Supports Supports Supports Supports Supports Supports SH-79273-1 SH-79273-2 SG-36 SG-33 SG-II2 SGII5 SC-2n6 SG-207 SG-208 VT-3 Vf"3 VT-3 VT"3 VT"3 VT-3 VT-3
.VT-3 VT-3 10 10 One Two fhree One Two
'three One Two Three One Two Throe One Two Three One Two Three Ono Two Three One Two Three One Two Three 100 100 100 100 100 33 55 100 20 70 100 33 67 100 20 70 100 100 100 100 100 100 100 REQUEST FOR BELIEF
//1 IL 3 INCLUDES EXAM ITEMS IDEHTI-I ED, ~ AS APPLI" CABLE.
%%HDE IAETIIOD =
ItICLUDES VT-II EXAthS, WIEnE Ar-
'LICABLE.
PV41947CE Aev. 3/86
~-
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ANPP ASME CLASS 2 2-I WF TA8LE PAGE DF ASME ITEM NO.
ZONEiCOMPONENT OR SYSTEM IDENTIFICATION DESCAIPTION, LINE No. ~ OA SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PEAIOD RUNNING REMARKS AND RELIEF REOUESTS F'I 10 F120 F130 Fl>>0 F210 F220 F230 F2>>0 F310 F320 F330 F3>>0 F350 CONTINUED 50-Ilain Steam SG-2 90 MSSS 51-Atmosphere Dump SG-1 52-Atmosphere Dump SG-2 53-Steam to Aux.
Feedwater System 5>>-Feedwater SG-1 Inside Cont 55-feedwater SG-2 Inside Cont 56-I'eedwa te r SG-1 MSSS 57-Feedwater SG-2 I"ISSS 58-Aux. and Down-comer Feedwater SG-1 Inside Cont 59-Aux. and Down-comer Feedwater SG-2 Inside Cont 60-Downcomer Feed-water SG-I IISSS 61-Downcomer Feed-water SG-2 MSSS Supports Supports Supports Supports Supports Suppcrts Supports Suppc rts Supports Suppc rts Suppc rts Supports SG-209 SG-59 SG-70 SG-84 SG-103 SG"81 SG-83 SG"2 SG-13 SG-5 SG-14 SG-202 SG-205 SG-8 AF->>
SG-11 Af-6 SG-200 SG-203 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 19 18 22 6
6 10 One Two Throe One Two Three One Two Three One Two Three One Two Three One Two Three One Two Three One Two Throe One Two Three One Two Three One Two Three Ono Two Three 100 50 100
.. 100 100 50 75 100 31 63 100 38 78 100 100 100 100 32 6>>
100 27 54 100 33 33 100 66 100 PV419%7CE Aev,3I86
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAh'IIIIATION
~~SUMMARY~~
AN PP ASME CLASS 2 2-I WF TABLE 4
PAGE OF ASME ITEM NO.
ZONE+COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS F110 F120 F130 F140 F210 F220 F230 F2IIO F310 F320 F330 F340 F350 COIIT I IIUED 62-Aux.
Feedwater SG-1 NSSS 63-Aux.
Feedwa te r SG-3 FISSS 64-Blowdown SG-1 Inside Cont.
Suppc rts Suppc rts Suppcrts AF-4 Af-18 AF-6 AF-16 SG-39 SG-53 VT-3 V'I-3 VT-3 5
37 2
2 1
12 13 12 One Two Three One Two Three One Two Three 25 50 100 40 80 100 32 67 100 65-Blowdown SG-2 Inside Cont.
68-Regenerative lleat Exchanger 70-LPSI Pump Suction Loop 1
71-LPS I Pump Suction Loop 2 72-LPSI Pump Discharge Loop 1
73-LPSI Pump Discharge Loop 2 74-SD Cooling Ilx Outlet Loop 1
Suppc rts Suppcrts Supports Suppc rts Suppc rts Supports Supports SG-48 SG-52 SN-79313 S I-241 SI-369 SI-239 SI-2 SI-67 S I -194 SI-368 S I-173 SI-36 SI-34 Sl-308 SI-87 Sl-78 S I -129 S I -123 SI-119 SI "70 SI-69 Sl-90 S I-87 VT-3 VT-3 VT-3 VT-3 VT-3
.VT-3 VT-3 37 32 33 10' 5'6 12 12 13 9
9 14 9
9 15 8
8 10 One TWO Throe One Two Three One Two Three One Two Three One Two Three One Two Three One Two Three 32 65 100 50 100 28 36 100 27 56 100 40 80 100 17 56 100 31 62 100 "INCLUDES 3
PUMP SUPPORTS PV419O/CE Aov. 3/66
~
-i
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMIIIATION
~~SUMMARY~~
ANPP ASME CLASS 2 TABLE PAGE 2-I WF 4
pf 4 ASME ITEM NO.
ZONEQCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS F110 F120 F130 F140 F210 F220 F230 F240 F310 F320 f330 f340 F350 CONTINUFD 75-SD Cooling IIx Outlet Loop 2 76-I.PSI lleader lA 77-LPSI lleader 10 78-LPSI lleader 2A 79-LPSI Ileader 28 80-Containment S p ray Pump Suction Loop 1
81-Containment Spray Pump Suction Loop 2 82-Containment Spray Discharge Loop 1
83-Containment Spray Discharge Loop 2 84-Containment Sump Suction Loop 1
85-Containment Sump S<<ction Loop 2 Supports Supports Supp<lrts Supports Supports Supports Supports Supports Supports Supports Supports SI-72 SI "134 SI 135 SI "129 S l-70 SI-202 SI "71 S I -220 S I-72 Sl-155 SI-73 Sl-174 SI-9 SI-34 SI-33 Sl-79 S I -82 Si-89 S I -'I 19 Sl-134 SI-147 Sl-7 Sl-30 VT-3 VT-3 VT-3 VT-3 VT-3 VT"3 VT-3 VT-3 VT"3 VT-3 VT-3 30 21 28 15 13'7 21 8
9 13 9
9 10 One Two Three One Two Three One Two Three One Two Three One Two Three One Two lhree One Two Three One Two Three One Two Three Orle Two Three One Two Three 27 57 100 29 62 100 32 64 100 27 60 100 23 62 100 100 100 100 43 100 38 62 100 29 62 100 100 100 100
+ I NCLUDES 3
PUMP SUPPORTS PVi1947CE ROV. 3/86
SECTION 6:0---'"--'SMH CLASS 3 EXA~t1INATION
~~SUMMARY~~
6-1
~-
INDEX TABLE EXING CATEGORY 3-1 D-A, D-B, Systems in support of reactor shutdown function Systems in support of emergency core cooling, containment heat removal, atmosphere
cleanup, and reactor residual heat removal Systems in support of residual heat removal from spent fuel storage pool 3-IWF F-A, F-B, F-C, Plate and shell type supports Linear type supports Component standard supports 6-2
~~PALO VERDE NUCLEAR GENI.:RATING STATION 10 YEAR INTERVALEXAMINATION~~
~~SUMMARY~~
ANPP ASME CLASS 3 3-1 TABLE PAGE ASME ITEM NO.
ZONE+COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING RELIARKSAND RELIEF REOUESTS D120 thru D160 D220 thru D260 0320 thru 0360 ExwthlNnTION CATECORY 0-A SYSII IIS Itt SUP-PoltI'f REACTott SIIU fDO'IIII FUIICT I ON ntll)
EXAMI tlATI ott CATFGORY D-II SYS I I tIS I tl SUP-POR f Of EHI.RGtlECY COIIF. COOI. I tIG CON-J lnltIHFN1'H'AI'E-
<<oynl n1<<ospttt:IIE
(:I.f:AtlUP ntlo III.AC-R TOII !IfSIDUAI HEAT Rf.tlovnl.
- ntln fxntws ttnTIorl t.nTFGORY O-C SYSI fHS I N SUP-
. ~
i'oti r or 'Iti:st ounce.
III.AI ltl:t10VAI,FltOtl Sl'L'N I' UE.I S I ORAGE POOL ASME CLASS THE ISI I30 SECTION 10 3
SYSTEMS AR IDENTIFIED ON INDARY DRAWltl S CONf INED IN 0.
REQUEST fOR RELIEF
//1 Bc //3 Al I Class 3 Systems IExcept Auxiliary feedwater)
Auxiliary Feedwater Systems Integra I ly We I dad Atta "tlments tntegra I ly Weld d
Atta"hments All lines greater than II nollll na I pipo size Atl lines YT-3 VT-3 All
~
Al I 100$
100$
Each in-spection Intorva I Each in-spection Interva I 100$
100$
PVi1947CE Rev. 3/86
0'
AMP P PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
ASME Cl ASS 3 3-1 TABLE PAGE ASME ITEM NO.
ZONE+COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 0110 D210 0310 D110 D210 0310 EXAMINATION CATEGORY 0-A~SYSTEllS I N SUP-POIll OF HEACl'OR SHUTDOWN FUII~CTlor At(I)
E)(AMItiAT I Oti CATEGORY 0-13 SYSl I MS IN SUP-PORT Or EMCHGENCY CONF COOI I t(G COII-TAINIIFNT HFAT RE-MOVAL ATMOSPHFRE J
CI.EANIIP AtiD REAC-TOR RFSIDUAL HEAT RFI40VAI AND EXAtlINATlOth CATFGORY D"C SYS I EtlS I N SUP-PORT OF RFS I OUAI.
!IEAT HEtIOVAL FHOI/I SPEtiT FUEL STORAGE POOL SYSTEM INSFRVICE TESTS Pressure Retaining Components SYSTEtl HYDRO-TESTS Pressure Retaining Components Pressure Retaining l3oundary Prcssure Retaining Boundary VT-2 VT-2 Entire Pres-sure Retain-ing Boundary IWA-5000 IWD-5000 Entire Pres-sure Retain-ing Boundary IltA-5000 IWD-5000 100 100 "EACH INSPECT I Oti PER I OD.
EACH INSPECT ION I tiTERVAL.
Pv4194/CE Aov. 3/86
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMlhlATION
~~SUMMARY~~
ANPP ASME CLASS 3 3-IWF TABLE PAGE 1
1 ASME ITEM NO.
ZONEP COMPONENT OR SYSTEM IDENTI'.=ICATION DESCRIPTION LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS F110 F120 F130 F1<<0 F210 F220 F230 F2<<0 F310 F320 F330 F3<<0 F350 EXAII CATEGORY'-A'I.ATEAND SHELL TYPE SUPPORTS Atli)
FXAtl CATEGORY F-B L I tIEAR 'I YPI SUPPORTS AND FXAth CATEGORY F-C A
COtIPOtlENT S'I'ANDARD SUPPOR1S All Class 3 Systems (Except Auxi I iary Feedwa ter)
Auxiliary Feedwater Systems Suppcrt Compcnents Suppc rt Compcnents Al I I ines greater tha tt" nomina I pipe sl7e All lines
~ k<<
VT-3 VT-3 All All 100%
100%
Each I tl spection Inte rva I Each In-spection Interva I
<< I NCLUDES EXAM ITEMS IDENTIFIED, AS APPLI-CABLE'~
""tlDE IRETIIOD INCLUDFS VT-<< EXANS, WIIERE'P-PLICABLE.
100%
REQUEST FOR RELIEF //3 100%
PV41947CE Aev. 3/86
0 O~
\\'
""SECTION 7.0
-"'--'UGiKNTED HIGH ENERGY PIPING 7-1
0
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMIIIATION
~~SUMMARY~~
AN PP ASME CLASS 2 2-AIIE'ABLE PAGE QF ASME ITEM NO.
ZONEvCOMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATI0 N AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 510 511 512 AU('itlEIITEO EXAHINA-AT IONS OF tlltdl ENERGY PIPltlG P I P I NG WE I.I)s 1/?
I N.
tIOH I NAL WAI.I. I HI CKtlESS CIRCIIHFFRFtITIAL AND
>>>> I,0tlG I 1 UO I tIAL WEI.I)s 51-Bypass UV-180 52-Bypass UV-171 Butt Welds II" X.337" Butt Welds II" x
. 337" SG-95-II" SG-100-II"
(>>)
S,Vol (12)
S, Vo I (12) 0 12 0
0 0
12 One Two Three One Two Three 100 100 100
(>>)IOENTI-F IES TIIE tIUthBER OF WELDS TIIAT ARE tlOT ASIDE CLASS-IFIED
>>>>NOtlE 520 521 522 53-Steam to Aux Feedwater PIPING WEI,OS 1/P.
I tt tlOIII tlAI. WAI I TllI CKNESS CIRCUtlf'FRENTIAL AND
>>I.ottr, I1uo ITi~t. WELDs II7-tiain Steam SG-1 270 HSSS II8-Ha in Steam SG-1 90o IRSSS II9-Hain Steam SG-2 2700 Hsss 50-Hain Steam SG-2 90o HSSS Butt Welds 6" x
. II32" Butt Welds Butt Aetds Butt Welds Butt Welds SG-81-6" SG-83-6" SG-206-28" SG-206-12" SG-206"6" SG-207-28" SG-207-1?"
SG-207-6" SG-208-28" SG-208"12" SG-208-6" SG-209-28" SG-?09-12" SG-209-6>>
S, Vo I S, Vo I S, Vo I S, Vo I S,Vol S,Vol S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I 1tl 15 II(1) 2 5
tl(1) 2 ll(1) 2 5
II(1 )
2 5
10 9
10 12 0
0 0
12 0
0 0
12 0
0 12 One Two 1hree One Two Three One Two Three One Two Three One Two Three 35 68 100 100 100 100 100 100 100 100
>>100'g OF AI.L I tlTER-SECTIIIC LONGI1UO-tNAI. WEi.OS WILL OE FXAIIINt0.
PV4194lCE Aev,3186
e 1
II II ll
PALO VERDE NUCLEAR GENERAT(NG STAT(ON 10 YEAR INTERVALEXAM(NATION
~~SUMMARY~~
A lV P P ASME CI.ASS 2 2-AHE TABLE PAGE 0"
ASME ITEM NO.
ZONE0COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENO. ~ OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 521 522 CONTINUED 51-Atmos phe r I c Dump SG-1 52-Atmospheric Dump SG-2 56-feedwater SG-1 I'Isss 57-Fecdwater SG-2 IISSS 60-Downcomcr I'ecd-wator SG-1 HSSS 61-Downcomer Feed-water SG-2 HSSS Butt Welds 12" x.811II" Butt Holds 12" x.811II" Butt Molds Butt Wetds Butt Wclds 8" x.719" Butt Welds Bn y,
719R SG-59" 12" SG-70-12" SG-BII-12" SG-103-12 SG-201-2II" SG-202-21 SG-22II-2II" SG-20II-2II" SG-205-2II" SG-225-2(I" SG-2OO-8" SG-8"8" SG-203-8" SG"11-8" S, Vo I S, Vo I S, Vo I S, Vol S, Vo I S,Vo I S, Vo I S,Vol S,Vol 8, Vo I S, Vo I S, Vo I S, Vo I S, Vo I 11 13 13ll 2
2 (2) 2 2(2)
(8)6-(8) 6 11 13 0
0 0
2II One Two Three One Two Three Ono Two Three Onc Two 1l1ree Ono 1wo Three One Two fhree II6 100 100 100 67 IOO 100 100 6II 100 100 36 100 66-Blowdown SG-1 HSSS 67-Blowdown SG-2 HSSS Butt Welds Butt Molds SG-39-6" SG"II8-6" S, Vo I 2(13)
S, Vo I 2(10)
One Two Three Ono Two Three 60 100 100 50 100 PV4194 IC E Rev. 3/86
~
0'
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
AN PP ASME CLASS 2 2-AHE TABLE PAGE OF ASME ITEM NO.
ZONEo COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PEAIOD RUNNING REMARKS AND RELIEF REQUESTS 530 531 532 Pipe Aranch Cnnnoc-tions Ci rrnrnof'orontia I and "I.onqitudinal Wclds II7-Hain Steam SG-1 270o HSSS II8-Hain Steam SG-1 90o HSSS II9-Ha I n S tea m SG-2 2700 HSSS 50-Hain Steam SG-2 90 HSSS Sweepolets Sweepolets Sweepolets Swoepolots SG-206-28ff SG-207"28<<
SG-208-28<<
SG-209-28<<
S,Vol S, Vo I S, Vo I S,Vol 8(1) 8(1)
Ono Two Three One Two Three One Two Three One Two Throe 100 100 100 100 100 100 100
<<SCIIEOULEO UNDER C5.21 AND C5 ~ 22 PV41941CE Rov. 8/86
SECTION 8.0
~~RHR, ECCS, AND CHR PIPING~~
~~L AN PP PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION~~
~~SUMMARY~~
IRHR, ECCS, end CHR SYSTEMS)
ASME CLASS 2 TABLE PAGE~ OF5 ASME ITEM NO.
ZONE COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINE NO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS-40 YR 10 YR EXAMAMOUNT INSPECTION PERIOD (40 YA) 10 YR REMARKS AND RELIEF REOUESTS C500 510 511 512 Exnx. c*vccccv c-F".
PRESSUAF'ETAItllHG WEI.DS IH PIPIttp PI Pl ttG MFI.DS MALL TH I CKttESS CIRClltlFFAENTIAL AND
<<<< I OHG I TUD I HAI.
MEI.DS NOTE 2 NOTE 1
<<EX TEAt TIIA SEC CIA EXAt ttOTI EXAI T IAt CON WIIF.t EttT Of EXAH IIICD USING SUHHER 197 ION XI 5T I4IN FROt WELD IttTEA IHED.
1:
AH AUG IHATIOtt OF WELDS WILL UNCTlOth WITI PRACTICAL (
NOTE 3 WERE DE-IIE 197ll EDIT OH ADDENDA OF SHE EACII SCHEDU ED ECTION WILL E
ENTED YOLUHE RIC Ilf C I ACUHFER tt-BE PERFOIIHED t H TIIE REQUIRE SUAFA E
EXAHS NOTE IE BULL TIN 79 17) 70 IL 71 LPSI Pump Suction Butt We lds 10" x.250" 6ll x 280<< <<
Butt Welds 16" x.312 Butt Molds 10" x.250 10" x
. 365<<
Butt Welds 12" x.250 SI"369 SI-368 S I -2ll1 S I -19ll S I -173 SI-239 S I-173 SI-2 SI-38 S,Vol S, Yo I S, Vo I S, Yo I S, Vo I S,Vol S, Vo I S,Vol S, Vo I (26) 9 17-(33) 15 16 2
(21) 10 11 (1II) 10ll NOT COH UtIL NOT lip (13) 9 (16) 8 8
(11) 5 6
(7) 5 2
2:
ALL Llt IDEAED HULT SS NOTED 3'UHBER EAR TOTALS.
(3) 1 1
1 (H) 1 2
(3) 1 1
1 (2) 0 1
ES AAE PLE SYSTEHS IN (<<)
ARE One Two Three One Two Three One Two Three One Two Three (100) 8 15 23 (100) 6 13 P5 (100) 9 18 27 (100) 1ll 29
<<1 WELD PER LINE
<<1 WELD PER Lt ttE PV419.01cr Aev 9 86
0 0
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
(RHR, ECCS, end CHR SYSTEMS)
ASME CLASS 2 TABLE PAGE 2-CFR OF5 ASME ITEM NO.
ZONE COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMAMOUNT 10 YR 40 YR INSPECTION PERIOD (40 YR) 10 YR REMARKS AND RELIEF REQUESTS 511 512 CONTINUED 70 IL 71 LPSI Pump Suction (cont'd) 72 8c 73 LPSI Pump Discharge Butt Welds 18n X.312 Butt Molds 16" x.312 14" x 312'utt Welds 20" x.375" Butt Welds 14" x.312 Butt Welds 8" x.322" Butt Welds 1 On x 365n Butt Welds 10" x.365" Butt Welds 10n x.365" Butt Welds 20n X.500" S I -241 S I -194 S I-67 Sl-34 SI-307 SI-308 Sl-307 Sl-308 SI-87 SI-129 SI "87 S I -129 SI-78 SI-123 S I -79 SI-119 S I -78 S I "123 S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S,Vol S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S,Vol S,Vol J
S, Vo I S, Vo I (50) 24 26 (18) 9 9
(20) 10 10 (12) 6 6
(4) 2 2
(26) 14 12 (28) 14 14 (12) 6 6
(8) 3 5
(25) 12 13 (9) 5 4
(10) 5 5
(6) 3 3
(4) 2 2
(14) 7 7
(15) 7 8
(6) 3 3
(4) 2 2
(7) 2 3
3 (3) 1 1
1 (3) 1 1
1 (2) 1 0
1 (2) 2 0
0 (3) 1 1
1 (4) 1 2
1 (2) 1 1
0 (2) 0 1
1 One Two Three One Two Three One Two Three Ono Two Three One Two Three One Two Three One Two Three One Two Three One Two Three (100) 8 20 32
( 100) 11 18 27 (100) 10 20 30 (100) 14 14 29 (100) 50 50 50
( 100) 7 14 21
( 100) 7 20 27
( 100) 14 29 29
( 100) 20 40 ee2 WELDS Pf(I L'INf.
PV4 l9-OICF Rev ai66
0
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
(RHR, ECCS, end CHR SYSTEMS)
ASME CLASS 2 2-CfR TABLE PAGE 3
Of5 ASME ITEM NO.
ZONE COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION.
LINENO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMAMOUNT 10 YR 40YR INSPECTION PERIOD (40 YR) 10 YR REMARKS AND RELIEF REQUESTS 511 512 CONTINUEO 7<<
8c 75 SO Cooling tlx Outlet.
76, 77, 78 8c 79 LPSI Ileaders 1A, 18,2A and 28 77 8c 78 LPSI lleaders 18 and 2A.
80 8c 81 Containment Spray Pump Suction Butt Welds 20" x.500" Butt Welds 16" x.375 Butt Welds
)Of x.365 Butt Welds 6" x.280" Butt Wolds 1<<" x.375" Butt Welds 10" x.365u Butt Welds 12 x
375N Butt Welds 10" x.365" Butt Wolds 1>>" x.312" S I"70 S I -72 SI-70 SI-72 S I "89 S I-13<<
SI-131 S I-131 SI-90 SI-135 SI-87 SI-129 SI-70 SI-71 Sl-72 S I-73 SI-71 S I "172 S I "67 S I-3<<
S,Vol S, Vo I S,Vol S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Yo I S, Vo I S, Vo I S, Yo I S, Vo I S,Vol S,Vol S,Vo I S, Vo I S, Vo I S, Vo I S,Vol
(<<8) 27:
21 (8)
I (16).
8 (8),
(21)'0
=:
11 i (38) 22:
16:
(38) 9 8
'5 6
=
(6)
(10) 5 (2<<)
11 11
(<<)
2 2
(8)
(<<)
2 2
(10) 5 5
(19)ll 8
(10) 2 2
2 (3) 1 2
(5) 2 3
(6) 2 2
2 (1) 1 0
0 (2) 1 0
1 (1) 1 0
0 (3) 1 1
1 (5) 1 2
2 (3) 1 1
1 (1) 0 1
(2) 1 0
One Two Three One Two Three One Two
'Ihree One Two Three Ono Two Throe One Two Three One Two Throo One Two Three One Two Throe
( 100) 8 17 25
( 100) 25 25 25 (100) 13 13 25
( 100) 25 25 25
( 100) 10 20 30 (100) 5 15 25
( 100) 10 20 30
( 100) 33 33 (100) 20
<<0
<<0 PVcl9 09CF Acv 3/86
0 0
i
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATION
~~SUMMARY~~
(RHR, ECCS, end CHR SYSTEMS)
ASME CLASS 2 2-CFR TABLE PAGE v
OF~
ASME ITEM NO.
ZONE COMPONENT OR SYSTEM IDENTIFICATION DESCRIPTION, LINENO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS EXAMAMOUNT 10 YR 40 YR INSPECTION PERIOD (40 YR) 10 YR 4P REMARKS AND RELIEF REOUESTS 511 512 520 521 522 CONTINUED 80 8c 81 Containment Spray Pump Suction 82 IL 83 Containment Sp ray Pump Discharge 84 IL 85 Containment Sump Suction PIPING WEI.DS OVER 1
P.
IN.
NOIIINAL WALI,TIIICKttFSS I;IIICtttff:fltFtt I IAL ANO
<<LOIIGITUDIIIALWELDS
('75 Category C-F) 70 8c 71 LPSI Pump Suction Butt Welds 18" x
. 312" Butt Welds 1ff<<x
~ 3121I Butt Wolds 10" x.365" 8" x.322 Butt Welds 10" x.365" Butt Welds 8" x.322" Butt Welds 2ff" x
. 375" Butt Welds 16" x 1.592" SI-9 SI-33 SI-9 SI-33 S I -79 S I-119 SI-82,89 SI-13ff, 147 SI-89 S I-134 Sl-7 S 1-30 S I-241 Sl-194 S, Vo I S,Vol S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S,Vol S, Vo I S, Vo I S,Vol S,Vol S, Vo I S,Vol (17) 9 (8),
ff ff (61) 31 30 (63) 3528-A (4) 2 l 2
I (8) 4 4
(4) 2 2'9) 5 tf (4) 2 2
(31) 16 15 (32) 18lff (2) 1 1
(4) 2 2
(2) 1 1
(3) 1 1
1 (1) 0 0
1 (8) 3 3
3 (8) 2 3
3 (I) 0 1
0 (1) 0 0
1 (0) 0 0
0 One T'wo Three One Two Three One Two Tiff'ee One Two Three One Two Throo One Two Three One Two Three
( 100) 25
( 100)
"2.5T MIN.
FROM EACtl SCIIEOULEO CIRC.
WELD ItlTERSEC-TION WILL BE EXAMINED.
(100) 11 22 33
, (100) 25
( 100) 10 19 "IIICLUOEic 1 29 WELD PER X LINE (100) 6 16 25
( 100) 50 50 PV4 l947CF Aev. 3/66
t
~
PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVALEXAMINATIONSUI'JIMARY A N P P (RHR,ECCS,<<FndCHR SYSTEMS)
ASME CLASS 2 2-CFR TABLE PAGE OF ASME ITEM NO.
520 521 522 ZONE COMPONENT OR SYSTEM CntlT I tlUED IDENTIFICATION DESCRIPTION, LINENO., OR SERIAL NO.
NDE METHOD TOTAL ITEMS 40 YR 10 YR EXAMAMOUNT INSPECTION PERIOD (40 YR) 10 YR
<</o REMARKS AND RELIEF REQUESTS 530 531 532 76, 77, 78 8c 79 LPSI Ileaders IA,10,2A and 20 84 8c 85 Containment Sump Suction PI PF.
BRANCH CONtlFC-TIOLIS.
C I RMlfhfEREtlT I AL AND
<<Lortt: I TIInirlAI.WELns 70 8c 71 LPSI Pump Suction 72 8c 73 LPSI Pump 0 i scha rge 74 8c 75 SD Cooling Hx Outlet Butt Welds 1?"
X 1. 125" Butt Welds 12" x 1. 312" Butt Welds 24" x.562" Sweepolets 18" x 12" Sweepolets 20" x 10" Sweepolets 20" x 6" 20<< x 10<<
20" X 1?"
20" x ill" SI-70 IL 202 SI"71 8c 220 SI-72 8c 155 SI-73 8c 17<<
SI-202 SI-2?0 S I-1 rjrj SI-17<<
SI-307 SI-308 SI-2<<l S I -19<<
SI-78 SI-123 SI-70 SI-72 S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I S, Vo I (45)ll 12 12 10 (91),
21 34 21 15 (4) 2 2
(2) 1 1
(4) 2 2
(10) 5 5
-'12) 3 3
3.
3 (2<<)
rj 10
<<5
~
(2)
I 1
(I)
I 0
(2) 1 1
(5) 2 3
(3) 1 1
1 (6) 2 2
2 (1) 0 1
0 (0) 0 0
0 (1) 1 0
0 (2) 1 0
1 One Two 1'llroe One Two Three One T'wo Three One Two Three One Two Three One Two Three (100) 8 17 25
( 100) 8 17 25 (100) jr0 50
( 100)
(100) 50 50 50 (100) 20 20 40
<<2.5T I4III.
FROM EACII WELD INTER-SECTION WILL BE EXAHIIIED.
pv419.0tcF Rev, 3m8
SECTION 9.0 REQUESTS FOR RELIEF 9-1
RELIEF REqUEST INDEX NUHBER DESCRIPTION Hydraulic and mechanical snubbers will be tested in accordance with PVNGS Technical Specifications.
2 ~
Volumetric Examinations of nozzle inside radius sections will be performed only on specified nozzles.
3 0 Insulation will not 'be removed for visual examinations of welded or mechanical attachments.
9-2
RELIEF REQUEST NO.
1 COMPONENT OR ITEM HYDRAULIC AND MECHANICAL SNUBBERS CODE CLASS l
2 3
PROGRAM TABLE 1-IWF 2-IMF 3-IHF CODE ITEM N/A N/A N/A EXAM CATEGORY N/A N/A N A CODE REQUIREMENT Perform inservice functional testing of hydraulic and mechanical snubbers in accordance with IWP-5000.
BASIS A detailed and comprehensive testing program for snubbers is contained in the PVNGS Technical Specificationk ALTERNATE EXAMINATION The requirements for testing Section 4.7.9.
snubbers will be in accordance.,with the PVNGS Technical Specifications, SCHEDULE FOR IMPLEMENTATION First Ten Year Inspection Interval
RELIEF Rl:()UEST NO.
2 COMPONENT OR ITEM i
CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY NOZZLE INSIDE RADIUS SECTIONS PRESSURIZER STEAM GENERATOR STEAM GENERATOR SilUT DONN COOLING iiEAT EXCHANGERS 1
1 2
2 1-3 1-3 1-3 1-3 B3.120 B3.140 C2.22 C2.22 B-D B-D C-B C-B Perform volumetric examination of the nozzle inside radius section.
BASIS The volumetric examinations of the nozzle inside radius sections on the referenced vessels (other than those identified under Alternative Examination) will not be performed.
For nozzles that do not experience a
temperature gradient in a cycling environment that could possibly induce a thermal fatigue mechanism, there is no technical basis for performing these examinations.
The industry has evidence that problems can arise in inner radius areas but they have all been associated with the cyclic temperature gradients, and generally in extremely high cyclic environments.
In addition, the unique geometries, large metal paths, compound angles, etc.,
that have been encountered while performing an ultrasonic examination of the inner radius sections have essentially prevented a cod required or recommended method from being prepared and/or referenced in ASME Sectoin XI.
These examinations also require extremely large amounts of time, effort, expense, and radiation exposure.(expected to be as high as 1 to 4 man REH per nozzle).
ALTERNATE EXAMINATION The volumetric examination will be performed to the maximum extent practical on the steam generator feedwater nozzles (Table 2.2) and on the pressurizer spray nozzle (Table 1-3).
SCNEDULE FOR IMPLEl'iENTATION First Ten Year Interval l
RELIEF REQUEST NO. 3 COMPONENT OR ITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY SUPPORT COMPONENTS INTEGRAL ATTACHMENTS 1
2 3
3 1-IWP 2-IWP 3-IWF 3-1 ALL ITEMS F-A,P"B & P-C P-A,F-B & P-C F-A,P-B & F-C D AsD B & D C CODE REQUIREMENTS I
Perform visual examinations (VT-3) of the mechanical or welded attachments to the pressure retaining component on in-sulated systems.
BASIS The visual examinations of the mechanical or welded attachments will be performed to the extent practical.
The insul-ation will not be removed to perform these examinations.
It has been our experience that any loss of support capabi-lity.or adequate restraint can usually be detected through the examination of uninsulated portions of the support, the accessible portions of the <<ttachments through the insulation gaps, and or the surrounding insulation.
ALTERNATE EXAMINATIONS The mechanical and welded attachments wil be visually examined to the extent practical.
The insulation will be removed from around the support attachment for further examinations whenever the mechanical connections can not be examined or whenever an abnormality is detected.
SCHEDULE FOR IMPLEMENTATION First Ten Year Inspection Interval
l f
SECTION 10.0 ISI BOUNDARY DRAWINGS 10-3,
'1
NOTE:
See ISI Drawings for Unit 1
ISI Program submitted 8-26-85 (Letter
// ANPP-33266-EEVB/KLH).
10-2
4-(
f
)
l

v t e Letter Sequence Other
TAC:62797, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML17299A543, ML17300A258, ML17300A261, ML17300A681, ML17300B108, ML17303A539
MONTHYEAR1986-07-17 [Table View]

ML17300A261

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