ML17313A751

Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3

ML17313A751
Person / Time
Site:	Palo Verde
Issue date:	12/16/1998
From:	Browning R ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17313A750	List: ML17313A749 ML17313A751
References
PROC-981216, NUDOCS 9901210349
Download: ML17313A751 (94)

Text

INSERVICE INSPECTION PROGRAM

SUMMARY

MANUAL PALO VERDE NUCLEAR GENERATING STATION UNIT 3 ARIZONA PUBLIC SERVICE COMPANY P.O.

Box 52034

Phoenix, AZ 85072-2034 PVNGS 5801 S. Wintersburg Road Wintersburg,Az 85354-7529 PREPARED BY:

PREPARED BY:

REVIEWED BY:

ATE:

3 DATE:

DATE:

ANII CONCURRENCE:

DATE:

APPROVAL BY ENGINEERING DEPARTMENT LEADER:

DATE: /2 /0 Pg COMMERCIAL SERVICE DATE: 01/08/88 PROGRAM NO: ISI-3 REVISION NO:

2 DATE:

12-15-98 score.<03'C9 ceo~'i'X '. ~'.,','." '

PDR

~ 'ADQCK 05000530

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PDR' P

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Cover BKZL'UQH ii and iii 1-1 thru 1-4 1-5 1-6 and 1-7 4-1 and 4-2 Table 1-1 page 1 of 2 1-1 page 2 of 2 1-2 page 1 and 2 of 2 1-3 page 1 of 2.

1-3 page 2 of 2'-5 page 1 of 2 1-5 page 2 of 2 1-6 page 1 of 3

1-6 page 2 and 3 of 3 1-7 page 1 of 4 1-7 page 2 thru 4 of 4 1-8 1-9 page 1 thru 3 of 5

1-9 page 4 and 5 of 5 1-10 1-3,2 page:1 of ";2 1-12 page 2 of 2

1-13 1-14 1-15 1-16 1-XWF page 1 of 3, 1-XWF page 2 and 3 of 3

1-RCP REV.

2 12-15-98

5-1 and 5-2 Table 2-1 page 1 thru 2 of 3

2-1 page 3 of 3 Table 2-2 page 1

2-2 page 2

2-3 page 1

2-3 page 2

2-3 page 4

2-4 of 2

of 2

of 4 and 3 of 4 of 4 2-5 page 1 thru 3 of 4

2-5 page 4 of 4

2-6 2-7 2-IWF page 1,3, and 4 of 6

2-IWF page 2,5, and 6 of 6

6-1 and 6-2 Table 3-1 page 1 of 2

3-1 page 2 of 2 3-IWF 4

0 Table 2-AHE page 1 and 3 of 3

2-AHE page 2 of 3

8-1 Table 9-1 9-2 2-CFR page 1 and 2 of 6

2-CFR page 3 of 6

2-CFR page 4 thru 6 of 6

9-3 thru 9-7 9-8, 9-9 and 9-9A 9-10 9-11 thru 9-22 10-1 10-2 11-1 thru 11-4 Zone Drawings (see Dwg)

REV.

2 12-15-98

0

'h

, 'Qgj:i

3

~ 10 KZHHXQHR The exemption criteria j.dentified in the 1980 Edition through and including the Winter 1981 Addenda of ASME Section XI was utilized for all ASME 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 10 CFR 50.55a requires the 1974 Edition through and including the 1975 Summer Addenda be utilized. It was concluded after a detailed review that the exemption criteria identified in the Winter 1981 Addenda was 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 components.

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.

3.11 CQDF~BSZN ASME Section XI Code Case acceptability will be based on Regulatory Guide 1.147.In addition, Code Case N-416-1 was approved for use in an SER attached to NRC letter addressees.

to Mg.

W. L. Stewart, dated March 16, 1995.

g '

1-5 REV.

2 12-15-98

(

0 e

I'

A0Q PALOVERDENUCLEARGENERATINGSTATION L k3 10 YEARINTERVAL-EXAMINATIONSUMNIARY ASMKCLASS I TABLE I I PAGE I

OF 2 AShfE ITEhf NO.-

B 100 ZOibE~hfPONENP ORSYSIHrf IDENTIFICATIOiN DES CRIPTIOiI LINENO., OR SERIALNO.

NDE hfETIIO TOTAL ITEMS EXAMINATION AhfOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEFREQUESTS 110lll 112 120 121 I-Reactor Vessel I-Rextori Vessel hfEEininleAL I-Reactor Vessel Bonom Head 2-Closure Head Butt Welds Butt Welds None Butt Weld Butt Weld SN 65173 SN 65173 SN 65173 SN 65173 Vol Vol Vol Vol 3 aa 9 a ~

33%

33%

34%

Onc Two Ihfee 0

0 100 0

0 100 0

0 100 33 66 100 Note Request for Relief lt 13 BrlrBEEL EI2dQZEL2.

EXAMINE ENTIRE ACCESSIBLE LENGTH I-Reactor Vessel Bun Weld SN 65173 Vol 50%

0%

100%

One Trro Three a EXAhlFROM FLANGE hlATING SVRFACF Butt Weld SN 65173 Vol, S 33%

33%

34%

One Tsro Three 33 66 100

'AIIIOhIATED EXAhfCORE BARREL EEhfOZEn REV. 2 12-15-98

I 0

l%

A~Q PALO VERDENUCLEARGENERATINGSI'ATION A M IOYEARINTERVAL-EXAMINATIONSVMMIARY ASME CLASS 1 TABLE I 2 FAGP 1

GF 2 ASME ITEM NO.

ZOiiE~hIPOi~ORSYSIEM IDENTIFICATION DESCRIPTION LINENOOR NDE TOTAL SERIALNO.

METHOD ITEMS E)GlhHNATION AhIOUNT INSPECTION PERIOD RUNNING REMARKSAND RELIEF REQUESTS B 200 210 211 212 5-Pressurizer Shell to bonom Head

5. Pressurizer Shell to Top Head Bun Weld Butt Weld None None None SN 65373 SN 65373 Vol Vol 33%

33%

34%

33%

33%

34%

Onc 7wo Three One 7FFo Three 33 66 100 33 66 100

~I FOOT hllN.

. OF EACH iLONGIIlJDINAL lVELDTHAT

'- INIERSECIS THESCHED-ULED CIRC.

lVELDSWILL BE EXAMINED.

230 231 3-Steam Generator I 4-Steam Generator 2 Butt Welds Butt Welds SN 65273-1 SN 65273-2 Vol Vol I

I I

F ~

I I

~ F One 7wo Thrcc Onc 7FFO 1hrec 33 67 100 33 67 100 G'STAY-CYLINDER EXAMS GFSTAY CYLINDER EXAMS REV; 2 12-15-98

'l 4

0 e

C ii

~

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PALOVERDENUCLIttRGENERATINGSTATION J. W 10YEARINTERVAL-EXAMINATION

SUMMARY

ASMKCLASS 1 TABLE 1-2 PAGE 2

OF 2

ASME ITEM NO.

ZONE'COhIPONENTORSYSIEM IDENTIFICATION DESCRIPTION LINENO., OR SERIALNO.

NDE TOTAL hIETHOD ITEMS EXAMINATION AhIOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS B-Steam Generator I 4-Steam Generator 2 Butt tlVelds Butt tVclds SN 65273-1 SN 65273-2 Vol Vol One 7ato IllfCC Onc 7wo IllfCC 33 50 100 83 100 MIILTIPLEVESSELS PERCENTAGES COMBINED.

3. Steam Generator I 4-Steam Generator 2 Butt iVelds Butt iVelds SN 65273-1 SN 65273-2 Vol Vol I

0 I

0 I

I One 7wo lllrcc One 7wo Ttucc 50 50 100 50 100

<<STAY-CYUNDER EXAMS 250 251 252 253 260 None None None None None REV. 2 12-15-98

0 0

A PALOVERDENUCLEARGENERATINGSTATION IOYFARINTERVAL-EXAMINATION

SUMMARY

ASME CLASS 1 TABLE 1-6 PAGE~GF~

ASME ITEM NO.

ZOiIE~hIPONENTOR SYSTEM IDENTIFICATION DESCRIPI'ION LINENO., OR "

NDE TOTAL SERIALNO.

hIETHOD ITEMS EXAMINATION AhIOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESIS 690 6100 None None 6110 MtV SIIEEK None None 6120 6130 None None 6140 6150 6160 IKEY

~T ILOI'ER85252RK None None None 6170 6180 16 Reactor Coolant Pump IA 17 Reactor Coohnt Pump IB IS.Reactor Coolant Pump 2A 19.Reactor Coolant Pump 2B None FhnSe Studs HanSe Studs HanSc Studs 4.33" x 3257" 4.33" x 32.87" 4.33" x 3287" 4.33" x 32.87" Vol'ol'ol'ol'6 16 16 16 One 7ppo IhfCc One 7PPO

'IlltCC One 7PPO ThfCc One 7wo Three 31 62 100 31 62 100 31 62 100 31 62 100 FA SUPPLEMENTAL VTEXAMtVILLBE PERFORMED 100% PE REFUELING OUTAGE INCONIUNCIION lVIIHEXAMCAT. B.P (SEE IEIN80-27)

EFSUPPLEMENIED BY VISUAL(EACH REMOVAL)ANDSUR.

FACE (AT5 YEAR INTERVALS)EXAMS WHEN REMOVED (SEE IEB 82-02)

REV. 2 12-15-98

0

A PALOVERDENUCIL~GENERATINGSTATION 10 YEARINTERVAL-EXAIVIINATION

SUMMARY

ASME CLASS 1 TABLE 1-6 PAGE~GF~

ASME ITEM NO.

ZOiIE'COiiOOANEN1'ORSYSIEM IDENTIFICATION DESCRIPTION LINENO., OR NDE TOTAL SERIALNO.

METHOD ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING fo REMARKSAND RELIEF REQUESTS 6190 Note Rctiuest for

-RciicfSt 14 16, 17, 18 and 19-Reactor Coohnt Pumps IA,IB,2A,2B E8SHERS"

,16 Reactor Coohnt Pump IA 17-Reactor Coohnt Pump IB 18-Reactor Coolant Pump 2A 19-Reactor Coohnt Pump 2B

': Range As; Sutfacc I

Nuts ti'G Clamping Ring Nuts tL Clamping Ring Nuts dc Clamping Ring Nuts dc Clamping Ring CASING SN IA-1259 IB-1261 2A - 1260 2B - 1262 4528" x 7.283" 4528" x 7.283" 4528" x 7.283" 4528" x 7.283" VT-I VT-I

! 16 per

'ump 16 16 16 16 One TFPO 1lllec Onc TFPO iiirec Onc TWO Ilircc One Two llircc One 7PFO lllrec 31 62 100 31 62 100 31 62 100 31 6?.

100

'100% EXAhlWHEN DISASSEMBLED ITHERE ARE NO

, BUSHINGS INTHE PUMP FLANGES)

<<<<THE CLAMPING RING WILLBE EXAMINED(THERE ARE NO WASHERS) 6210 6220 None None None REV. 2 12-15-98

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PALOVERDENUCLEARGENERATINGSTATION J. W IOYEARINTERVAL-EXAMINATION

SUMMARY

ASME CLASS 1 PAGE I

OF ASME ITEM NO.

ZOiMKOhIPOiifORSYSIKM IDENTIFICATION DESCRIPTION LINENO., OR SERIALNO.

NDE METIIOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS B 800

, SIO None NotcRelieffor Requert tt l4 5-Pressurizer Support Skirt SN 65373 S, Vol 33%

33%

34%

One Wo Ttucc 33 66 l00 3-Stem Generator I 4-Steam Generator 2 Support Skirt Support Skirt SN 65273-l SN 65273-2 VoLS Vol, S 33%

34%

33%

a One Two Ttuec One TiNO Ttucc 33'00' hiULTIPLE

VESSELS, EXAhIINATIONS TOTAL100%

SUPPORT SKIRT tVELD IN I STEAM GENERATOR.

None REV. 2 12-15-98

~ ~

~Q PALOVERDENUCLEARGENERATINGSTATION k7 10 YIM,RINTERVAL-EXA1tdINATIONSUMVIARY ASME CLASS 1 TABLE I-9 PAGE I

OF 5

ASME ITEh1 NO.

ZOiIE~hIPOi~ORSYSIEhI IDENTIFICATIOiN DESCRIPTION LINENO OR NDE TOTAL SERIALNO.

METHOD ITEMS EXAhfINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEFREQUESTS B 900 MWLDRIEZIHhYi 910 911 912

6. RCS Primary Piping 20-PZR Surge Une 214D Cooling Loop I 2WD Cooling Loop 2 2341 Loop IA HLI HL2 CL IAtoRCP CL IB to RCP CL2Ato RCP CL2B to RCP CL IAtoRPV CL IB to RPV CL2Ato RPV CL2B to RPV Butt Welds Butt Welds Butt Welds Butt Welds RC-3242" ID RC6342" ID RC.33-30" ID RC-30-30" ID RC-73-30" ID RC-84-30" ID RC 34-30" ID RC-31-30" ID RC-79-30" ID RC-93-30" ID RC 28-12" RC-51-16" Sl-2tth16" RC 68.16" SI-193-16 SI-207-14" SI 203-12" S, Vol S, Vol S, Vol S, Vol S, Vol 62 19 18 18 o r 7

6 9

One Two Tllfee One Trio Tliree One Ttjro Ttuee One Two Ttuee One Trio 11 21 35 9

9 27 11 21 32 11 22 39 17 17 iTHE LESSER OF12" ORI PIPE DIAMEIER LENGTHFROhl SCHEDULED CIRC tVELDINIERSECIION WILLBE EXAMINED AUIOhIATEDEXAM OF NOZZLETO EXTENSION AND EXIENSIONTO PIPE iVELDS

• • AdditionslWeld Added Per IN97-19 REV. 2 12-15-98

~,

I

~Q PALOVF<NDENUCLEARGENERATINGSTATION J. k3 10 YEARINTERVAL-EXAMNATION

SUMMARY

ASME CLASS 1 TABLE 1-9 PAGE 2 OF~

AShIE ITEM NO.

ZONE~hiPOi iENTORSYSK&I IDENTIHCATION DES CRIPI'ION LINENO., OR SERIALhO.

NDE TOTAL hIETHOD ITEMS EXAMINATION AhIOUNT INSPECHON PERIOD RUNNING REMARKSAND RELIEF REQUESTS 911 IL 912 24$ 1 Loop IB 2

25$ 1 Loop 2A Buu Welds Butt Weids SI-223-14" Sl-221 ~ 12" SI.160.14",

SI 156 12" S, Vol S, Vol 17 21 0

3 2E ~

2 3

One TWO lllrce One TWO lllfee 0

18 29 10 24 29 O'Additional Weld Added Pcr IN97-19 26 SI Loop 2B 28 d2 29-PZR SPray Loop iB and Combined 31.PZR Safeties Butt Welds Bun Welds Bun iVelds SI-179-14" 81-175-12" RC-184" RC-1-6" RC-3$

RC-5$"

RC.7.6" S, Vol 17 S, Vol S, Vol 15 12 2

I 2FF Onc TWO Ttuec Onc TWO lllfec One TWO 12 18 29 13 18 33 8

25 42 921 36-Letdown Line Dehy Coil 27.PZR Spray Loop IA 28.PZR Spray Loop IB Butt Welds Butt Welds Butt Welds RC.91 ~ 16" RC$2-3" RC-16-3" RC 17-3" RC-18-3" S, Vol 39 36 One TWO Three Onc TWO lllfee One TWO Ttlrec 0

25 25 8

15 26 ll 19 28

'HE LESSER OF 12" OR I PIPE DIAMEIER LENOTHFROM SCHEDVLEDCIRC WELDINIERSECITON WILLBE EXAMINED REV. 2 12-15-98

0, 0'

A PALOVERDENUCU<ARGENERATINGSI'ATION 10 YIBRINTERVAL-EXAMNATION

SUMMARY

ASME CLASS 1 TABLE 1-9 PAGE~GP~

AShIE ITEhI NO.

ZOiiE~hImEN1'ORSYSIKN IDENITFICATION DESCRIPTIOiN LINENO., OR SERIALNO.

NDE TOTAL hIETHOD ITEhIS EXAMINATION AhIOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 30.Aux PZR spfay.

I 32.Drain Line I Loop IA 33-Drain Une Loop IB 34.Drain Une Loop 2A 35-Drain Linc Loop 2B 36 Letdown Unc 37-Chafgin8 Line 38-Drain Une Loop I 39-HPSI Supply Loop I 40 HPSI Supply Loop 2 Butt Wews Butt Welds Butt Welds Butt Welds Butt Welds Butt Welds Butt Welds Butt Welds Butt Welds Butt Welds CHES-2" t CH-520-2" CH-521-2" t RC-60.2" I RC 58-2" RC-96.2" RC-89-2" RC.91-2" CH-5-3" RC.70-2" Sl-248-3" Sl-199-3"

\\ Pi 5

70 36 2

2 0<< ~

5 6

6<< ~

One<<

7wo One 7wo IllfCC One 7wo Three One 7wo ThfCC One 7wo 1Ilfec Onc 7wo Tllrcc One 7wo Ttucc Onc 7wo TllfCC Onc 7wo Tlucc One 7wo Itucc 18 36 36 0

40 40 0

0 40 0

0 40 6

14 26 8

18 28 0

25 25 6

14 25 13 21 29

<<VOLEXAMOF2 WELDS ANDBASE-hiETALDOWN-STREAM OF V431 PER IEB 88418.

• <<AdditionalWeld Added Per IN97-19 REV. 2 12-15-98

I

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~Q PALO VERDENUCLEARGENERATINGSTATION A k7 10 YEARINTERVAL-EXAMINATIONSUMVIARY ASME CLASS 1 PAGE~OF~

ASME ITEM NO.

ZOi IE<<CORIPOiiIENTORSYSTEM IDENTIFICATION DESCRIPTIOiN LINENOOR NDE SERIALNO.

METHOD TOTAL ITEMS EXAhlINATION AMOUNT INSPECTION PERIOD RUNNING REMARKSAND RELIEF REQUESTS B 1000 1010 XPSD Cooling Loop 2 2441 Loop IB 2541 loop 2A 2641 Loop 2B 36.Letdown Line Stanchion Stanchion Stanchion Sl-193-16",

Sl-223-14" SI-160.14" i SI-179-14" R(ASI-16" li.".'.ll:>

it t

I 0<<

One One Tate ITEhl BIO.IO COhlBINED FOR PERCENTAGE

<<SUPPORT DELEIED None 1030 None REV. 2 12-15-98

I

A0Q PALO VERDENUCLEARGENERATINGSTATION L k3 10 YEARINTERVAL-EXAMNATION

SUMMARY

ASME CLASS 1 TABLE 1-12 PAGE P GF~

ASME ITEM NO.

ZOiqEKOhIPOiKKKORSYSTEM IDENTIFICATION DESCRIPTION LINENO., OR SERIALNO.

NDE METEIOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF RE(}UESTS 1210 16 RC Pump IA 17.RC Pump IB 18-RC Pump 2A 19-RC Pump 2B ZSIZK IIQD~tELDR Internal Surfaces None 1259 1261 1260 1262 Examine thc Internal Surfaces in I Pump

<<BYTHE END OF

'IHEINTERVAL No(c Request for Relief Sr 14 Borg Warner Gate Valves UtilizingForged Consuuction UV-651 UV.653 UV-652 UV-654 UV-634 UV-644 UV-614 UV-624 RC-51-16" SI-240.16" RC-68-16" SI.193-16" SI-207-14" SI-223.14" SI-160-14" SI-179-14" Vol Exanunc the lVeld in I Valve 100

<<BYTHE END OF THE INTERVAL REV. 2 12-15-98

0 II 0

A DQ PALOVERDENUCLEARGENERATINGSTATION J. k3 10 YEARINTERVAL-EXAjIdINATION

SUMMARY

ASME CLASS 1 TABLE PAGE I GF~

ASME ITEM NO.

ZONEKOhIPOiifORSYSIKM IDENTIFICATION DESCRIPTION LINENO., OR NDE SERIALNO.

METHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND REI IEF REgUESTS Note Rcxlucst for Relief g 11 gc 12 1510 1520 1530 1540 1550 1560 1570 Reactor Vessel Pressurizer Stcam Generators Heat Exchangers Piping Pumps Valves Pressure Retaining Boundary

",:.= i.'r --Enure Pressure retaining boundary IWA-5000 IWB-5000

• EACH REFULING OUTAGE 1511 1521 1531 1541 1551 1561 1571 Reactor Vessel Pressurizer Stcam Generators Heat Exchangers Piping Pumps Valves Pressure Retaining Boundary Entire Pressure retaining boundary IWA-5000 IWB-5000 EE BYTHE END OF THE INIERVAL

• 'E PERFORM WALKDOWNATTHE BEGINNINGOF EACH REFUELING OUTAGE FOR GENERIC LETIER gg415. INADDITION, WALKDOWNREQUIR-MENTS SHALLBE EVALUATEDFOR SHUTDOWNS FOLLOWING OPERATION LONGER THAN APPROXIMATELY6 hIONIHS INhlODE I OR 2.

REV. 2 12-15-98

A~Q PALOVERDENUCIL'ARGENERATINGSTATION W 10YEARINTERVAL-IKAMINATION

SUMMARY

ASME CLASS 1 TABLE PAGE i GF~

ASME ITEM NO.

ZOiEE~hfPOiKffORSYSIEhI IDENTIFICATION DESCRIPTION LINENO., OR NDE SERIALNO.

hIETHOD TOTAL ITEMS EXAMINATION AMOUNT INSPECTION PERIOD 'UNNING Fo REMARKSAND RELIEF REQUESTS F

110 F

120 F

130 F

140 F 210 F 220 F 230 F 210 F 310 F 320 F 330 F 340 F 350 and i

I-Reactor Vessel 3-Steam Generator I 4-Steam Gennator-2 Support Colunms t

Support Skirt Support Skirt SN 65173 SN 65273-1 SN 65273-2 VT-3 VT-3 VT-3 0

GEE 0

4 One 7FFO Thfcc One 7FFO Three One Two Iliiec 0

0 100 100 100 100 100 100 REQUEST FOR RELIEF III&II3 E INCLUDESEXAM IIEhIS IDENIIFIED AS APPLICABLE f

EE NDE hIEIHOD INCLUDESVlA EXAhIS. WHERE APPLICABLE

• 'E REQUEST FOR RELIEFit 6 WAS WIIHDRAWN 5-Pressurizer Support Skirt SN 65373 One 7FPO Three 100 16.Reanor Coolant Pump IA Vntical and Lateral Supports SN 1111-IA VT-3 10 Onc 7PPO

%luce 17-Reactor Coolant Pump IB Vntical and Lateral Supports SN 1111-1 B VT-3 10 One 7FFO Thrcc 18-Reactor Coolant Pump 2A Vnticsl and Lateral Supports SN 1111-2A VT-3 10 One 7PFO 19-Reanor Coolant Pump 2B V<<nicaI and Latnal Supports SN 1111-2B VT-3 10 One 7PFO Three REV. 2 12-15-98

l 0

I i

~Q PALO VERDENUCLEARGEMINATINGSI'ATION J. M 10 YEARINTERVAL-EXAMNATION

SUMMARY

ASMKCLASS 2 TABLE 2-2 FAGE~GF~

ASME ITEM NO.

ZOiiE~hIPONENTOR~I IDENTIFICATION DESCRIPTION LINENO., OR NDE SERIALNO.

METHOD TOTAL ITENIS EKAIillNATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 210 None FC"'el 41-Steam Generator I 42-Steatn Generator 2 Nozzle to Vessel Welds Nozzle to Vessel Welds SN-65273-1 SN-65273-2 S,Vol S,Vol One Two Tlnee One Two Ihrce 29 57 100 INSIDE RA-DIVSON PIP-ING ONLY GREATER THAN 12" DIAMETER MVLTIPLEVESSELS:

PERCENTAGE COM-BINED Note Retlucst for Relief St 10 84-SD Cooling Heat Exchanger I 87-SD Cooling Heat Exchanga 2 Nozzle to Shell Welds Nozzle to Shell Welds SN-18345 SN-18346 S,Vol S,Vol One Two Three One Two Ih!ce 100 MULTIPLE VESSELS PERCENTAGE COMBINED REV. 2 12-15-98

aa g

A53 Q PALOVERDENUCLEARGENERATINGSI'ATION L k3 10 YEARINTERVAL-EXANIINATIONSUMNIARY ASME CLASS 2 TABLE 2-3 PAGE~GF~

ASME ITEM NO.

ZOiIE~iWIPOi&TTOR~I IDENTIFICATION DESCRIPTION LINENO., OR NDE TOTAL SERIALNO.

METIIOD ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKSAND RELIEF REQUESTS 54-Fecdwata SG-1 Inside Cont.

55-Fcedwater SG-2 hside Cont.

6'bAux. Feedwata SG-1 6t-Blowdown SG-1 Imide Cont.

slowdown SG-2 Inside Conn 71-LPSI Room A Discharge 76.CS Room ASuction L

Anadunents Anaduncnts SG402 SG405 AF418 SG-39 SG-53 SOS SG-52 SI-87 SI-9

.- S L

S' EL 4

."S One'-

Two 7llfee One Two 7hfce

~

One'wo Ihfcc One Two IllfeC Onc Two Three One One 100 50 50 100 100 100 43 57 100 Note Request for Relief tt 14 SI SYSIEM O'S COMBINED 77~ Room A Discharge 8MB Room B Discharge 82$ DCHX Room A 83$ DCHXRoom A 86$ DCHXRoom B 88-East Wrap 89-East Wrap Auachments Anachmcnts Attachments Anachments Anachments Attachments Anachments S1-79 SI.119 81-78 SI-70 8147 SI-90 81-72 srin Sl-194 One One REV. 2 12-15-98

0 e

0

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A DQ PALO VERDENUCLEARGENERATINGSTATION J. M 10YEARINTERVAL-EXAMINATIONSUNINIARY ASME CLASS 2 TABLE 2-3 PAGE~OF~

ASME ITEM NO.

ZONE~hIPONENr OR SYSIKKI IDENTIFICATION DESCRIPTION LINENO.,OR NDE TOTAL SERIALhO.

hIETHOD ITEMS EXAhIINATIOiN AMOUNT INSPECTIOiN PERIOD RUNNING REMARKSAND RELIEF REQUESTS Q?HIIHUED 9 I.West Wrap 92-West Wrap 93-West Wrap 94$ 1 A th SS'5$

1 B tL SS'6$

1 LPSI IA 99$ 1 LPSI 2B IOO-SI LPSI A Attachments Attachments Attachments Atachmcnts Auachments Attachments SI-70 S1-239 SI-24I SI49 SI-70 SI-194 SI-202 SI-174 Sl-7 SI-369 One Onc Two ltvo One Two 101-SI LPSI B Total Safety Injection SI-30 10 9

11 Onc Two Ihfcc 33 63 100 AITACEhIIRKR 72-LPSI Pump Loop I 7S.LPSI Pump Loop 2 7S-Containment Spray Pump Loop I Anachment Lugs Attachment Lugs Attachment Lugs SN OS76-44 SN OS7645 SN OS76-46 One Two Ihicc One Two Three 66 100 100 33 100 66 100 100 REV. 2 12-15-98

I Up

A0Q PALO VERDENUCLEARGENERATINGSTATION L M 10YEARINTERVAL-EXANIINATIONSUMIVIARY ASME CLASS 2 TABLE 2-7 PAGE~OP~

ASME ITEM NO.

ZOAAIE'ECOhIPOA'IffORSYSIKhI IDENTIFICATION DESCRIPTION LINENO., OR SERIALNO.

NDE TOTAL METHOD ITEMS EXAMINATIOiN AMOUNT INSPECTION PERIOD RUNNING REMARKSAND RELIEF REQUESTS

<< ~ <<

710 730 750 770 Pressure Vessels Piping Pumps Valves Pressure Retaining Boundry Entire Pres-sure retain ing boundly IWA-5000 IWC 5000

• EACH INSPECIION PERIOD 720 740 760 780 Pressure Vessels Piping Pumps Valves Pressure Retaining Boundry Entire Pres-sure retain ing boundry IWA-5000 IWC.5000

<<'EACH INSPECIION INIERVAL

<<<<<<REQUEST FOR RELIEFg 7 dc tr II REV. 2 12-15-98

0 0,

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II

0Q PALOVERDENUCLEARGENERATINGSI'ATION L k3 10YEARINTERVAL-EXAMINATIONSUMVIARY ASME CLASS 2 TABLE 2-DVF FAG~OF~

ASME ITEM NO.

ZOiiEKOhIPONEN1'OR~1 IDENTIFICATION DESCRIPTIOiN LINENOOR NDE TOTAL SERIALhO.

hIETIIOD ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REhIARKS AND RELIEF REQUESTS F110 F120 F130 F140 F210 F220 F230 F240 H10 H20 H30 F340 H50 92ZGEUED 50-hfain Steam SG-2 917'lSSS 51-Aunosphae Dump SG-1 52-Atmosphere Dump SG-2<.,

53-Steam to Aux.

Feedwater System 54.Fcedwater SG-1 Inside Cont.

55 Feedwater SG.2 Inside Cont.

56-Feedwatcr SG-1 hlSSS.

57-Fcedwater SG-2 hlSSS 58-Aux. and Down-coma Fmlwata SG.1 Inside Cont.

Supports Supports Supports Supports Supports Supports Supports 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 AF4 VT-3 VT-3 VT-3 Vl'-3 Vl'-3 VI'-3 2

19 19

~ 'P One Two three One Two three One Two lhfec One Two 1llfee Onc Two lhfcC Onc Two Three Onc Trro

'lhfcc 100 50 100 100 100 50 75 100 30 65 100 42 79 100 100 100 100 32 64 100 59-Aux. and Down-coma Feedwata SG-2 Inside Cont.

60.Downcomer Fccd-wata SG-1 hlSSS 61-Downcomer Feed-wata SG-2 hlSSS Supports Supports Supports SG-11 AF6 SG-200 SG-203 Vl'-3 22 6

6 10 Onc Two three 27 55 100 33 33 100 66 100

I

": req I

~I I'w N

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A D Q PALO VERDE NUCLEARGENERATINGSTATION X M 10YEARINTERVAL-EXAMNATIONSUMNIARY ASME CLASS 2 TABLE 2-IWF PAGE~GF~

ASME ITEM NO.

ZOiiEKOitIPOiKNTORSYSIEM IDENTIFICATION DESCRIPTION LINENO., OR SERIALNO.

TOTAL METHOD ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMIIARKSAND RELIEF RE(}UESIS F110 F120 F130 F140 F210 F220 F230 F240 F310 H20 H40 F350 CQHIIHUEQ 88-Safety Injec6ion 89-Safety Injection 90-Safety Injection 91-Safety Injection 92$ afety Injection 93$ afety Injection 94$ afety Injection Supports Supports

'i' Supports i

'i Supports Supports Supports Supports SI-72 SI-73 SI-173 SI-194 SI-134 SI-70 SI.71 SI-2 SI-239 SI-241 81.89 SI-70 SI-89 SI-24 I VT-3 VT-3 14 10 12 15 One IllfCC One IllfCC One Two 7tlfee One Two 7hfCC Two ThfCC One TWO Illrcc 95$ afety Injection 96.LPSI IA 97-LPSI IB 98.LPSI 2A 99-LPSI 2B Supports Supports Supports Supports SI-72

$1-134 SI-194 SI-202

$1-220 SI-155 SI-174 VT-3 VT-3 18 18 10 6

10 2

10 7

10 One TWO 1Iifec One TWO 1ilfee One TWO

%luce Onc Two REV. 2 12-15-98

tt 0,

l h

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0

'I

)

A0Q PALOVERDENUCLEARGENERATINGSTATION L M 10YEARINIKRVAL-XXAMINATION

SUMMARY

ASMKCLASS 2 TABLE 2-IWF PAGE~OF~

ASME ITEhI NO.

ZONE~hlPONENTOR SYSIEhf IDENTIFICATION DESCRIPTION I.INENO OR NDE TOTAI SERIALNO.

METHOD ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REhIARKS AND RELIEF REQUEFIS F110 F120 F130 F140 F210 F220 F230 F240 F310 H20 F330 F340 HSO CQHIIHUEQ 100-IPSI ASuction IOI-LPSIB Suction SI SYSTEMS ZONES (70-101)

TOTALS Suppotts Suppotts SI-7 SI-24I SI-369 SI-30 SI-194 SI-368 a

.GVT-3 79 87 109 One Two One TEto Thfee 29 60 100 REV. 2 12-15-98

I J

II 0

0

A0Q PALOVI%DENUCLEARGENERATINGSTATION J. W 10YPARINTERVAL-EXAMINATIONSUMNIARY ASMKCLASS 3 PAGE~GP~

ASME ITEM NO.

ZONEKOiiIPOA~ORSYSTEM IDENTIFICATION DESCRIPTIOi I LINENO., OR SERIALNO.

METIIOD TOTAL ITEMS EXAMINATION AMOUNT INSPECI'ION PERIOD RUNNING REMARKSAND RELIEF REQUESTS DIIO D210 D310 TEST 144 Pressure Retaining Components Prcssure Retaining Bomxhy Entire Pres-sure Retain-ing Boundry IWA-5000 IWD-5000 EEACH INSPECIION PERIOD.

D110 D210 D310 Pressure Retaining Components Pressure Retaining Bomxhy Entire Pres-sure Retain-ing Boundry 100 EPEACH INSPECIION INTERVAL E"REQUEST FOR RELIEF g7,8, 4 ll

( 0 8 withdrawn )

REV. 2 12-15-98

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'I I

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A0Q PALOVERDENUCLEARGENERATINGSI'ATION L. k2 10YEARINTERVAL-EXAlIdINATION

SUMMARY

ASME CLASS 3 PAGF I

OF i

AShfE ITEhf NO.

ZOiiE~hfPOi4ENI'ORSYSIEM IDENTIFICATION DESCRIPTION LINENO., OR SERIALNO.

NDE MEI'HOD TOTAL ITEhfS EXAhfINATIOirI AMOUNT INSPECTION PERIOD RUNNING REhfARKS AND Io RELIEF REQUESTS FIIO F120 F130 F140 F210

~

F220

F230,

~

~

F240 HIO H20; H30 H40 F350 AllChss 3 Systems i i (Except Auxiliary Feed wata)

AuxiliaryFeedwater Systems Support Components Support Components Alllines greata than 4" nominal pipe size Alllines VT-3 All All 100%

Each In-specdon Interval Each In-spection Intaval GINCLVDES EXAMITEhfS IDENIIFIED, AS APPU-CABLE o'NDE MEIHOD INCLUDES VT4 EXAMS,r WHERE APP-LICABLE REQVEST FOR RELIEFd I, 3, rL 14 REV. 2 12-15-98

0 t

PALOVERDENUCLEARGENERATINGSTATION 10 YEARINTERVAL-IKAMNATIONSUNIMARY gSMK CI,gss g (RHR, ECCS, and CHR SYSTEMS)

TABLE 2 CFR PAGE 3

OF 6

ASME ITEM NO.

ZOiiEKOhIPOiNEYfOR SYSIEhI IDENTIFICATION DESCRIPTION LINENO., OR SERIALNO.

NDE METHOD TOTAL ITEMS 40 YR 10 YR EXAMAh(OUNT INSPECTION PERIOD (40 YR) 10 YR REMARKS AND RELIEF RE(}

511 512-88 dc 91 Safety injection Mtand West Wraps 89 &,92 Shutdown Cooling Suction East and West Wraps Butt Welds

~

10" x 0.365" 12" x 0.375" 20" x0~"

Butt Welds 10" x 0.25ty'10" x 0365" SI-70 SI-72 SI-172 SI-71 Sr-72 Sl-73 SI.70 SI-71

$1-72 Sl-70 Sl-173 Sl-239 S,Vol S,Vol S,Vol S,Vol S,Vol S,Vol S,Vol S,Vol S,Vol S,Vol S.Vol S,Vol 14 14 (52) 4 2

17 6

9 8

(64) 11 10 7

7 (16) 2,I (33) 6 5

One Two

%%fee "One Weld per line 12" x 0.250" 16" x 0.312" 18" x 0.312" SI-38

$ 1-2 Sl-194 Sl-241 SW73 SI-194 Sl-241 S,Vol S,Vol S,Vol S,Vol S,Vol S,Vol S,Vol 4

10 8ll 2

REV. 2 12-15-98

RELIEF REQUEST INDEX DESCRIPTION Hydraulic and Mechanical Snubbers willbe tested in'accordance with PVNGS Technical Specifications.

Withdrawn Insulation willnot be removed for visual examinations or welded or mechanical attachments.

Level IIIPersonnel willbe recertified by examination every 5 years.

Withdrawn Withdrawn Class 2 and 3 Systems Pressure Test (revised)

Withdrawn Steam Generator Handhole Pressure Test Main Steam Nozzle Volumetric Examination Code Case N498-1 Class 1 Pressure Test Boundary Reactor Vessel Shell and,Head Coverage Misc. Code Limited Examinations 9-2 REV. 2 12-15-98

0 0

RELIEF REQUEST NO. I COMPONENT OR ITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY HYDRAULICANDMECHANICALSNUBBERS I-IWF 2-IWF 3-IWF N/A N/A

. N/A N/A N/A N/A Perform inservice functional testing ofhydraulic and mechanical snubbers in accordance with IWF-5000 A detailed and comprehensive testing program for snubbers is contained in the PVNGS Technical Speci fications.

The requirements fortesting snubbers willbe in accordance with the PVNGS Technical Specifications, Section 4.7.9.

First Ten Year Inspection Interval NRC letter dated October 21, 1987, from E.A. Licitra, NRC, to E.E. Van Brunt, Jr., "Inservice Inspection Programs Palo Verde, Unit I, 2, A 3".

0, e

RELIEFREQUEST NO. 2 COMPONENT OR ITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY NOZZLEINSIDERADIUS SECTIONS PRESSURIZER STEAM GENERATOR STEAM GENERATOR SHUT DOWN COOLING HEATEXCHANGERS 1-3 1-3 2-2 2-2 B3.120 B3.140 C2.22 C2.22 B-D B-D C-B C-B

0 0

RELIEF REQUEST NO. 3 COMPONENT OR ITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY SUPPORT COMPONENTS INTEGRALATI'ACHMENTS I-IWF 2-IWF 3-IWF 3-1 ALL ITEMS F-A, F-B &F-C F-A, F-B &F-C F-A, F-B &F-C D-A,D-B&D-D R

R Perform visual examinations (VT-3)ofthe mechanical or welded attachments'to the pressure retaining component on insulated systems.

p ~BI F'he visual examinations ofthe mechanical or welded attachments willbe performed to the extent practical. The insulation willnot be removed to perform these examinations. It has been our experience that any loss ofsupport capability or adequate restraint can usually be detected through the examination ofuninsulated portions of the support, the accessible portions ofthe attachments through the insulation gaps, and or the surrounding insulation.

The mechanical and welded attachments willbe visually examined to the extent practical. The insulation willbe removed from around the support attachment forfurther examinations whenever an abnormality is detected.

First Ten Year Inspection Interval NRC letter dated October 21, 1987, from E.A. Licitra, NRC, to E.E. Van Brunt, Jr., "Inservice Inspection Programs Palo Verde, Unit I, 2, &3".

tri

0, 0

0

RELIEF REQUEST NO. 4 COMPONENT OR ITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY N/A N/A N/A N/A N/A AllLevel IIIpersonnel shall be recertified by examination on a triennial basis (IWA-2300(a)(1)).

The 1986 Edition ofSection XIand the 1983 Edition thru Summer 1983 Addenda ofASME III(Latest Edition and Addenda referenced in 10 CFR 55.55a) requires Level IIIpersonnel to be recertified every 5 years.

AllLevel IIIpersonnel shall be recertified by examination every 5 years.

S HED F

I P

First Ten Year Inspection Interval LERKMI NRC letter dated October 21, 1987, from E.A. Licitra, NRC, to E.E. Van Brunt, Jr., "Inservice Inspection Programs Palo Verde, Unit 1, 2, &3".

RELIEF REQUEST NO. 5 COMPONENT OR ITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY N/A N/A N/A N/A N/A WITHDRAWN

0 0

0

RELIEF REQUEST NO. 6 COMPONENT OR ITEM Reactor Vessel Supports CODE CLASS PROGRAM TABLE I-IWF CODE ITEM F2.10 F2.20 F2.30 F2.40 EXAM CATEGORY F-B

0 0

RELIEF REQUEST NO. 7 COMPONENT OR ITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY Piping Systems Penetrating Containment C7.10, C7.20 C7.30, C7.40 C7.50, C7.60 C7.70, C7.80 C-H The System Leakage Test and System Hydrostatic Test requirements ofthe 1980 Edition through and including the Winter 1981 Addenda includes essentially all ASME Class 2 pip-ing.

LTER ATEEXAMINATION Utilize 10CRF50 Appendix J Leak Rate Testing requirements and results to satisfy the ASME Section XIrequirements. This would apply to the followingmechanical/piping pene-trations:

Penetration No:

6 7

9 21 22 23 24 25A/B 28 29 30 31 32A 33 34 35 36 38 39 42A System:

DW FP RD SI SI SI SI HC SI GA GA IA HC NC NC HP HP HP

- HP SS Line No:

055 096 259 088 130 007 030 008 149 009 002 069 007 135 137 001 002 003 004 004 P&IDNo:

DWP-002 FPP-006 RDP-001 SIP-002 SIP-002 SIP-001 SIP-001 HCP-001 SIP-001 GAP-001 GAP-001 IAP-003 HCP-001 NCP-003 NCP-003 HPP-001 HPP-001 HPP-001 HPP-001 SSP-001 System ASME Classification 2

2 2

2 2

l,

0

RELIEF REQUEST NO. 7 Cont'd Penetration No:

42B 42C 43 44 45 50 51 52 53 54A 55A 56 57 58 59 60 61 62A 62B 62C 67 77 78 79 System:

Line No:

SS 007 SS 001 CH 122 CH 283 CH 275 PC 073 PC 072 GR 001 FUELTRANSFER TUBE HC 006 HC 004 CP 005 CP 007 CL 001 IA 080 WC 039 WC 042 HC 005 CL 009 CL 008 SI 114 SI 106 CP 006 CP 008 P&IDNo:

SSP-001 SSP-001 CHP-002 CHP-003 CHP-003 PCP-001 PCP-001 GRP-001 PCP-001 HCP-001 HCP-001 CPP-001 CPP-001 CLP-001 IAP-002 WCP-001, WCP-001 HCP-001 CLP-001 CLP-001 SIP-002 SIP-002 CPP-001 CPP-001 System ASME Classification 2

2 2

The applicable containment piping penetrations are subjected to 10 CFR 50, Appendix J testing. This Request for Relief was accepted for the 1st 10 Year Inspection Interval in the USNRC letter dated April 12, 1996, from W. H. Bateman to W. L Stewart, "Evaluation ofthe First Ten Year Interval Inspection Program Plan, Revision I, and Associated Request forRelief for Palo Verde Nuclear Generating Station, Units 1, 2, and 3." This Request for Relief has been revised to reflect ASME Class 2 piping systems and Code Case N498-1 (refer to Request for Relief ¹11) for the System Hydrostatic Test requirements.

~~ First Ten Year Inspection Interval SRH~VI Pending USNRC review and acceptance.

0 0

RELIEF REQUEST NO. 9 COMPONENT OR ITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY Steam Generator Handhole Modification N/A IWA-5000 IWC-5000 Perform hydrostatic pressure test (1.25 times the system design pressure) after repairs by welding.

Adetailed basis was provided under separate cover. The followingis a brief summary:

-The hydrostatic pressure test must be performed with the vessel defueled due to testing prerequisites.

-This would require an additional reactor reassembly.

-The reactor coolant pumps would be used to raise and maintain temperatures in a precore type configuration at their upper design limit.

-Allmain steam safety valves and atmospheric dump vales would require removal and replacement with blind fianges.

-Additional supports would be required due to filingthe steam lines with water.

A system inservice test willbe performed at normal operating pressures.

First 10 Year Inspection Interval NRC letter dated April8, 1993, from T. R. Quay to W. F. Conway, "REQUEST FOR RELIEF FROM THE ASME CODE, SECTION XI,HYDROSTATICPRESSURE TEST RE-QUIREMENTS".

0 0

0

RELIEF REQUEST NO. 10 COMPONENT OR ITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY Steam Generator Main Steam Nozzle Inner Radius Sections 2-2 C2.22 C-B The 1980 Edition through and including the Winter 1981 Addenda ofthe ASME Section XICode requires volumetric examination ofthe nozzle inside radius area.

LTERNATEEXAMINATION A surface examination was performed on the nozzles selected for examination.

g Due to the design ofthe PVNGS Steam Generator Main Steam Nozzles the volumetric examination is not practical. The nozzles have a protrusion into the steam generator. This area is accessible during outages thmugh the secondary side manway. A copy ofthe nozzle drawing is attached that illustrated the geometric conditions.

SCHED LE F R IMPLEMENTATI 1st 10 Year Inspection Interval hHXQVU,4 Pending USNRC review and acceptance.

0 e

RELIEF REQUEST NO. 10 Cont'd 37.5" 16" Main Steam Nozzle Cross Section (Typical)

I l

~

RELIEF REQUEST NO. 11 COMPONENT OR ITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY ALLISI PROGRAM ITEMS ANDCOMPONENTS 1-15 2-7 3-1 B15.11, B15.21, B15.31 B ISA I,.B15.51, B15.61 B15.71 C7.20, C7.40 C7.60, C7.80 D1.10, D2.10 D3.10 B-P C-H D-A,D-B, D-C IR K The 1980 Edition through and including the Winter 1981 Addenda of the ASME Section XIcode requires the performance ofa System Hydrostatic Test during the end ofthe 10 Year Inspection interval. The boundaries, systems, and components are identified in the referenced ISI Program Tables.

Perform a System Leakage Test for Class I and a System Pressure Test for Class 2 and 3 in accordance with the requirements ofN498-1.

Code Case N498 includes all ASME Class I and 2 systems and has been accepted by the USNRC in Regulation Guide 1.147. The N498-1 Code Case is essentially identical to the accepted Code Case, with the exception that itincludes ASME Class 3 Systems. Therefore the basis for acceptance would be the same.

First 10 Year Inspection Interval

~P~+QVVI g~

Pending USNRC review and acceptance.

a ca<

I 0

RELIEF REQUEST NO. 12 COMPONENT OR ITEM ASME Class 1 ISI PROGRAM ITEMS ANDCOMPONENTS CODE CLASS PROGRAM TABLE 1-15 CODE ITEM B15.11, B15.21, B15.31, B15.41 B15.51,.B15.61, B15.71 EXAM CATEGORY B-P

'P The 1980 Edition through and including the Winter 1981 Addenda ofthe ASME Section XIcode and Code Case N498 requires the boundary for the end ofinterval pressure test be V

extended to all Class 1 boundaries. This includes the small portion ofpipe between two Class 1 isolation valves; or between a valve and blind flange.

The visual examination performed during the System Leakage Test willbe extended to include the small portion ofpipe and downstream valve or blind fiange. The first valve will not be opened. A listofthese areas follows:

System:

Line No:

CH CH026 CH CH024 CH CH022 CH CH020 CH CH026 CH CH520 CH CH001 RC RC091 RC RC091 RC RC089 RC RC096 RC RC062 RC RC017 RC RC099 PAIDNo:

CHP001 CHP001 CHP001 CHP001 CHP001 CHP001 CHP001 CHP001 CHP001 RCP001 RCF001 RCP001 RCP001 RCP001 Valve

Description:

3PCHNV848 3PCHNV849 3PCHNV859 3PCHNV860 3PRCNV752 3PCHEVM41 3PCHEV853 3PRCEV061 3PRCEV063 3PRCEV332 3PRCEV333 3PRCEV001 3PRCEV062 3PRCEV057 System:

RC RC RC RC RC RC RC RC RC SI SI SI SI SI Line No:

RC200 RC203 RC024 RC024 RC022 RC112 RC106 RC118 RC124 SI207 SI217 SI223 SI240 SI248 PAIDNo:

RCP002 RCP002 RCP002 RCP002 RCP002 RCP002 RCP002 RCP002 RCF002 SIP002 SIP002 SIP002 SIP002 SIP002 Valve Description 3PRCNV900 3PRCNV903 3PRCNVR30 3PRCNV753 3PRCNV754 3PRCNV869 3PRCNV868 3PRCNV871 3PRCNV870 3PSIEV882 3PSIEV974 3PSIEV883 3PSIAV892 3PSIAV902

0

RELIEF REQUEST NO. 12 Cont'd System:

RC RC RC RC RC RC RC RC RC RC RC RC RC Line No:

RC005 RC005 RC005 RC098 RC069 RC070 RC060 RC018 RC179 RC058 RC020 RC202 RC201 P&IDNo:

CHP001 CHP001 CHP001 RCP001 RCP001 RCP001 RCP001 RCP001 RCP001 RCP001 RCP002 RCP002 RCP002 Valve

Description:

3PCHEV939 3PCHEVM42 3PCHEV096 3PRCEV056 3PRCEV214 3PRCEV215 3PRCEV334 3PRCEV058 3PRCEV392 3PRCEV335 3PRCNV755 3PRCNV902 3PRCN V901 System:

SI SI SI SI SI SI SI SI SI SI SI SI SI SI Line No:

SI248 SI248 SI156 SI156 SI179 SI175 SI193 SI225 SI203 SI199 SI248 SI221 SI199 SI240 P&IDNo:

SIP002 SIP002 SIP002 SIP002 SIP002 SIP002 SIP002 SIP002 SIP002 SIP002 SIP002 SIP002 SIP002 SIP002 Valve Description 3PSIAV055 3PSIAV906 3PSIAV880 3PSIAV804 3PSIEV881 3PSIEV803 3PSIBV879 3PSIEV975 3PSIEV064 3PSIBV057 3PSIAV056 3PSIEV063 3PSIBV907 3PSIAV801 The normal reactor pressure boundary is examined during each refueling outage and no pressure boundary leakage has been noted. Currently these valves are independently verified closed prior to plant startup and are not manipulated during any procedurally guided plant evaluations while at power. Since these valves are not cycled at NOP/NOT, the opportuni-ty to experience an incident where a valve willnot reseat is increased. This can be due to several mechanisms, foreign material moving into the seating surface, stem failure while opening or closing, packing shifting, or valve binding. The opportunity for a packing leak willalso present itself, with the added challenge ofnormal RCS pressure behind it. Cy-cling ofthese valves and the resulting compensatory actions due to a leak can easily result in leakage and a forced unit shutdown or cooldown. Current operating procedures require these valves to remain closed with no exceptions. Valves that need to be operated are specifically identified to manipulate only in mode 5 (to prevent RCP seal damage).

D F

P First Ten Year Inspection Interval Pending USNRC review and acceptance.

+ e, RELIEF REQUEST NO. 13 COMPONENTORITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY Reactor Vessel and Closure Head Weld Coverage B1.22 B-A D

The 1980 Edition through and including the Winter 1981 Addenda ofthe ASME Section XICode requires the Meridional Head Welds to be examined for 100% ofthe accessible length.

I A

The ultrasonic examinations ofboth the Closure Head and Bottom Head Meridional weld was performed to the extent possible. A sketch showing scan limitations is attached for both areas. The total coverage is estimated to be 31% for the closure head and 20% for the bottom head welds.

These examinations are both limited by physical constraints. The sketches attached attempt to depict each limitation.

N First Inspection Interval hRR~VI Pending USNRC review and acceptance.

fj

RELIEF REQUEST NO. 13 Cont'd 0

Accessible Portion of MERIDINALWELD ooo 0 0 0 0

/ 000000 00000 OOOSO 0 0 0 0 0 er 0 0 0 0 oo' OOOOOOOOOr 0

r ooo 6

ood r

P 0 0 0 6 0 0 0 0 0 0 r

0 0 0 0 re 0 0 0 0 0 osr d

0 0 0 0 0 0 0 0 0 d 0 0 0 0 0 0 0 0 0 0 Accessible Portion of MERIDINALWELD CEDM Penetrations (97)

CLOSURE HEAD TOP VIEW Accessible Portion of MERIDINALWELD Support Skirt Accessible Portion of MERIDINALWELD CLOSURE HEAD SIDE VIEW

0 0

RELIEF REQUEST NO. 13 Cont'd LOWER VESSEL ASSEMBLY SIDE VIEW Accessible Portions of MERIDINALWELD Flow Skirt~

ICIPenctrations (61) Typ.

Accessible Portion of MERIDINALWELD 000 00 r

0 0 00' 0

0 r 0 0 iO 0

0 08 000 0

0 0

0 0

0 0 0

0 Or 0 0

rO0 0o 00 000 0

0 Flow Skirt ICI Penetrations INSIDE VIEWLOOKINGDOWN

0 0

RELIEF REQUEST NO. 14 COMPONENT OR ITEM CODE CLASS PROGRAM TABLE CODE ITEM EXAM CATEGORY Misc. Code Limited Examinations

1. RCP Flange Ligaments (RCPIA, IB, 2A, 2B)

2. Pressurizer Skirt Weld (5-1)

3. RCP Casing (Internal Surfaces)

4. Integrally Welded Attachment

5. Spray Pond Piping Supports 1-6 1-8 1-12 2-3 3-IWF B6.190 B8.20 B12.20 C3.20 B-G-I B-H B-L-2 C-C F-A, F-B, F-C The 1980 Edition through and including the Winter 1981 Addenda ofthe ASME Section XIcode requires 100% examinations unless otherwise noted in the code.

I n

B I

l. Allfour of the Unit 3 Reactor Coolant Pumps were disassembled during the first period. No examinations were performed at that time. The pumps were not disassembled during the remainder of the first interval. The examination offour Unit I pump flanges and two Unit 2 pump fianges have not revealed any abnormal conditions. Additionallythe pump fianges were examined for leakage and boric acid accumulations through the piping penetrations ofthe motor support stands while in mode 3 after each refueling outage and no degraded conditions were detected. AllUnit 3 RCP flanges willbe examined to Section XIrequirements at the next pump disassemblies.

2. Limitations were noted for the Pressurizer Skirt weld due mainly to the design. The attached sketch identifies the limitations for both volumetric and surface examinations. It should be noted that the ASME Code requires either volumetric or surface examinations be performed as applicable. Both examination techniques were applied to the weld from the outside. The inside surface area is considered inaccessible due to the pressurizer heaters, drain/instrumentation lines, and insulation. Avolumetric examination was performed to augment the surface exam, but it also is limited to scans from the skirt side of the weld only.

3. Allfour ofthe Unit 3 Reactor Coolant Pumps were disassembled during the first period. No examinations were performed at that time. The pumps were not disassembled during the remainder of the first interval. Allfour Unit 3 pumps were examined remotely. The examinations were performed by Wesdyne International using a submersible robotic cam-era system. The examinations were accomplished by directing the submersible from the reactor vessel thru the cold leg piping and into the pump. The examinations were limited and 100 lo coverage ofthe internal surfaces could not be obtained. No abnormal conditions were detected during the examinations. Allfour Unit I pumps were examined during refueling outage ¹ 7. These examinations were performed from the top ofthe pumps with the diffusers installed. No abnormal conditions were detected during the examinations.

Examiiiation ofthe internal pressure boundary shall be performed to the extent practical on all Unit 3 pumps at the next disassembly.

0

RELIEF REQUEST NO. 14 Cont'd

4. The integrally welded attachments for SG-52-H5 and SG-05-H9 are limited due to proximitywith structural steel and concrete. Due to this physical limitation, two adjacent inte-grally welded attachments ((3/4" design thickness) willbe examined at the next outage for Unit 3.

5. The examination of the Spray Pond (Ultimate Heat Sink) piping supports was performed utilizingtrained and certified divers. However, due to the environment in these spray ponds a deposit layer covers a majority ofthe examination area. Ifthese examinations reveal abnormal indications such as bent, missing, or broken, components; then that support willbe cleaned to enable a detailed examination ofthe welds.

First available outage BR'ending USNRC review and acceptance.

0 0

RELIEF REQUEST NO. 14 Cont'd PRESS UMZER LOWER VESSEL ASSEMBLY Skirt to Vessel Welds 12 Holes 6.00" Dis.

Support Skirt Pressurizer Heaters (36) Typ.

P 1

0