ML17313A751
| 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: |
| 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 PVNGS P.O. Box 52034 5801 S. Wintersburg Road Phoenix, AZ 85072-2034 Wintersburg,Az 85354-7529 PREPARED BY: ATE: 3 PREPARED BY: DATE:
REVIEWED BY: DATE:
ANII CONCURRENCE: DATE:
APPROVAL BY ENGINEERING DEPARTMENT LEADER: DATE: /2 /0 Pg COMMERCIAL PROGRAM NO: ISI-3 SERVICE DATE: 01/08/88 REVISION NO: 2 DATE: 12-15-98 score.<03'C9 ceo~'i'X PDR ~ 'ADQCK 05000530
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BKZL'UQH Cover 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 2-2 page 1 of 2 2-2 page 2 of 2 Table 2-3 page 1 of 4 2-3 page 2 and 3 of 4 2-3 page 4 of 4 2-4 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
4 3-IWF 0
Table 2-AHE page 1 and 3 of 3 2-AHE page 2 of 3 8-1 Table 2-CFR page 1 and 2 of 6 2-CFR page 3 of 6 2-CFR page 4 thru 6 of 6 9-1 9-2 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
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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
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AL0 k3Q PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVAL-EXAMINATION SUMNIARY ASMK CLASS I TABLE I I PAGE I OF 2 AShfE DES CRIPTIOi I ITEhf LINE NO., OR NDE TOTAL EXAMINATION INSPECTION RUNNING REMARKS AND NO.- ZOibE~hfPONENP ORSYSIHrf IDENTIFICATIOiN SERIAL NO. hfETIIO ITEMS AhfOUNT PERIOD RELIEF REQUESTS B 100 110 lll I- Reactor Vessel Butt Welds SN 65173 Vol 3 aa 0 0
100 112 I- Rextori Vessel Butt Welds SN 65173 Vol 9 a~ 0 0
100 120 121 None Note Request for Relief lt 13 hfEEininleAL I- Reactor Vessel Butt Weld SN 65173 Vol 0 Bonom Head 0 100 BrlrBEEL EI2dQZEL2.
EXAMINE ENTIRE ACCESSIBLE LENGTH 2- Closure Head Butt Weld SN 65173 Vol 33% Onc 33 33% Two 66 34% Ihfee 100 I- Reactor Vessel Bun Weld SN 65173 Vol 50% One a EXAhl FROM 0% Trro FLANGE 100% Three hlATING SVRFACF
'AIIIOhIATED EXAhf CORE BARREL EEhfOZEn Butt Weld SN 65173 Vol, S 33% One 33 33% Tsro 66 34% Three 100 REV. 2 12-15-98
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A~ Q A M PALO VERDE NUCLEAR GENERATING SI'ATION IOYEARINTERVAL-EXAMINATIONSVMMIARY ASME CLASS 1 TABLE FAGP 1 I2 GF 2 ASME DESCRIPTION ITEM LINE NOOR NDE TOTAL E)GlhHNATION INSPECTION RUNNING REMARKS AND NO. ZOiiE~hIPOi~ORSYSIEM IDENTIFICATION SERIAL NO. METHOD ITEMS AhIOUNT PERIOD RELIEF REQUESTS B 200 210 ~ I FOOT hllN.
. OF EACH 211 i LONGIIlJDINAL 212 lVELDTHAT INIERSECIS 5- Pressurizer Bun Weld SN 65373 Vol 33% Onc 33 THE SCHED-Shell to bonom 33% 7wo 66 ULED CIRC.
Head 34% Three 100 lVELDS WILL BE EXAMINED.
- 5. Pressurizer Butt Weld SN 65373 Vol 33% One 33 Shell to Top Head 33% 7FFo 66 34% Three 100 None None None 230 231 3- Steam Generator I Butt Welds SN 65273-1 Vol I One 33 I 7wo 67 G'STAY-I F~ Thrcc 100 CYLINDER EXAMS 4- Steam Generator 2 Butt Welds SN 65273-2 Vol I Onc 33 GFSTAY I 7FFO 67 CYLINDER
~F 1hrec 100 EXAMS REV; 2 12-15-98
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@ PALO VERDE NUCLIttRGENERATING STATION 10YEARINTERVAL-EXAMINATION
SUMMARY
ASMK CLASS 1 TABLE PAGE 2 1-2 OF
~s 2
ASME DESCRIPTION ITEM LINE NO., OR NDE TOTAL EXAMINATION INSPECTION RUNNING REMARKS AND NO. ZONE'COhIPONENTORSYSIEM IDENTIFICATION SERIAL NO. hIETHOD ITEMS AhIOUNT PERIOD RELIEF REQUESTS B- Steam Generator I Butt tlVelds SN 65273-1 Vol One 33 MIILTIPLEVESSELS 7ato 50 PERCENTAGES IllfCC 100 COMBINED .
4- Steam Generator 2 Butt tVclds SN 65273-2 Vol Onc 7wo 83 IllfCC 100
- 3. Steam Generator I Butt iVelds SN 65273-1 Vol I One 50 0 7wo 50 <<STAY-I lllrcc 100 CYUNDER EXAMS 4- Steam Generator 2 Butt iVelds SN 65273-2 Vol 0 One I 7wo 50 I Ttucc 100 250 None 251 None 252 None 253 260 None None REV. 2 12-15-98
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A PALO VERDE NUCLEARGENERATING STATION IOYFARINTERVAL-EXAMINATION
SUMMARY
ASME CLASS 1 TABLE PAGE~GF~
1-6 ASME DESCRIPI'ION "
ITEM LINE NO., OR NDE TOTAL EXAMINATION INSPECTION RUNNING REMARKS AND NO. ZOi IE~hIPONENTOR SYSTEM IDENTIFICATION SERIAL NO. hIETHOD ITEMS AhIOUNT PERIOD RELIEF REQUESIS 690 None 6100 None 6110 None MtV SIIEEK None 6120 None 6130 None 6140 None IKEY
~T 6150 ILOI'ER85252RK None 6160 None 6170 None FA SUPPLEMENTAL VT EXAM tVILLBE PERFORMED 100% PE 6180 REFUELING OUTAGE IN CONIUNCIION lVIIHEXAMCAT. B.P (SEE IEIN 80-27) 16 Reactor Coolant FhnSe Studs 4.33" x One 31 EFSUPPLEMENIED BY Pump IA 3257" 7ppo 62 VISUAL(EACH IhfCc 100 REMOVAL)ANDSUR.
FACE (AT 5 YEAR INTERVALS)EXAMS 17 Reactor Coohnt 4.33" x 16 One 31 WHEN REMOVED Pump IB 32.87" Vol'ol'ol'ol'6 7PPO 62 (SEE IEB 82-02)
'IlltCC 100 IS.Reactor Coolant HanSe Studs 4.33" x 16 One 31 Pump 2A 3287" 7PPO 62 ThfCc 100 19.Reactor Coolant HanSc Studs 4.33" x 16 One 31 Pump 2B 32.87" 7wo 62 Three 100 REV. 2 12-15-98
0 A PALO VERDE NUCIL~GENERATING STATION 10 YEAR INTERVAL-EXAIVIINATION
SUMMARY
ASME CLASS 1 TABLE PAGE~GF~
1-6 ASME DESCRIPTION ITEM LINE NO., OR NDE TOTAL EXAMINATION INSPECTION RUNNING REMARKS AND NO. ZOi IE'COiiOOANEN1'OR SYSIEM IDENTIFICATION SERIAL NO. METHOD ITEMS AMOUNT PERIOD fo RELIEF REQUESTS 6190 Note Rctiuest for
-Rciicf St 14 16, 17, 18 and 19- ': Range CASING SN ! 16 per One '100% EXAhl WHEN Reactor Coohnt As; Sutfacc IA- 1259 'ump TFPO DISASSEMBLED Pumps IA,IB,2A,2B I IB - 1261 1lllec ITHERE ARE NO 2A - 1260 , BUSHINGS IN THE 2B - 1262 PUMP FLANGES)
<<<<THE CLAMPING RING WILLBE E8SHERS" EXAMINED(THERE ARE NO WASHERS)
,16 Reactor Coohnt Nuts ti'G 4528" x VT-I 16 Onc 31 Pump IA Clamping Ring 7.283" TFPO 62 iiirec 100 17-Reactor Coohnt Nuts tL 4528" x 16 Onc 31 Pump I B Clamping Ring 7.283" TWO 62 Ilircc 100 18-Reactor Coolant Nuts dc 4528" x 16 One 31 Pump 2A Clamping Ring 7.283" Two 62 llircc 100 19-Reactor Coohnt Nuts dc 4528" x VT-I 16 One 31 Pump 2B Clamping Ring 7.283" 7PFO 6?.
lllrec 100 6210 None 6220 None None REV. 2 12-15-98
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PALO VERDE NUCLEARGENERATING STATION IOYEARINTERVAL-EXAMINATION
SUMMARY
ASME CLASS 1 PAGE I OF ASME DESCRIPTION ITEM LINE NO., OR NDE TOTAL EXAMINATION INSPECTION RUNNING REMARKS AND NO. ZOiMKOhIPOiifORSYSIKM IDENTIFICATION SERIAL NO. METIIOD ITEMS AMOUNT PERIOD RELIEF REQUESTS B 800
, SIO None NotcRelieffor Requert tt l4 5- Pressurizer Support Skirt SN 65373 S, Vol 33% One 33 33% Wo 66 34% Ttucc l00 3- Stem Generator I Support Skirt SN 65273-l VoL S 33% One hiULTIPLE Two 33'00' VESSELS, 34% Ttuec EXAhIINATIONS TOTAL 100%
4- Steam Generator 2 Support Skirt SN 65273-2 Vol, S One SUPPORT 33% TiNO SKIRT tVELD a Ttucc IN I STEAM GENERATOR.
None REV. 2 12-15-98
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~ k7Q PALO VERDE NUCLEAR GENERATINGSTATION 10 YIM,RINTERVAL-EXA1tdINATION SUMVIARY ASME CLASS 1 TABLE PAGE I I-9 OF 5 ASME DESCRIPTION ITEh1 LINE NO OR NDE TOTAL EXAhfINATION INSPECTION RUNNING REMARKS AND NO. ZOi IE~hIPOi~ORSYSIEhI IDENTIFICATIOiN SERIAL NO. METHOD ITEMS AMOUNT PERIOD RELIEF REQUESTS B 900 MWLDRIEZIHhYi 910 911 i THE LESSER 912 OF12" ORI PIPE DIAMEIER LENGTH FROhl SCHEDULED CIRC tVELD INIERSECIION o r WILLBE EXAMINED
- 6. RCS Primary Piping HL I RC-3242" ID S, Vol 62 7 One 11 AUIOhIATEDEXAM HL2 RC6342" ID 6 Two 21 OF NOZZLE TO CL IAto RCP RC.33-30" ID 9 Tllfee 35 EXTENSION AND CL I B to RCP RC-30-30" ID EXIENSION TO PIPE CL2Ato RCP RC-73-30" ID iVELDS CL 2B to RCP RC-84-30" ID CL IAto RPV RC 34-30" ID CL IB to RPV RC-31-30" ID CL2Ato RPV RC-79-30" ID CL 2B to RPV RC-93-30" ID 20-PZR Surge Une Butt Welds RC 28-12" S, Vol One 9 Trio 9 Tliree 27 214D Cooling Butt Welds RC-51-16" S, Vol 19 One 11 Loop I Sl-2tth16" Ttjro 21 Ttuee 32 2WD Cooling Butt Welds RC 68.16" S, Vol 18 One 11 Loop 2 SI-193-16 Two 22 Ttuee 39 2341 Loop I A Butt Welds SI-207-14" S, Vol 18 One 17 SI 203-12" Trio 17
- AdditionslWeld Added Per IN 97-19 REV. 2 12-15-98
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~ Q J. k3 PALO VF<NDE NUCLEAR GENERATING STATION 10 YEARINTERVAL-EXAMNATION
SUMMARY
ASME CLASS 1 TABLE PAGE 2 1-9 OF~
AShIE DES CRIPI'ION ITEM LINENO., OR NDE TOTAL EXAMINATION INSPECHON RUNNING REMARKS AND NO. ZONE~hiPOi iENTOR SYSK&I IDENTIHCATION SERIAL hO. hIETHOD ITEMS AhIOUNT PERIOD RELIEF REQUESTS 911 IL 912 24$ 1 Loop I B Buu Welds SI-223-14" S, Vol 17 0 One 0 O'Additional Weld 2 Sl-221 ~ 12" 3 TWO 18 Added Pcr IN 97-19 2E ~ lllrce 29 25$ 1 Loop 2A Butt Weids SI.160.14", S, Vol 21 2 One 10 SI 156 12" 3 TWO 24 lllfee 29 26 SI Loop 2B Butt Welds SI-179-14" S, Vol 17 2 Onc 12 81-175-12" I TWO 18 2FF Ttuec 29 28 d2 29- PZR SPray Bun Welds RC-184" S, Vol 15 Onc 13 Loop i B and Combined TWO 18 lllfec 33 31.PZR Safeties Bun iVelds RC-1-6" S, Vol 12 One 8 RC-3$ TWO 25 RC-5$ " 42 RC.7.6" 36-Letdown Line Butt Welds RC.91 ~ 16" S, Vol One 0 Dehy Coil TWO 25 Three 25
'HE LESSER OF 12" OR I PIPE DIAMEIER LENOTH FROM 921 SCHEDVLEDCIRC WELD INIERSECITON WILLBE EXAMINED 27.PZR Spray Butt Welds RC$ 2-3" 39 Onc 8 Loop I A RC-16-3" TWO 15 lllfee 26 28.PZR Spray Butt Welds RC 17-3" 36 One ll Loop I B RC-18-3" TWO 19 Ttlrec 28 REV. 2 12-15-98
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A PALO VERDE NUCU<AR GENERATING SI'ATION 10 YIBRINTERVAL-EXAMNATION
SUMMARY
ASME CLASS 1 TABLE PAGE~GP~
1-9 AShIE DESCRIPTIOiN ITEhI LINE NO., OR NDE TOTAL EXAMINATION INSPECTION RUNNING REMARKS AND NO. ZOiiE~hImEN1'ORSYSIKN IDENITFICATION SERIAL NO. hIETHOD ITEhIS AhIOUNT PERIOD RELIEF REQUESTS
<<VOLEXAMOF2 WELDS AND BASE-hiETALDOWN-STREAM OF V431 30.Aux PZR spfay . Butt Wews CHES-2" t \ Pi 2 One<< 18 PER IEB 88418.
CH-520-2" 2 7wo 36 CH-521-2" t 0<< ~ 36 *<<Additional Weld Added Per IN 97-19 I
32.Drain Line I Butt Welds RC-60.2" I One Loop IA 7wo IllfCC 33-Drain Une Butt Welds RC 58-2" 5 One 0 Loop IB 7wo 40 Three 40 34.Drain Une Butt Welds RC-96.2" One 0 Loop 2A 7wo 0 ThfCC 40 35-Drain Linc Butt Welds RC-89-2" One 0 Loop 2B 7wo 0 1Ilfec 40 36 Letdown Unc Butt Welds RC.91-2" 70 Onc 6 7wo 14 Tllrcc 26 37-Chafgin8 Line Butt Welds CH-5-3" 5 One 8 6 7wo 18 6<< ~ Ttucc 28 38-Drain Une Butt Welds RC.70-2" Onc 0 Loop I 7wo 25 TllfCC 25 39-HPSI Supply Butt Welds Sl-248-3" 36 Onc 6 Loop I 7wo 14 Tlucc 25 40 HPSI Supply Butt Welds Sl-199-3" One 13 Loop 2 7wo 21 Itucc 29 REV. 2 12-15-98
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~ Q A k7 PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVAL- EXAMINATIONSUMVIARY ASME CLASS 1 PAGE~OF~
ASME DESCRIPTIOiN ITEM LINE NOOR NDE TOTAL EXAhlINATION INSPECTION RUNNING REMARKS AND NO. ZOi IE<<CORIPOiiIENTOR SYSTEM IDENTIFICATION SERIAL NO. METHOD ITEMS AMOUNT PERIOD RELIEF REQUESTS B 1000 1010 li.".'. ll:> ITEhl BIO. IO COhlBINED it FOR PERCENTAGE t
XPSD Cooling Sl-193-16", I Loop 2 2441 Loop I B Stanchion Sl-223-14" 0<< <<SUPPORT DELEIED 2541 loop 2A Stanchion SI-160.14" i 2641 Loop 2B Stanchion SI-179-14" One 36.Letdown Line R(AS I-16" One Tate None 1030 None REV. 2 12-15-98
I AL0 k3Q PALO VERDE NUCLEARGENERATING STATION 10 YEAR INTERVAL-EXAMNATION
SUMMARY
ASME CLASS 1 TABLE PAGE P 1-12 GF~
ASME DESCRIPTION ITEM LINE NO., OR NDE TOTAL EXAMINATION INSPECTION RUNNING REMARKS AND NO. ZOiqEKOhIPOiKKKORSYSTEM IDENTIFICATION SERIAL NO. METEIOD ITEMS AMOUNT PERIOD RELIEF RE(}UESTS 1210 16 RC Pump IA Internal 1259 Examine thc <<BY THE END OF 17.RC Pump IB Surfaces 1261 Internal Surfaces 'IHE INTERVAL 18-RC Pump 2A 1260 in I Pump No(c Request for 19-RC Pump 2B 1262 Relief Sr 14 ZSIZK None IIQD~tELDR Borg Warner UV-651 RC-51-16" Vol Exanunc the 100 <<BY THE END OF Gate Valves UV.653 SI-240.16" lVeld in THE INTERVAL UtilizingForged UV-652 RC-68-16" I Valve Consuuction UV-654 SI.193-16" UV-634 SI-207-14" UV-644 SI-223.14" UV-614 SI-160-14" UV-624 SI-179-14" REV. 2 12-15-98
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AJ. D Q k3 PALO VERDE NUCLEAR GENERATING STATION 10 YEAR INTERVAL-EXAjIdINATION
SUMMARY
ASME CLASS 1 TABLE PAGE I GF~
ASME DESCRIPTION ITEM LINENO., OR NDE TOTAL EXAMINATION INSPECTION RUNNING REMARKS AND NO. ZONEKOhIPOiifORSYSIKM IDENTIFICATION SERIAL NO. METHOD ITEMS AMOUNT PERIOD REI IEF REgUESTS Note Rcxlucst for Relief g 11 gc 12 1510 Reactor Vessel Pressure ",: .= i.'r --Enure Pressure
- EACH REFULING 1520 Pressurizer Retaining retaining boundary OUTAGE 1530 Stcam Generators Boundary IWA-5000 1540 Heat Exchangers IWB-5000 1550 Piping 1560 Pumps 1570 Valves 1511 Reactor Vessel Pressure Entire Pressure EE BYTHE END OF 1521 Pressurizer Retaining retaining boundary THE INIERVAL 1531 Stcam Generators Boundary IWA-5000 1541 Heat Exchangers IWB-5000 1551 Piping *'E PERFORM 1561 Pumps WALKDOWNATTHE 1571 Valves BEGINNING OF EACH REFUELING OUTAGE FOR GENERIC LETIER gg415. IN ADDITION, WALKDOWNREQUIR-MENTS SHALLBE EVALUATEDFOR SHUTDOWNS FOLLOWING OPERATION LONGER THAN APPROXIMATELY6 hIONIHS IN hlODE I OR 2.
REV. 2 12-15-98
A~ WQ PALO VERDE NUCIL'ARGENERATING STATION 10YEARINTERVAL-IKAMINATION
SUMMARY
ASME CLASS 1 TABLE PAGE i GF~
ASME DESCRIPTION ITEM NO. ZOi EE~hfPOiKffORSYSIEhI IDENTIFICATION LINE NO., OR SERIAL NO.
NDE TOTAL hIETHOD ITEMS EXAMINATION AMOUNT INSPECTION PERIOD
'UNNING Fo REMARKS AND RELIEF REQUESTS REQUEST FOR RELIEF F 110 III & II3 F 120 F 130 E INCLUDES EXAM F 140 IIEhIS IDENIIFIED F 210 AS APPLICABLE F 220 and i f
F 230 EE NDE hIEIHOD F 210 INCLUDES VlA F 310 EXAhIS. WHERE F 320 APPLICABLE F 330 F 340 I- Reactor Vessel Support SN 65173 VT-3 0 GEE One 0 *'E REQUEST FOR F 350 Colunms 0 7FFO 0 RELIEF it 6 WAS 4 Thfcc 100 WIIHDRAWN t
3- Steam Generator I Support Skirt SN 65273-1 VT-3 One 100 7FFO 100 Three 100 4- Steam Gennator-2 Support Skirt SN 65273-2 VT-3 One Two 100 Iliiec 100 5- Pressurizer Support Skirt SN 65373 One 7FPO Three 100 16.Reanor Coolant Vntical and SN 1111-IA VT-3 10 Onc Pump IA Lateral Supports 7PPO
%luce 17-Reactor Coolant Vntical and SN 1111-1 B VT-3 10 One Pump IB Lateral Supports 7FFO Thrcc 18-Reactor Coolant Vnticsl and SN 1111-2A VT-3 10 One Pump 2A Lateral Supports 7PFO 19-Reanor Coolant V<<nicaI and SN 1111-2B VT-3 10 One Pump 2B Latnal Supports 7PFO Three REV. 2 12-15-98
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~ Q J. M PALO VERDE NUCLEAR GEMINATINGSI'ATION 10 YEAR INTERVAL-EXAMNATION
SUMMARY
ASMK CLASS 2 TABLE 2-2 FAGE~GF~
ASME DESCRIPTION ITEM LINE NO., OR NDE TOTAL EKAIillNATION INSPECTION RUNNING REMARKS AND NO. ZOiiE~hIPONENTOR~I IDENTIFICATION SERIAL NO. METHOD ITENIS AMOUNT PERIOD RELIEF REQUESTS 210 None FC"'el INSIDE RA-DIVS ON PIP-ING ONLY GREATER THAN 12" DIAMETER MVLTIPLEVESSELS:
PERCENTAGE COM-41-Steam Generator I Nozzle to SN-65273-1 S,Vol One 29 BINED Vessel Welds Two 57 Tlnee 100 42-Steatn Generator 2 Nozzle to SN-65273-2 S,Vol One Note Retlucst for Vessel Welds Two Relief St 10 Ihrce 84-SD Cooling Heat Nozzle to SN-18345 S,Vol One MULTIPLE Exchanger I Shell Welds Two VESSELS Three PERCENTAGE COMBINED 87-SD Cooling Heat Nozzle to SN-18346 S,Vol One Exchanga 2 Shell Welds Two Ih!ce 100 REV. 2 12-15-98
aa g AL53 k3Q PALO VERDE NUCLEAR GENERATING SI'ATION 10 YEAR INTERVAL-EXANIINATIONSUMNIARY ASME CLASS 2 TABLE 2-3 PAGE~GF~
ASME ITEM NO. ZOi IE~iWIPOi&TTOR ~I IDENTIFICATION DESCRIPTION LINE NO., OR SERIAL NO.
NDE TOTAL METIIOD ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REMARKS AND RELIEF REQUESTS 54-Fecdwata SG-1 L SG402 .- S One'-
Inside Cont. Two 7llfee 100 55-Fcedwater SG-2 Anadunents SG405 S'L One 50 hside Cont. Two 50 EL 7hfce ~ 100 4
6'bAux. Feedwata AF418 ."S One'wo SG-1 100 Ihfcc 100 6t-Blowdown SG-1 SG-39 One 43 Imide Cont. SG-53 Two 57 Note Request for IllfeC 100 Relief tt 14 slowdown SG-2 Anaduncnts SOS Onc Inside Conn SG-52 Two Three 71-LPSI Room A Discharge SI-87 One SI SYSIEM O'S COMBINED 76.CS Room A Suction SI-9 One 77~ Room A Discharge Auachments S1-79 8MB Room B Discharge Anachmcnts SI.119 82$ DCHX Room A Attachments 81-78 83$ DCHX Room A Anachments SI-70 8147 SI-90 86$ DCHX Room B Anachments 81-72 88-East Wrap Attachments srin One 89-East Wrap Anachments Sl-194 One REV. 2 12-15-98
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AJ. MQ D PALO VERDE NUCLEAR GENERATING STATION 10YEARINTERVAL-EXAMINATIONSUNINIARY ASME CLASS 2 TABLE 2-3 PAGE~OF~
ASME DESCRIPTION ITEM LINENO.,OR NDE TOTAL EXAhIINATIOiN INSPECTIOiN RUNNING REMARKS AND NO. ZONE~hIPONENr OR SYSIKKI IDENTIFICATION SERIAL hO. hIETHOD ITEMS AMOUNT PERIOD RELIEF REQUESTS Q?HIIHUED 9 I.West Wrap Attachments SI-70 One 92-West Wrap Attachments S1-239 Onc SI-24I Two 93-West Wrap SI49 ltvo 94$ 1 A th SI-70 SS'5$
1 B tL Attachments SI-194 SS'6$
1 LPSI I A Atachmcnts SI-202 99$ 1 LPSI 2B Auachments SI-174 IOO-SI LPSI A Attachments Sl-7 One SI-369 Two 101-SI LPSI B SI-30 Total Safety Injection 10 Onc 33 9 Two 63 11 Ihfcc 100 AITACEhIIRKR 72-LPSI Pump Anachment SN OS76-44 66 Loop I Lugs 100 100 7S.LPSI Pump Attachment SN OS7645 One Loop 2 Lugs Two 33 Ihicc 100 7S-Containment Attachment SN OS76-46 One 66 Spray Pump Loop I Lugs Two 100 Three 100 REV. 2 12-15-98
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AL0 MQ PALO VERDE NUCLEARGENERATING STATION 10YEARINTERVAL-EXANIINATIONSUMIVIARY ASME CLASS 2 TABLE 2-7 PAGE~OP~
ASME DESCRIPTION ITEM LINE NO., OR NDE TOTAL EXAMINATIOiN INSPECTION RUNNING REMARKS AND NO. ZOAAIE'ECOhIPOA'IffORSYSIKhI IDENTIFICATION SERIAL NO. METHOD ITEMS AMOUNT PERIOD RELIEF REQUESTS
<<~<<
710 Pressure Vessels Pressure Entire Pres- *EACH 730 Piping Retaining sure retain INSPECIION 750 Pumps Boundry ing boundly PERIOD 770 Valves IWA-5000 IWC 5000 720 Pressure Vessels Pressure Entire Pres- <<'EACH 740 Piping Retaining sure retain INSPECIION 760 Pumps Boundry ing boundry INIERVAL 780 Valves IWA-5000 IWC.5000
<<<<<<REQUEST FOR RELIEF g 7 dc tr I I REV. 2 12-15-98
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L0 k3 Q PALO VERDE NUCLEAR GENERATING SI'ATION TABLE 2-DVF 10YEARINTERVAL-EXAMINATIONSUMVIARY ASME CLASS 2 FAG~OF~
ASME DES CRIPTIOiN ITEM NO. ZOiiEKOhIPONEN1'OR ~1 IDENTIFICATION LINE NOOR SERIAL hO.
NDE TOTAL hIETIIOD ITEMS EXAMINATION AMOUNT INSPECTION PERIOD RUNNING REhIARKS AND RELIEF REQUESTS F110 92ZGEUED F120 50-hfain Steam SG-2 SG-209 VT-3 One F130 917'lSSS Two F140 three 100 F210 F220 51-Aunosphae Dump Supports SG-59. =
2 One 50 F230 SG-1 SG-70 Two 100 F240 three 100
~ 'P H10 H20 52-Atmosphere Dump Supports SG;84 One H30 SG-2<., SG-103 Two F340 lhfec 100 H50 53-Steam to Aux. Supports SG-81 VT-3 One 50 Feedwater System SG-83 Two 75 1llfee 100 54.Fcedwater SG-1 Supports SG-2 VT-3 19 Onc 30 Inside Cont. SG-13 Two 65 lhfcC 100 55 Feedwater SG.2 Supports SG-5 19 Onc 42 Inside Cont. SG-14 Two 79 Three 100 56-Feedwatcr SG-1 Supports SG-202 Vl'-3 Onc hlSSS. Trro 100
'lhfcc 100 57-Fcedwater SG-2 Supports SG-205 Vl'-3 hlSSS 100 58-Aux. and Down- Supports SG-8 VI'-3 32 coma Fmlwata AF4 64 SG.1 Inside Cont. 100 59-Aux. and Down- Supports SG-11 Vl'-3 22 6 27 coma Feedwata AF6 6 55 SG-2 Inside Cont. 10 100 60.Downcomer Fccd- Supports SG-200 33 wata SG-1 hlSSS 33 100 61-Downcomer Feed- Supports SG-203 Onc wata SG-2 hlSSS Two 66 three 100
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AX M D Q PALO VERDE NUCLEAR GENERATING STATION 10YEARINTERVAL-EXAMNATIONSUMNIARY ASME CLASS 2 TABLE 2-IWF PAGE~GF~
ASME DESCRIPTION ITEM LINE NO., OR TOTAL EXAMINATION INSPECTION RUNNING REMI IARKS AND NO. ZOiiEKOitIPOiKNTOR SYSIEM IDENTIFICATION SERIAL NO. METHOD ITEMS AMOUNT PERIOD RELIEF RE(}UESIS F110 CQHIIHUEQ F120 F130 88-Safety Injec6ion Supports SI-72 VT-3 14 One F140 SI-73 IllfCC F210 F220 F230 89-Safety Injection Supports SI-173 One
'i' F240 SI-194 IllfCC F310 H20 90-Safety Injection Supports i SI-134 H40 'i F350 91-Safety Injection Supports SI-70 10 One SI.71 Two 7tlfee 92$ afety Injection Supports SI-2 12 One SI-239 Two SI-241 7hfCC 93$ afety Injection Supports 81.89 VT-3 Two ThfCC 94$ afety Injection Supports SI-70 15 One SI-89 TWO SI-24 I Illrcc 95$ afety Injection Supports SI-72 18 6 One
$ 1-134 10 TWO SI-194 2 1Iifec 96.LPSI I A Supports SI-202 18 One TWO 1ilfee 97-LPSI I B Supports $ 1-220 10 One 7 TWO 10 %luce 98.LPSI 2A SI-155 VT-3 Onc Two 99-LPSI 2B Supports SI-174 VT-3 10 REV. 2 12-15-98
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AL0 MQ PALO VERDE NUCLEARGENERATING STATION 10YEARINIKRVAL-XXAMINATION
SUMMARY
ASMK CLASS 2 TABLE 2-IWF PAGE~OF~
ASME DESCRIPTION ITEhI I.INE NO OR NDE TOTAI EXAMINATION INSPECTION RUNNING REhIARKS AND NO. ZONE~hlPONENTOR SYSIEhf IDENTIFICATION SERIAL NO. METHOD ITEMS AMOUNT PERIOD RELIEF REQUEFIS F110 CQHIIHUEQ F120 F130 100-IPSI A Suction Suppotts SI-7 One F140 SI-24I Two F210 SI-369 F220 F230 IOI-LPSI B Suction Suppotts SI-30 a .GVT-3 F240 SI-194 F310 SI-368 H20 F330 SI SYSTEMS 79 One 29 F340 ZONES (70-101) 87 TEto 60 HSO TOTALS 109 Thfee 100 REV. 2 12-15-98
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AJ.0 WQ PALO VI%DENUCLEAR GENERATING STATION 10YPARINTERVAL-EXAMINATIONSUMNIARY ASMK CLASS 3 PAGE~GP~
ASME DESCRIPTIOi I ITEM LINE NO., OR TOTAL EXAMINATION INSPECI'ION RUNNING REMARKS AND NO. ZONEKOiiIPOA~ORSYSTEM IDENTIFICATION SERIAL NO. METIIOD ITEMS AMOUNT PERIOD RELIEF REQUESTS 144 TEST DIIO Pressure Prcssure Entire Pres- EEACH D210 Retaining Retaining sure Retain- INSPECIION D310 Components Bomxhy ing Boundry PERIOD.
IWA-5000 IWD-5000 D110 Pressure Pressure Entire Pres- 100 EPEACH D210 Retaining Retaining sure Retain- INSPECIION D310 Components Bomxhy ing Boundry INTERVAL E "REQUEST FOR RELIEF g7,8, 4 ll
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REV. 2 12-15-98
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AL.0 k2Q PALO VERDE NUCLEARGENERATING SI'ATION 10YEARINTERVAL-EXAlIdINATION
SUMMARY
ASME CLASS 3 PAGF I OF i AShfE DESCRIPTION ITEhf LINE NO., OR NDE TOTAL EXAhfINATIOirI INSPECTION RUNNING REhfARKS AND NO. ZOiiE~hfPOi4ENI'ORSYSIEM IDENTIFICATION SERIAL NO. MEI'HOD ITEhfS AMOUNT PERIOD Io RELIEF REQUESTS FIIO GINCLVDES F120 EXAM ITEhfS F130 IDENIIFIED, F140 AS APPU-F210 ~
CABLE F220 F230, ~ ~ . o'NDE MEIHOD F240 INCLUDES HIO VT4 EXAMS,r H20; WHERE APP-H30 LICABLE H40 F350 AllChss 3 Systems i i Support Alllines VT-3 All Each In- REQVEST FOR (Except Auxiliary Components greata than specdon RELIEF d I, 3, rL 14 Feed wata) 4" nominal Interval pipe size Auxiliary Feedwater Support Alllines All 100% Each In-Systems Components spection Intaval REV. 2 12-15-98
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PALO VERDE NUCLEAR GENERATING STATION 2 CFR TABLE 10 YEAR INTERVAL-IKAMNATIONSUNIMARY gSMK CI,gss g PAGE 3 OF 6 (RHR, ECCS, and CHR SYSTEMS)
ASME DESCRIPTION EXAMAh(OUNT (40 YR)
ITEM LINE NO., OR NDE TOTAL INSPECTION 10 YR REMARKS AND NO. ZOiiEKOhIPOiNEYfOR SYSIEhI IDENTIFICATION SERIAL NO. METHOD ITEMS 40 YR 10 YR PERIOD RELIEF RE(}
511 512-SI-70 S,Vol 14 7 SI-72 S,Vol 14 7 88 dc 91 Safety injection Butt Welds ~ (52) (16)
Mtand West Wraps 10" x 0.365" SI-172 S,Vol 4 2 One SI-71 S,Vol 2 ,I Two
%%fee 12" x 0.375" Sr-72 S,Vol 17 Sl-73 S,Vol 6 SI.70 S,Vol 9 SI-71 S,Vol 8 20" x 0~" $ 1-72 S,Vol Sl-70 S,Vol 89 &, 92 Shutdown Cooling Butt Welds (64) (33)
Suction East and West 10" x 0.25ty'10" Sl-173 S.Vol 11 6 Wraps x 0365" Sl-239 S,Vol 10 5 "One Weld per line 12" x 0.250" SI-38 S,Vol 4
$ 1-2 S,Vol 10 16" x 0.312" Sl-194 S,Vol 8 Sl-241 S,Vol ll SW73 S,Vol 2 18" x 0.312" SI-194 S,Vol Sl-241 S,Vol REV. 2 12-15-98
RELIEF REQUEST INDEX DESCRIPTION Hydraulic and Mechanical Snubbers will be tested in'accordance with PVNGS Technical Specifications.
Withdrawn Insulation will not be removed for visual examinations or welded or mechanical attachments.
Level IIIPersonnel will be 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
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RELIEF REQUEST NO. I CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY I-IWF N/A N/A HYDRAULICAND MECHANICALSNUBBERS 2-IWF N/A N/A 3-IWF . N/A N/A Perform inservice functional testing of hydraulic 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 for testing 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".
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RELIEF REQUEST NO. 2 CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY NOZZLE INSIDE RADIUS SECTIONS PRESSURIZER 1-3 B3.120 B-D STEAM GENERATOR 1-3 B3.140 B-D STEAM GENERATOR 2-2 C2.22 C-B SHUT DOWN COOLING HEAT EXCHANGERS 2-2 C2.22 C-B
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RELIEF REQUEST NO. 3 CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY SUPPORT COMPONENTS I-IWF ALL F-A, F-B & F-C 2-IWF ITEMS F-A, F-B & F-C 3-IWF F-A, F-B & F-C INTEGRALATI'ACHMENTS 3-1 D-A,D-B & D-D R R Perform visual examinations (VT-3) of the mechanical or welded attachments'to the pressure retaining component on insulated systems.
p ~BI visual examinations of the mechanical or welded attachments willbe performed to the extent practical. The insulation willnot be removed F'he to perform these examinations. It has been our experience that any loss of support capability or adequate restraint can usually be detected through the examination of uninsulated portions of the support, the accessible portions of the attachments through the insulation gaps, and or the surrounding insulation.
The mechanical and welded attachments willbe visually examined to the extent practical. The insulation will be removed from around the support attachment for further 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".
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RELIEF REQUEST NO. 4 CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY N/A N/A N/A N/A N/A All Level IIIpersonnel shall be recertified by examination on a triennial basis (IWA-2300(a)(1)).
The 1986 Edition of Section XI and the 1983 Edition thru Summer 1983 Addenda of ASME III (Latest Edition and Addenda referenced in 10 CFR 55.55a) requires Level III personnel 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 CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY N/A N/A N/A N/A N/A WITHDRAWN
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RELIEF REQUEST NO. 6 CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY F2.10 Reactor Vessel Supports I-IWF F2.20 F-B F2.30 F2.40
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RELIEF REQUEST NO. 7 CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY Piping Systems Penetrating Containment C7.10, C7.20 C-H C7.30, C7.40 C7.50, C7.60 C7.70, C7.80 The System Leakage Test and System Hydrostatic Test requirements of the 1980 Edition through and including the Winter 1981 Addenda includes essentially all ASME Class 2 pip-ing.
LTER ATE EXAMINATION Utilize 10CRF50 Appendix J Leak Rate Testing requirements and results to satisfy the ASME Section XI requirements. This would apply to the following mechanical/piping pene-trations:
Penetration No: System: Line No: P&ID No: System ASME Classification 6 DW 055 DWP-002 7 FP 096 FPP-006 9 RD 259 RDP-001 21 SI 088 SIP-002 22 SI 130 SIP-002 23 SI 007 SIP-001 24 SI 030 SIP-001 25A/B HC 008 HCP-001 28 SI 149 SIP-001 29 GA 009 GAP-001 30 GA 002 GAP-001 31 IA 069 IAP-003 32A HC 007 HCP-001 33 NC 135 NCP-003 34 NC 137 NCP-003 35 HP 001 HPP-001 2 36 HP 002 HPP-001 2 38 HP 003 HPP-001 2 39 - HP 004 HPP-001 2 42A SS 004 SSP-001 2
0 RELIEF REQUEST NO. 7 Cont'd Penetration No: System: Line No: P&ID No: System ASME Classification 42B SS 007 SSP-001 2 42C SS 001 SSP-001 2 43 CH 122 CHP-002 2 44 CH 283 CHP-003 45 CH 275 CHP-003 50 PC 073 PCP-001 51 PC 072 PCP-001 52 GR 001 GRP-001 53 FUEL TRANSFER TUBE PCP-001 54A HC 006 HCP-001 55A HC 004 HCP-001 56 CP 005 CPP-001 57 CP 007 CPP-001 58 CL .
001 CLP-001 59 IA 080 IAP-002 60 WC 039 WCP-001, 61 WC 042 WCP-001 62A HC 005 HCP-001 62B CL 009 CLP-001 62C CL 008 CLP-001 67 SI 114 SIP-002 77 SI 106 SIP-002 78 CP 006 CPP-001 79 CP 008 CPP-001 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 L
USNRC letter dated April 12, 1996, from W. H. Bateman to W. Stewart, "Evaluation of the First Ten Year Interval Inspection Program Plan, Revision I, and Associated Request for Relief 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.
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RELIEF REQUEST NO. 9 CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM 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.
A detailed basis was provided under separate cover. The following is 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 filing the steam lines with water.
A system inservice test willbe performed at normal operating pressures.
First 10 Year Inspection Interval NRC letter dated April 8, 1993, from T. R. Quay to W. F. Conway, "REQUEST FOR RELIEF FROM THE ASME CODE, SECTION XI, HYDROSTATIC PRESSURE TEST RE-QUIREMENTS".
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RELIEF REQUEST NO. 10 CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM 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 of the ASME Section XI Code requires volumetric examination of the nozzle inside radius area.
LTERNATE EXAMINATION A surface examination was performed on the nozzles selected for examination.
g Due to the design of the 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 of the 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.
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RELIEF REQUEST NO. 10 Cont'd 37.5" 16" Main Steam Nozzle Cross Section (Typical)
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RELIEF REQUEST NO. 11 CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY ALLISI PROGRAM ITEMS AND COMPONENTS 1-15 B15.11, B15.21, B15.31 B-P B ISA I,.B15.51, B15.61 B15.71 2-7 C7.20, C7.40 C-H C7.60, C7.80 3-1 D1.10, D2.10 D-A, D-B, D-C D3.10 IR K The 1980 Edition through and including the Winter 1981 Addenda of the ASME Section XI code requires the performance of a System Hydrostatic Test during the end of the 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 of N498-1.
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 it includes ASME Class 3 Systems. Therefore the basis for acceptance would be the same.
First 10 Year Inspection Interval
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a Pending USNRC review and acceptance.
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RELIEF REQUEST NO. 12 CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY ASME Class 1 ISI PROGRAM ITEMS AND COMPONENTS 1-15 B15.11, B15.21, B-P B15.31, B15.41 B15.51,.B15.61, B15.71
'P The 1980 Edition through and including the Winter 1981 Addenda of the ASME Section XI code and Code Case N498 requires the boundary for the end of interval pressure test be V extended to all Class 1 boundaries. This includes the small portion of pipe between two Class 1 isolation valves; or between a valve and blind flange.
The visual examination performed during the System Leakage Test will be extended to include the small portion of pipe and downstream valve or blind fiange. The first valve will not be opened. A list of these areas follows:
System: Line No: PAID No: Valve
Description:
- System: Line No: PAID No: Valve Description CH CH026 CHP001 3PCHNV848 RC RC200 RCP002 3PRCNV900 CH CH024 CHP001 3PCHNV849 RC RC203 RCP002 3PRCNV903 CH CH022 CHP001 3PCHNV859 RC RC024 RCP002 3PRCNVR30 CH CH020 CHP001 3PCHNV860 RC RC024 RCP002 3PRCNV753 CH CH026 CHP001 3PRCNV752 RC RC022 RCP002 3PRCNV754 CH CH520 CHP001 3PCHEVM41 RC RC112 RCP002 3PRCNV869 CH CH001 CHP001 3PCHEV853 RC RC106 RCP002 3PRCNV868 RC RC091 CHP001 3PRCEV061 RC RC118 RCP002 3PRCNV871 RC RC091 CHP001 3PRCEV063 RC RC124 RC F002 3PRCNV870 RC RC089 RCP001 3PRCEV332 SI SI207 SIP002 3PSIEV882 RC RC096 RC F001 3PRCEV333 SI SI217 SIP002 3PSIEV974 RC RC062 RCP001 3PRCEV001 SI SI223 SIP002 3PSIEV883 RC RC017 RCP001 3PRCEV062 SI SI240 SIP002 3PSIAV892 RC RC099 RCP001 3PRCEV057 SI SI248 SIP002 3PSIAV902
0 RELIEF REQUEST NO. 12 Cont'd System: Line No: P&ID No: Valve
Description:
System: Line No: P&ID No: Valve Description RC RC005 CHP001 3PCHEV939 SI SI248 SIP002 3PSIAV055 RC RC005 CHP001 3PCHEVM42 SI SI248 SIP002 3PSIAV906 RC RC005 CHP001 3PCHEV096 SI SI156 SIP002 3PSIAV880 RC RC098 RCP001 3PRCEV056 SI SI156 SIP002 3PSIAV804 SI SI179 SIP002 3PSIEV881 RC RC069 RCP001 3PRCEV214 SI SI175 SIP002 3PSIEV803 RC RC070 RCP001 3PRCEV215 SI SI193 SIP002 3PSIBV879 RC RC060 RCP001 3PRCEV334 SI SI225 SIP002 3PSIEV975 RC RC018 RCP001 3PRCEV058 SI SI203 SIP002 3PSIEV064 RC RC179 RCP001 3PRCEV392 SI SI199 SIP002 3PSIBV057 RC RC058 RCP001 3PRCEV335 SI SI248 SIP002 3PSIAV056 RC RC020 RCP002 3PRCNV755 SI SI221 SIP002 3PSIEV063 RC RC202 RCP002 3PRCNV902 SI SI199 SIP002 3PSIBV907 RC RC201 RCP002 3PRCN V901 SI SI240 SIP002 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 will not 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 will also present itself, with the added challenge of normal RCS pressure behind it. Cy-cling of these 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 CODE PROGRAM CODE EXAM COMPONENTORITEM CLASS TABLE ITEM CATEGORY Reactor Vessel and Closure Head Weld Coverage B1.22 B-A D
The 1980 Edition through and including the Winter 1981 Addenda of the ASME Section XI Code requires the Meridional Head Welds to be examined for 100% of the accessible length.
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The ultrasonic examinations of both 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
ooo Accessible Portion of
/ 000000 0 0 0 0 00000 OOOSO0 0 0 0 0 0 0 0 0 er oo' MERIDINALWELD OOOOOOOOOr ooo ood r 0 r 6 0 0 0 6 0 0 0 0 P 0 0 r 0 0 re 0 0 0 0 0 0 0 osr 0 0 d 0 0 0 0 0 0 0 d 0 0 0 0 0 0 0 CEDM Penetrations (97)
Accessible Portion of 0 0 0 MERIDINALWELD CLOSURE HEAD TOP VIEW Support Skirt Accessible Portion of MERIDINALWELD Accessible Portion of MERIDINALWELD CLOSURE HEAD SIDE VIEW
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RELIEF REQUEST NO. 13 Cont'd LOWER VESSEL ASSEMBLY SIDE VIEW Accessible Portions of MERIDINALWELD Flow Skirt ~
ICI Penctrations (61) Typ.
Accessible Portion of MERIDINALWELD 0
00 00 r 0 0 0 00' 0 r 0 iO 0 0 Flow Skirt 0
0 0 08 0
000 ICI Penetrations 0 0 0 0 0 0 rO0 0 0 0o Or 0
000 000 INSIDE VIEW LOOKING DOWN
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RELIEF REQUEST NO. 14 CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY Misc. Code Limited Examinations
- 2. Pressurizer Skirt Weld (5-1) 1-8 B8.20 B-H
- 3. RCP Casing (Internal Surfaces) 1-12 B12.20 B-L-2
- 4. Integrally Welded Attachment 2-3 C3.20 C-C
- 5. Spray Pond Piping Supports 3-IWF F-A, F-B, F-C The 1980 Edition through and including the Winter 1981 Addenda of the ASME Section XI code requires 100% examinations unless otherwise noted in the code.
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- l. All four 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 of four Unit I pump flanges and two Unit 2 pump fianges have not revealed any abnormal conditions. Additionally the pump fianges were examined for leakage and boric acid accumulations through the piping penetrations of the motor support stands while in mode 3 after each refueling outage and no degraded conditions were detected. All Unit 3 RCP flanges willbe examined to Section XI requirements 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. A volumetric examination was performed to augment the surface exam, but it also is limited to scans from the skirt side of the weld only.
- 3. All four 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. All four 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 of the internal surfaces could not be obtained. No abnormal conditions were detected during the examinations. All four Unit I pumps were examined during
¹ refueling outage 7. These examinations were performed from the top of the pumps with the diffusers installed. No abnormal conditions were detected during the examinations.
Examiiiation of the 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 proximity with 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 utilizing trained and certified divers. However, due to the environment in these spray ponds a deposit layer covers a majority of the examination area. Ifthese examinations reveal abnormal indications such as bent, missing, or broken, components; then that support willbe cleaned to enable a detailed examination of the welds.
First available outage BR'ending USNRC review and acceptance.
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RELIEF REQUEST NO. 14 Cont'd PRESS UMZER LOWER VESSEL ASSEMBLY Skirt to Vessel Welds Support Skirt 12 Holes 6.00" Dis.
Pressurizer Heaters (36) Typ.
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