ML20024G776

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Forwards Info Re Inservice Insp Planned for Refueling Outage 8
ML20024G776
Person / Time
Site: Pilgrim
Issue date: 04/24/1991
From: Gina Davis
BOSTON EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-91-058, BECO-91-58, NUDOCS 9104300245
Download: ML20024G776 (21)
v • d • e


Text

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. I

'f 10CFR50.55(a)

ASME XI i BOSTON EDISON P0 grim Nuclear Power Station l Rocky Hill Road j Plymouth, Massachusetts 02300 j

l George W. Davis I semor vece Pedent - Nuclear April 24, 1991 BECo 91-058 U, S. Nuclear Regulatory Commission Document Controi Desk Hashington, DC 20555 License DPR-35 Docket 50-293 lain _yhAtpletions Planned for Refuelin2._Quiage #8 Pilariml{Uclear Power Station (PNPS)

Boston Edison Company hereby submits the inservice inspections planned for Refueling Outage #8 at PNPS. The examinations listed in Enclosure A are scheduled in accordance with the requirements of ASME XI 1980 Edition Hinter 1980 addenda and will complete 50% of the required examinations for the second ten year inspection interval. Additional ASME XI second interval examinations are listed in Enclosure B and will be performed, if possible. Certain ISI examinations originally scheduled for Rf0 #8 were performed during the April 1990 mid-cycle maintenance outage and they are identified with an asterisk in Enclosure A.

The following augmented examinations have also been scheduled for Rf0 #8:

- Examit. tions for Intergranular Stress Corrosion Cracking (IGSCC) in accordance with our response to Generic Letter 88-01 are listed in Enclosure C. Some of the examinations originally scheduled for Rf0

  1. 8 were performed during the April 1990 mid-cycle outage and they are identified with an asterisk. Several alternate welds have been substituted into the IGSCC exam schedule reported in our initial response to Generic Letter 88-01. These welds are identified in Enclosure D.

- The following IGSCC examinations will be conducted in accordance with our response to NRC Bulletin 88-08.

10R-IA-5 14R-A-13 14R-B-13 BECo committed to inspect 10-HS-18 and 10-HS-19 in the response to the bulletin. These welds will not be examined because the head spray line including these welds will be removed during this outage.

9104300245 910424 ADOCK 0500 3 gDR llI

BOSTON EDISON COMPANY 4e U.S. Nuclear Regulatory Commission Page 2

- Seven welds in non-safety related Reactor Water Cleanup piping are listed in Enclosure E and they will be examined for IGSCC in accordance with our most recent response to Generic Letter 88-01 (BECc Letter 90-140).

Ultrasonic thickness measurements for erosion / corrosion will be performed in accordance with our response to Generic Letter 89-08.

Ultrasonic examination of four Feedwater nozzles will be conducted in accordance with NUREG 0619.

Visual examination of the Core Spray spargers in response to Bulletin 80-13.

- Remote visual examination of a portion of the buried Salt Service Hater piping will be conducted.

- Ultrasonic thickness measurements of a portion of the accessible Salt Service Water piping will be conducted.

IG.H. Davis M RAH /cic/5515 cc: See page 3

Enclosures:

(A) ASME XI Second Ten-Year Interval Examinations Scheduled for Refuel Outage 8.

(B) Additional ASHE XI Second Ten Year Interval Examinations to be performed During Refuel Outage 8-if possible.

(C) Safety-Related IGSCC-Susceptible Helds Scheduled for Examination During Refuel Outage 8 in Accordance with Generic Letter 88-01.

(D) Modifled IGSCC Inspection Schedule ,

(E) Non-Safety Related IGSCC-Susceptible Helds Scheduled for Examination During Refuel Outage 8 in Accordance with Generic Letter 88-01 and BECo Letter 2.90.140.

' BOSTON EDISON COMPANY

'l U.S. Nuclear Regulatory Commission Page 3 cc: Mr. R. Eaton, Project Manager Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Mail Stop: 14D1 U. S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Senior NRC Resident Inspector Pilgrim Nuclear Power Station Mr. Fred P. Barton Supervising District Engineering Inspector Division of Inspection Department of Public Safety 1 Ashburton Place Room 1301 Boston, MA 02108 Factory Hutual Engineering Mr. Kevin McTaque ANIIS Boston District Office 1151 Boston-ProvidenceTurnpi(e Norwood, HA 02062 l

l

0 Exams perfonned ENCLOSURE A 4

. ' du ri n g.1990

Maintenance Outage, s PILCRIM WUCLEAR POWER $fAfl0N A$ME XI SECOND TEN TEAR INTERVAL EXAM! Nail 0N$ $CHEDULED FOR REFUEL OUTAGE 8

' .- .. . . . . . . . . . . . . . . . . SYST EM ID COMPOWE NT ID Wo. . COMPOWE NT . . . . . . . . . . . . I T E M NO. I SOME T R I C Wo. LOCAf l0N . . . . EX AN. ,

DESCRIPil0N METHOD CACS H 45*1 1 RlGID NANGER F(1 3) l$1 l*501 DW ACCESS VT 3 CACS H 45*1 1SG RIGID HANGER F(1 3) 181 1 50 1 DW ACCEtt VT 3

  • CACS M*45*1*5- SPRING MANGER F(1 4) 181 + 1 50 1 flP RouM VT*3 Vf*4
  • CACS M*45 1 6 $PRlWG HANGER F(1 4) l$1 1 50 1 T!P ROOM VT*3 VT 4

..e CRD 3+VSD*11 CAP TO P!PE C5.11 l$1*l*3 1 WEST CRD Mi ee.

CS 14 A 6 PIPE 10 ELBOW 89.11 l$1 1 14 1 DRYWELL UT45 l- UT60 Mi CS 14 B 6 PIPE TO ELBOW 89.11 ist l 14*1 DRYWELL - UT45 ,

UT60 Mi C$ 14R A 16 PENETRAtl0N 10 ELBOW 89.11 ISI l*14 1 DRYWELL PT DRYWELL UT45 U160 C$ 14R B 16 PENETRATION 10 ELBOW 89.11 ist i 14*1 DRYWELL - P1' '

UT45 U160 C$ Ga 14 1HLi(4) $UPPORT LUGS C3.40 181*l+14 2B WEST CR0 Mi

  • CS HL*14 F50 PIPE TO VALVE C5.11 - Islal.14 2A TORUS R00M Mi
  • CS - HLB 14*F48H PIPE TO ELBOW C$.11 'l$1*l.14*2A TORUS ROOM - Mi
  • CS HL 14 F51- PIPC 10 FLANGE -C$.11 l$l*1'14*28 TORUS ROOM Mi
  • CS ' HLB 14 F14H ' PlPE TO ELBOW C5.11 ISI I 14 2B TORUS R00M MT-CS DP/DC*14 3002 5 1 ELBOW TO PIPE C5.21 l$1 l*14*2A RWCU MX RM - Pi
  • UT45 UT60 CS DB/DC 14 3001*4-1 PlPE TO PIPE .C5.21 181 1 14 2B RB 51' .UT45 UT60 PT .

C$ M*14=1 2 RIGlD HANGER F(1 3) ISI t 14 2A TORUS Ro0M VT 3  ;

CS .H-14 1 4SH . RIGID HANGER F(1*3) ~ l$1 l=14 2A A RNA VV RM. Vf+3 CS =H+14*1+20$ RESTRAINT F(1 3) ISI 1 14*2A A RHR QUAD VT 3 CS N 14*1 6 RlGID HANGER F(1 3) . ISI l*14 2A . TORUS ROOM VT 3 CS H 14 1*10 RIGID HANGER F(1 3) Isl l 14 2B TORUS ROOM VT 3 -

. eee FW 6*A*4HL1(8) SUPPORT LUG B10.10 ISI 1 6 1 - DRYWELL. Mi
  • FW- ;6*A 10 P!PE TO FLUED HEAD . 89.11 ISI*l*6 1 STEAM TUNNEL Mi

!: U145 UT60

  • ' FW 6B8 rlPE TO FLUED HEAD B9.11 - 151 1 6 1 STEAN TUNNEL'MT Ui45 .

PAGEt 1-L L.

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-+--w,n-wwerew-_ mir w-wwg w mm- v -y-- t'mq M ---v'---- y wv'g1'er'--w-1-+ - -w-8-v*wwe"$w% 9Y -9'M*' T'" I

0 Exams performed ENCLOSURE A

.during 1,990 main tenance . outage.

- PILCRIM NUCLEAR POWER STA110N ASME XI SECOND TEN YEAR INTERVAL EXAMlhAll0h5 ECHEDULED FOR REFUEL OUTAGE 8

.......... . . . . . . . . . . S Y ST E H I D COMPONE N T 10 No. COMPONE N T . . . . . . . . . . . . I T EM No. I SOME T R I C NO. LOC Al l 0N . . . . E X AM. ,

DESCRIP110N METH00 U160

  • FW H 6 1 68 RIGID HANGER F(1 3) ISt i 6 1 STEAM TUNNEL VT 3
  • FW H 6 1 69 RIGID HANGER F(1 3) 151 l*6*1 STEAM TUNNEL VT 3 FW H 61 112 SPRING MANGEk F(1 4) Isl 1 6 1 DRYWELL VT 3 VT 4 FW H 6 1 SS 10 SNUBBER F(1 4) ISI t 6 1 DRYWELL VT 3 VT 4 FW H 61 SS 3 SNUBBER F(1 4) ISI t 6 1 DRYWELL VT 3 VT 4 FW H 6 1*SS 7 $NUBBE R F(1 4) 151 1 6 1 DRYWELL VT 3 V1+4 FW H 6 1 SS 9 SNUBBER F(1 4) 151 1 6 1 DRYWELL VT 3 VT 4 FW H 61 107 SPRING HANGER f(1 4) l$1 1 6 1 DRYWELL VT 3 VT 4 FW H 6 i+114 SPRING HANGER F(1 4) ISI I 6 1 DRYWELL VT 3 VT 4 HPCI 23 VB 2301 5 VALVE BOLilNG B7.70 ISI 1 23 1 DRYWELL VT 1 HPCI 23 VB 2301 8 VALVE BOLTING B7.70 151 1 23 1 IIP ROOM VT 1
  • HPCI 23 0 16 PIPE 10 PENETRA110N 09.11 151 1 23 1 DRYWELL MT U145 UT60
  • HPCI 23017 PENETRAll0N 10 PIPE B9.11 ISI 1 23 1 B RHR VV RM HT U145 UT60
  • 151 1 23 1 HPCI 23 1 12 PIPE 10 PIPE B9.11 TIP ROOM MT Ui45 U160 HPCI EB 23 37HL1(4) SUPPORT LUGS C3.40 151 1 23 5 HFCI ROOM HT
  • HPCI HL 23 1 2A FLANGE TO PlPE C5.11 151 1 23 4 TORUS REOM Mi
  • HPCI HL 23 F20 PIPE TO VALVE C5.11 151 1 23 4 HPCI ROOM MT HPCI DB 23 F53 ELBOW 10 PlPE C5.21 151 1 23 5 TORUS R00M MT UI45 UT60 HPCI H 23 1-23S RIGl0 HANGER F(1 3) 151 1 23 2 HPCI ROCH VT 3 HPCI H 23 1 25 RIGID HANGER F(1 3) IS! I 23 4 HPCI R004 VT 3 HPCI H 23 1 1SH ANCHOR F(1 3) 151 1 23 4 TORUS ROOM VT 3 HPCI H 23 1 28 RIGID HANGER F(1 3) 151-1 23 5 HPCI ROOM VT 3 HPCI H 23 1 SS13 SNUSBER F(1 4) 151 1-23 1 DRYWELL VT 3 VT 4 HPCI H-23 1-SS14 SNUBBER F(1 4) 151 1 23 1 DRYWELL VT 3 VT 4 HPCI H 23 1 20 SPRING HANGER ((1 4) ISI t 23 3 HPCI ROOM VT 3 VT 4 PAGE: 2
  • Exams ~ perfonted ENCLOSURE A

. duritig 1990 maintenance outage. i

.. PILGRIM NUCLEAR POWER $1A110N ASME XI SECOND TEN YEAR IW1ERVAL EXAMINAi!0NS SCHEDULED FOR REFUEL OUTAGE 8

.......... . .. . . . . . .. SYSTiM ID COMPONE NT ID No. . COMPONE NT. .. . . . . . . . . . I TEM NO. I SOMETR IC NO. LOCAT ION. . . . EXAM. ,

DESCRIPil0N METHOD MS- 1 VB 220 1 VALVE BOLilNG <2" B7.70 151 1 1 1 DRYWCLL vi+1 MS 1 VB 220 2 VALVE BOLTING <2" B7.70 151 1 1 1 STEAM fudWEt YT 1

  • MS 1 B 14 VALVE 10 PIPE B9.11 ISI I 1 1 DRYWELL MT U145 U160
  • MS 1 B 15 FLUED HEAD TO PlPE 99.11 1$1-1-1 1 '4TE AM TUNNEL Mi i Uf45 U160
  • MS 1B8 ELBOW 10 PIPE B9.11 ISI 111 DRYWELL Mi UT45 UT60
  • MS 1*B 9 PIPE 10 ELB0J B9.11 Ill I 1+1 DRYWELL- MT U145 U160 I
  • MS 1 AR*1 PIPE TO WELD 0LET B9.31 1$! 1 1 1 DRYWELL MT U145 UT60
  • _ MS H 1 1 29 RIGID MANGER F(1 3) ISI l*1 1 STEAM TUNNEL VT 3
  • MS M*t*1 36 RIGIO HANGER f(1 3) ISI l*1 1 STEAM TUNNEL VT 3
  • MS M*1 1*X7b ANCHOR F(1 3) lSt l*1'1 STEAM IUNNEL VT 3
  • - is M-1 1 108 RIGID SUPPORT F(1 3) ISI 1 1 1 STEAM TUNNEL VT 3
  • Ml W 1 1 X8 ANCHOR F(1 3) ISl 1 b1 STEAM IUNNEL VT 3 l MS H 1 1 HA1 SPRING HANGER f(1 4) istal 1 1 DRYWELL Vi*3 VT*4 1 MS ' H 1+1*HA4 SPRlWG HANGER F(14) 151 1 1+1 DRYWELL YT 3  !

VT 4 MS H 1*1 MB1 SPRING MANGER F(1 4) I$l*l 1 1 DRYWELL YT 3 VT*4 MS H 1 1*HC3 SPRING HANGER F(1 4) l$1 1 1 1 DRYWELL VT 3 VI 4 MS H 1 1 HD2 SPRING MANGER F(1 4) 151 161*1 DRYWELL VT 3 l VT 4

- MS 'H 1 1 HD4 SPRING HANGER F(1 4) ISI 1 1*1

. DRYWELL VT 3 Vi*4 MS H 1 1 SA3 SNUBBER F(1 4) 181 1 1 1- DRYWELL VT 3 VT 4 MS H 1 1 $B3 SNUBBER F(1 4) 151 1 1 1 DRYWELL VT 3-VT 4 l-RBCCU H +30 1

  • 44SG GUIDE F(1 3) 151 l*30 1 5 RNR QUAD VT*3
  • H 30 1*288 181*! 30-1 RB 74' vi 3 RBCCW GUIDE : F(1 3)

,

  • RBCCW- H 30 1 291.. . GUIDE F(1 3)' 151 I-30 1 FP HX RM VT 3

lI , - RBCCW ' :H 30 1 60SR GUIDE F(1 3) 151 1 30 1 FP HX RM VT 3

  • RBCCW H+30 1 61SA ANCHOR F(1 3). 181+1 30 1 'FP HX RM VT*3' l

PAGE: 3

  • Exams performed ENCLOSURE A

- dLirin'g 1990 maintenance outage.

PILGRIM NUCLEAR POWER $1AllON ASME x1 SECOND TEN YE AR IN1ERVAL EXAMINA110NS SCHEDULED FOR REFUEL OUT AGE 8

.......... . . . . . . . . . . SY S1E M ID COMP 0hE N T ID N0. . COMPONE N T . . . . . . . . . . . 11E M NO. I SOME T R IC NO. L OCAl lON. . . . E X AM. .

DESCRIPTION ME T HOD

  • RDCCW H 30 1 625A ANCHOR FL1 3) ISI 1 30 1 FP MX RM VI 3 RBCCW H 30 1 SR10 RIGID MANGER F(1 3) 181 l-30 1 FP HK RM YT 3
  • RBCCW H 30 1 125A ANCHOR F(1 3) 181 I 30 1 B AUX BAY vi 3
  • RBCCW H 30 1 75A ANCHOR F(1 3) 181 1 30 1 A Aux BAY VI 3
  • RBCCW H 30 1 1325SP ANCh0R F(1 3) ISt I 30 2 PIPEWAY VT 3 RBCCW H 30 1 135 klGID HANGER F(1 3) 151 1 30 2 A RHR OUAD Y1 3
  • RBCCW H 30 1 154 ANCHOR F(1 3) 151 1 30 2 B RHR QUAD V1 3
  • RBCCW M 30 1-275A ANCHOR F(1 3) 151 I 30 2 A AUX BAY VT 3
  • RCCCW H 30 1 30$A ANCHOR F(1 3) ist I 30 2 B AUX BAY VT 3 RBCCW H 30 1 52 RIGID HANGER F(1 3) 151 ! 30 2 B AUX BAY VT 3 RBCCW H 30 1 54 RIGID HANGER F(1 3) l$1 1 30 2 B AUX BAY W3 RBCCW H 30 1 66 RIGID HANGER F(1 3) 151 1 30 2 A AUX BAY VT 3 kBCCW H 30 1 67 RIGlD HANGER F(1 3) 151 I 30 2 A AUX PAY VT 3
  • RBCCW H 30 1 346 GUIDE F(1 3) 151 1 30 2 PIPEWAY VT 3
  • RBCCW M 30129sA ANCHOR F(1 3) 181 I 30 2 B AUX BAY V1 3
  • RBCCW H 30 1 745A ANCHOR F(1 3) 151 1 30 2 MG RC04 VT 3
  • RBCCW H 30 1 48 SPRING MANGER F(1 4) 151 I 30 2 8 RHR QUAD V1*3 VI 4 RBCCW H 30 1 65SH SPRING MANGER F(1 4) IS! t 30 2 PIPEWAY VT-3 VT 4 RCIC 13 VB 1301 16 VALVE BolilNG B7.70 151 1 13 1 DRYWELL VT 1 RCic 13 v81301 17 VALVE BoLilWG B7.70 151 1 13 1 11P ROOM VI 1 RCIC 13017 ELBOW 10 PIPE B9.21 151 1 13 1 DRYWELL Mi RCIC 13018 PIPE 10 P!PE 89.21 l$1 1 13 1 IIP ROOM M1 RCic HB 13 F MLi(2) HANGER LUGS C3.40 151 1 13 3 RCIC QUAD M1 RCic HL 13 F661 PIPE 10 ELBOW C5.11 151 1 13 3 TORUS ROOM M1
  • RCIC H 13 1 115A ANCHOR F(1 3) 181 1 13*1 IIP ROOM VT 3
  • RCIC H 13 1 A2 ANCHOR F(1-3) 181 1-13 1 11P ROOM VT 3
  • RCIC H 13 1 43 RESTRAIN 1 F(1 3) 151-1 13 1 11P ROOH VT 3
  • RCIC H 13 1 6SH RIGID MANGER F(1 3) ISI 1 13 1 11P ROON VT 3
  • RCIC H 13 1 25 RIGID SUPPORT F(1 3) l$1 1 13*2 RCic QUAD VT 3
  • RCIC H 131 26 RIGID SUPPORT F(1 3) l$1-1 13 2 RCIC QUAD VT 3
  • RCic H 13 1 2SR LATERAL RESTRAINT F(1 3) 151 1 13 2 RCic QUAD VT 3
  • RCIC H 13 1*29 RIG!D HANGER F(1 3) ISl t 13 3 RCic QUAD V1 3
  • RCIC H 13 1*33 SPRING HANGER F(1 3) ISI t 13 3 RClc QUAD vi 3 VT 4
  • RCIC H 13 1 44 SPRING MANGER F(1 4) 151 1 13 1 11P ROOM VT 3 VT 4 RECIRC 2R-FB BP 1A FLANGE BOLilNG B7.50 ist i 2R B DRYWELL VT 1 REclRC 2R FB N1A 7BC-1 FLANGE BOL11NG B7.50 ISI-t 2R B DRYWELL VT 1 RECIRC 2 v8 202 4B VALVE BOLilNG B7.70 ISI l 2R B DRYWELL V1 1 RECIRC 't N2C 3 CROSS TO PIPE B9.11 ISI-t=2R A DRYWELL P1 U145 U160 PACE: 4 l
  • Er.arns perfortned ENCLOSURE A durin'g 1990 maintenance outage.

PlLCRIM WUCLEAR POWER $1A110N ASME XI SECOND TEN YE AR INTER)AL EXAMiliAll0NS SCHEDULED FOR RifUtt OUTAGE 8

. . . . . . . . . . . . . . . . . . . . $Y $1 EM ID COMPokE N T 10 No. . CChP0NE NT . . . . . . . . . . . . I T EM Wo. I SOME T R I C WO. LOC Al l 0N . . . . E X AM . .

DESCRIPiloN METH00 REClRC 2R N18 4 PIPE 10 TEE B9.11  !$1 1 2R A DRYWELL PT U145 U160

  • RECIRC 2R W2H 3 CROSS TO PIPE 69.11 151 1 2R B DRYWELL P1 U145 UT60 RECIRC 2R N1A 14 TEE TO PlPE B9.11 151 1 2R B DRYWELL PT U145 UT60 RECIRC 2R W1B 9BC 3 PIPE TO VALVE B9.40 l$1 1 2R A DRYWELL PT
  • K2CILC H 2 1 G1 GUIDE F(1 3) ISI l*2R A DRYWE LL VT 3 REClRC H 2*1 $s23 SNunBER F(1 4) Ist I 2R A DRYWELL YT 3 VT 4 REClkC H 2 1 $57 $NUBBER F(1 4) Ill 1 2R A DRYWELL VT 3 VY 4 RECIRC H 2 1 $$1 $NUBBER F(1 4) ISt t 2R B DRYWELL VT 3 VT 4 REclRC H 2 1 H15 $PRING HANGER F(1 4) Ill 1 2R B DRYWELL VT 3 YT 4 RECIRC H 21 $$8 $NUBBER F(1-4) 151*l 2R B DRYWELL VT 3 VT 4 eee RHR 10 VB 100147 VALVE BOLilNG B7.70 1st i 10 1A A RHR W RM V1 1 RHR 10 IA 14 PIPE TO FLUED HEAD 89.11 Ill 1 10 1 A RNR W RM PT U145 U160 RHR 10R IA 12 PENETRATION 10 ELBCW B9.11 151 1 10 1 DRYWELL PT U145 U160 RHR 10R IA 5 VALVE 10 ELBOW 89.11 151 1 10 1 DRYWELL PT U145 UT60
  • RHR 10R 0-14 PIPE TO PIP! B9.11 ISI t 10 1A DRYWELL Pt U145 U160 RHR HL 10 200HL1(4) SUPPORT LUGS C3.40 ISl 1 10 4A A RHR QUAD MT RHR HL*10 F147 PlPE 10 VALVE C5.11 151 1 10 28 8 RHR QUAD Mi RHR CB 10 F163 VALVE TO PIPE C5.11 151 1 10 38 B RHR QUAD Mi
  • RHR CB 10 16 1C PIPE 10 ELBOW C5.11 1st I 10 4A A RHR QUAD MT
  • RHR CB 10 16 2C TEE 10 PIPE C5.11 151 1 10 4A A RHR QUAD Mi
  • RHR CB 10 F65 ELBOW 10 VALVE C5.11 ist 1 10 4A A RHR ouAD Mi RNR GB 10 3 3B PlPE TO ELBOW C5.11 151 1 10 4B torus ROOM MT RpR CB 10 F12 ELBOW TO PIPE C5.11 Isl 1 10 4R TORUS R00M Mi RHR HL 10 2 1E PIPE 10 ELBOW C5.11 ist I 10 ",B torus ROOM MT RHR DB/DC 10 3002 3 3 PIPE 10 P!PE C5.21 ISI t 10-4A A R4R W RM PT UT45 UT60 RHR DB/DC 10 3001 2 1 ELBOW 10 PIPE C5.21 151 1 10 4B B RHR W RM PT PAGE: 5 l
  • Exams perfonned ENCLOSURE A

- durilig 1990 maintenance outage.

PILGRIM WUCLEAR POWER STA110N ALMt Kl stCOND itW YE AR INTERVAL [KAMlhAflDNS SCHEDULED FOR REFull DJT AGE 8

....... .. .......... SYsitM ID COMPONENT 10 WO- COMP 0ht N T . . . . . . . . . . . . lit M WO. I s0Mt 1R i c WQ. L OCAt l 0N . . . . (K AM. .

DisCRIPil0N METHOD U145 U160 RHR CB 10 13 4C WELDotti 10 PIPt C5.31 151 1 10 3B B RHR QUAD Mi RHR M*10 1 43sH tlGlD HANGtt F(1*3) 151*l'10 10 TORUS ROOM VT 3 RHR H 10 1-51st Rts1RAlWT F(1 3) 151 1 10 1B torus Room VT 3 RHR H 10 1 52st Rts1RAlW1 F(1 3) l$1 1 10 1B TORUS Room Yi 3 Rh2 H 10153sH RIG 10 NANGtR F(13) Isl 1 10 10 TORUS RuoM VI 3 RKR H 10 1 55sR RisTRAINT F(1 3) 151 1 10 1B TORUS Room VT 3 RHR H 10 1 18st LATERAL Rit1RAlWI F(1 3) Isl 1 10 2A torus Room VT-3 RHR H 101 sG23 LAltRAL RisTRAlWT F(1 3) ist i 10 3A A RHR DUAD VT 3 nk H 10 1 sG20 LAftRAL REs1RAlki F(1 3) 151 1 10 38 8 RHR QUAD VT 3 RHR H 10 1 63 RIGID HANGER f(13) 151 1 10 48 torus Room VI 3 RNR H 10 1 63sR LAT(RAL Rts1RAlkt F(1 3) 151-1 10 4B 10Rus kooM VT 3 RHR H 101 108s LAftRAL REstRAlWi F(1 3) 151 1 10 49 TORUS Room vi 3 RHR H 10 1 110s RIGID HANGER F(1 3) 151 1 10 49 torus Room VT 3 RHR H 10 1 111s RIGID HANGER F(1 3) 151 1 10 48 torus Room VI 3 RHR H 10 1 37sH RlG1D HANGER F(1 3) 151 l*10 48 torus Room vi 3 RHR H 10 1 81 RIGID HAhGER F(1 3) ist 1 10 4B torus tooM VI 3 RHR M*10 1 1018 Ricl0 HANGER F(1 3) 151 1 10 5B 10Rus Room vi 3 RHR H 10 1 1025 LAftRAL RESTRAlWT F(1 3) 151 1 10 5B 10RUS ROOM VT 3 RHR H 10 1 103$ ALGID MANGER F(1 3) l$1 1 10 58 torus ROOM VT 3 RHR H 10-1 105s LAltRAL Ris1RA!WI F(13) 151 1 10 50 torus ROOM VT 3 RWR H 10 i+119 $PRlWG HANGtR F(1 4) l$1 1 10 19 8 RNR ouAD vi 3 VT 4 RHR H 10 1 2ss SPRlWG SUPPORT F(14) 151 1 10 3A A RHR QUAD vi 3 VT 4 RHR H 10 1 144 SPRING MAkCER f(14) Ist I 10 3A A RHR QUAD VI 3 VT 4 RHR M*10 1 145 sPetWG HANGta F(1 4) Isl.1 10+3A A pHR DUAD Vi*3 VI 4 RHR H 10 1 5ss SPRlWG SUPPORT F(14) ist I 10 3A A RHR QUAD VT-3 VT 4 RHR H 10 1-990 SPRlWG MANGER F(1 4) ist I 10 3A A RHR QUAD vi 3 VT 4 RHR H 10 1 117 $PRING HAkCER F(14) 151 1 10 38 8 RHR QUAD VT 3 VT 4 RHR H 10 1-96 SPRING HANGER F(1 4) Ist I 10 4A torus Room vi 3 VT 4 RHR M*10 1 85 SPRING HANGER F(1 4) 151 1 10 4B 10Rus Room VT 3 VT 4 ee.

RPV RPV C 1-180 CIRC WELO 3180 B1.11 151 1-54 1 DRYWELL UT45 U160 RPV RPV L 3 LONG SHELL WELD B1.12 151 1 54 1 DRYWELL U145 U160 RPV RPV sF 120 240 $NtLL TO FLANGE B1.30 151 1 54 1 DRYwtLL U145 U160 RPV RPV HF 120 240 NE AD 10 F L ANGE B1.40 151 1 54 2 DRYWELL UT45 PAGE: 6 l

o Eums performed ENCLOSURE A duH ng' 1990 maintenance outage.

PILCRIN NUCLEAR POWER $1All0N ASMI RI SECOND IEN TEAR ik1tRVAL EXAMihA110N$ $CHEDULED FOR REFull OU1A01 8

.......... .......... $YllEM ID COMP 0hthi ID Wo. . COMPONENT . . . . . . . . . . . 11 tM NO. I SOMt 1R I C Wo. LOCA110N . . . . EXAM. .

DESCRIPil0N MtIN00 U160 M1 RPV RPV Inittl0A VElsEL INittl0R 813.10 h/A 117' VT 3 RPV RPV N10 NIR N02ZLt INNER RADlus 83.100 151 1 54 1 DRYWELL UT REV RPV N18 Nit NO22LE IWWtt RADIUS 63.100 151 1 54 1 DRYWELL Ut RPV RPV N2D WIR N0ZZLt INNER RADIUS R3.100 l$1 1 54 1 DRYWELL UT RPV RPV N2E WlR NO22Lt INNtt RADIUS B3.100 151-1 54 1 DRYWELL Ut RPV RPV N2F Wit N0ZZLE INNER RADlVS B3.iOO 161 1 54 1 DRYWE LL V1 RPV RPV N2J Wit N0Z2LE INNER RADIUS B3.100 l$1 1 54 1 DRYWELL UT RPV RPV N4A Wit NO22Lt INNER RADIUS & B3.100 151 1 54 1 DRYWELL UT BORE RPV RPV N48 WIR N022Lt INNER RADIUS & B3.100 181 1 54 1 DRYWELL UT BORE RPV RPV N4C Wit NO2ZLt INNER RADIUS & 83.100  !$1 1 54 1 DRYWELL U1 BORE RPV RPV N40 WlR N022LE INNER RADIUS & B3.100 181 1 54 1 DRYWELL Ut BORE RPV RPV N68 NIR NO2ZLt INNER RADIUS B3.100 151 1 54 1 DRYWELL UT RPV RPV NiO NV N022LE 10 Visstl 83.90 1s1 1 54 1 DRYWELL Ut RPV RPV N18 NV NO2ZLE 10 VtsstL B3.90 1st i 54 1 DRYWELL Ut kPV RPV N2D WV NOZZLE TO VI$$[L B3.90 Iti t 54 1 DR M LL U1 RPV RPV N2E WV NO22LE 10 Visstl B3.90 l$1 1 54 1 DRYWELL Ut RPV RPV W2F NV NO22LE 10 Vts$tt B3.90 151 1 54 1 DRYWELL Ut RPV RPV N2J WV NO2ZLE 10 vissEL B3.90 151 1 54 1 DRYWELL U1 RPV RPV W68 WV N0ZZLt 10 VitttL B3.90 l$1 1 54 1 DRYWELL UT RPV 14 Bai SAFE END YO N0ZILE B5.10 181 1 14 1 ORYWELL U145 U160 P1 RPV 2R N2C 1 SAFE END to N0ZZLE B5.10 It! 1 2R A DRYWELL P1 U145 U160 RPV 2R N2D 1 SAFE END 10 N0ZZLE B5.10 ISI 1 2R A DRYWELL P1 U145 U160 RPV 2R N2t 1 SAFE END 10 N022LE B5.1U ist 1 2R A DRYWELL P1 U145 U160 RPV 2R N19*1 N0ZZLt 10 $ ATE [WD B5.10 ISI-t 2R A DRYWELL P1 U145 U160 RPV 2R N2F 1 SAFE END 10 WOZZLE B5.10 151 1 2R B DRYWELL P1 U145 U160 RPV 2R N2J 1 SAFE (No 10 N0ZZLt B5.10 Isl 1 2R B DRYWELL P1 U145 U160 RPV 311 9.022LE 10 CAP B5.10 151 I 3 1 DRYWELL P1 U145 U160 RPV RPV N9A 1 N0ZZLE 10 SAFC Eko B5.10 151 1 54 4 DRYWELL P1 PACE: 7

  • Exams perfonned ENCLOSURE A

- durihg 1990 Insintenance outage.

PILCRIM NUCLE AR POWER $1ATION

  • ALME kl $ECOND TEN TE AR IWiERVAL EKArlbA110h$ $CHEDULED FOR REfull OU1 ACE 8

. . . . . . . . . . . . . . . . . . . . SY S1 E M 10 CQHPONE N T 10 NO. . COMPONE N T . . . . . . . . . . . . I T E M No. 150ME T R I C Wo. LOC Al l0N . . . . E X AM. .

DESCRIPil0N METHOD U145 U160 kPV 6 N4A 1 $AFE END 10 N022LE B5.10 15116. DRYWELL Mi U145 Uf60 RPV h N48 1 SAFE END 10 N022LE B5.10 181 1 6 1 DRYWELL MT U145 U160 RPV 6 N4C 1 SAft END 10 N027tt B5.10 151 1 6 1 DRYWELL MT U145 U160 RPV 6 N4D 1 $AFE JND 10 NOZ2LE B5.10 ist-i 6 1 DRYWELL M1 U145 U160 RPV RPV CHN 19 36 CLOSURE HEAD Null B6.10 151 1 54 2 DRYWELL MT UT RPV RPV CS 19 36 CLOSURE STUDS B6.20 151 1 54 2 DRYWELL UT RPV RPV F1 10 36 1HREADs IN FLANGE B6.40 151 1 54 2 DRYWELL UT RPV RPV C619 36 CLOSURE BUSHINC$ 86.50 Ist i 54*2 DRYWELL VI 1 RPV RPV CW 19 36 CLOSURE WASHER 5 B6.50 151-1 54 2 DRYWELL VI 1 RPY RPV $W 120 240 SKIRT VELD 88.10 l$1 1 54 3 DRYWELL UT ee.

RWCU 12R 0 1A SWEEPOLET 10 ELBOW B9.11 151 1 12 1 DRYWELL P1 U145 U160 RWCU 12R 0 23 ELBOW 10 PENEIRATION 99.11 l$1 l+12 1 DRYWE LL Pi U145 U160 RWCU 12118 ELBOW TO PIPE B9.11 l$1 1 12 2 A RHR VV RM UT 45 UT 60 PT RWCU 12 l*19 PIPE 10 ELBOW B9.11 l$1 1 12 2 A RHR W RM U1 45 UT 60 Pi

  • RWCU H 441 1 GUIDE F(1 3) 111 1 12 1 DRYWELL VT 3
  • RWCU H 12197 GulDE f(1 3) 131 1 12 1 DRyyE(( y1 3 kWCU H 12 1 99 (.UlDE f(1-3) 151 I-12 1 RWCU HX RM VT 3
  • RWCU H 1 M i13 GUIDE F(1 3) 151 1 12 2 A RHR VV RM v1 3
  • RWCU N 12 1 1243 RESTRAlkT f(1 3) lll l*12 2 RWCU HX RM vi 3
  • RWCU H 12 1 1258 RES14AINT F(1 3) l$1 1 12 2 RWCU HX RM vi 3
  • RWCU N 12*i 35G CUlDE F(1 3) l$1 1 12 2 RWCU HX RM VT 3 RWCU H 12 1 14 $PRING HANGER F(14) l$1 1 12 1 DRY" ELL VT 3 VT 4 ee.

$sLC 11 vs 1101 1 VALVE BOtilkG B7.70 151 1 11 1 DRYWELL vi 1

$RLC 11 vs-1101 15 VALyt BotilNG B7.70 l$1 1 11 1 DRYWILL VT 1 PAGE : 8

0 Exams performed ENCLOSURE A

. . during 1990 maintenance outage.

PILGRIM NUCLEAR POWit $1All0N ASME XI EtCOND JEW YE AR lWi!RVAL EnAMihAllDNS SCHEDUttD FDR REFUtt OUTAGE 8

... ...... . . . . . . . . . . $Y Si t M I D COMPOWI N T 10 NO. . COMP 0ht W T . . . . . . . . . . . . lit M NO. I SOME T R i c WO. L DCA110N . . . . E X AM . .

DE SCRIPilDN MITH00

$BLC B 11 165 PIPE 10 (L90W B9.4D l$l*l 11*) DRYWELL PT SBLC B 11 178 ELBOW 10 PIPE 89.40 151 1 11 1 RB 74' BW PT

  • $8LC Mail 1 21 GUIDE f(1 3) l$1 1 11*1 DRYWELL VT 3
  • $8LC H 11*1 22 GulDE f(1 3) Ill*l 11 1 DRYWELL VT 3
  • $8tC H 11 1 23 GulDE f(1 3) ISI t 11 1 DRYWELL VT 3
  • $8LC H 11*1 24 GUIDE F(1 3) l$1 1*11 1 DRYWELL V1 3
  • $8LC H 11 1*25 GUIDC F(1 3) 151 1 11 1 DRYWELL VT*3
  • SBLC H 11 1*26 GUIDE F(1 3)  !$1 1 11 1 DRYkELL vi 3
  • $8tC H 11 1*31 GUIDE F(1 3) lll l.11 1 RB 74' V1 3
  • SBLC H 11*i 36 GUIDE F(1 3) 151 l*11 1 RB 74' VT 3
  • $$LC H 11 1*37 GUIDE F(1 3)  !$1*l 11 1 RB 74' VT 3

, $8LC H 11*1 40 GUIDE F(1 3) ist 1 11 1 RB 91' VT 3

..e

$$W H 29 1 15 RIGlD HANGtt f(13) l$1 l*29 1 $ AUX BAY VT 3

$$W H 29 1 25 RIGID HANGtt f(1 3) ISI t 29 1 $CRttN HS VT*3

$$W H 29 1 36- RIG 10 HANGER f(1 3) l$1 1 29 1 SCRitN H$ VT*3

$$W H 29 1 37 RIGID HANGER f(1 3) Ill I 29 1 SCREEN HS VT*3

$$W H 29 1 1 RIGlD MANGtt F(1 3) ISI t 29 1 A AUX BAY VT 3

$$W H 29 1 20 R GID HANGtt F(1 3) l$1 l*29 1 B AUX BAY VT 3

$$W H 29 1*21 RIGID HANGER F(1 3) l$1 1 29 1 B AUX BAY VT 3

$$W M 29 1*6SR RIGID MANGER F(1 3) lllal 29 1 B AU4 BAY V1+3

$$W H 29** 26 RIGID MANGER F(1-3) l$1 1 29 1 $CRttN HS VT 3

  • $$W H 29 1 1321$A ANCHOR F(1 3) l$1 1-29 1 SCRttN H$ VT 3 PAGE: 9

ENCLOSVRE B

. PILCRIM NUCLEAR POWER STA110N ADDlil0NAL ASME XI SECOND TEN YEAR INTERVAL EXAMlWATIONS TO BE PERFDRMED DURING REFUEL DUTAGE 8 SCHEDULE PERMITTING

.... ..... . . . . . . . . . . SYST E M 10 COMPONE N T 10 No. . COMP 0NE hi . . . . . . . . . . . . I T E M N0. I SOME T R I C NO. L OCAt l 0N . . . . E X AM. -

DESCRIP110N METHOD CRD H 3 1 22 RESTRAINT f(1 3) ISl 1 3 1 EAST CRD VT 3 CRD H 3142 RESTRAINT F(1 3) 151 1 3 1 WEST CRD VT 3 CRD H 3 1 14 RIGlD SUPPORT F(1 3) ist i 3 1 EASI tRD VT 3 CRD - H 3127 ANCHOR F(1 3) l$1 1 3*1 EAST CRD VT 3 CRD H 3 1 40 RIGID SUPPORT F(1 3) l$1-l 3 1 WEST CRD VT 3 l

1 CS 14 A 4 PIPE 10 PIPE 89.11 151 1 14 1 DRYWELL U145 UT60 MY CS 14 A 5 ELBOW TO PlPE 89.11 ISI 1 14 1 DRYWELL UT45 UT60 MT J

CS 14 A 7 ELBOW 10 PIPE 89.11 151 I 14*1 DRVWE LL UT ".5 1 UT60 l Mi  ;

CS 14 8 4 PIPE 10 PIPE B9.11 151 1 14 1 DRYWELL UT45 UT60 MT CS 14 B 5 ELBOW 10 PIPE 89.11 151 1 14 1 DRYWELL UT45 UT60 MT CS 14 B 7 ELBOW TO PIPE 89.11 151 1 14 1 DRYWELL UT45 UT60 MT CS 14 B+8 ELBOW TO ELBOW 89.11 151 1 14 1 DRYWELL UT45 UT60 M1 CS 14 B 9 PIPE TO ELBOW B9.11 1S1 1 14-1 DRYWELL UT45 UT60 Mi i CS- CB 14 F31 PIDE TO VALVE C3.11 Isi I-14 2A A RNR QUAD Mi CS GB 14 F46 VALVE TO PIPE C5.11 ISI 1 14 2A A RHR QUAD MT CS G8 14 F21 ELBOW TO PIPE C5.11 ISI t-14 2B WEST CR0 MT CS HL 14 2 4A FLANGE TO PIPE C5.11 151 1 14 28 10RUS ROOM Mi CS H-14 1 3SA ANCHOR F(1 3) ISI 1 14 2A A RHR QUAD VT 3 CS H 14 1-7SG CUIDE F(1 3) ISI 1 14 2A RWrU HX RM VT 3 CS H 14 1 41 SPRING HANGER F(1 4)  !$1 1 14 1 DRYWELL VT 3 VT-4 CS H 14 1 43 SPRING HANGER F(14) 151 1 14 1 -DRYWELL VT 3 VT-4 CS H 14 1 40 SPRING HANGER F(1 4) ISl*I 14 1 DRYWELL VT 3 VT 4 CS H 14 1 42 SPRING HANGER F(1 4) ISI l 14 1 DRYWELL VT 3 VT 4 CS H 14 1 3 SPRING HANGER F(1 4) 151-1 14 2A TORUS ROOM VT 3 VT*4 CS H 14 1 37 SPRING HANGER F(1-4) ISI-t-14 2A. EAST CRD vi 3 PAGE: -1

ENCLOSURE B PILGRIM NLCLE AR POWER STATION ADDITIONAL ASME XI SECOND TEd YE AR INTERVAL EXAMINA110NS l

TO BE PERFORMED DURlWG REFUEL OUT AGE B SCHEDULE PERMITilNG

. . . . . . . . . . . . . . . . . . . . SYSTEM I D COMPONE N T I D NO. . COMPONE N T . . . . . . . . . . . . I T EM NO. I SOME T R I C NO. LOC AT I ON . . . . E X AM. .

DESCRIPTICC METHOD VT 4 FW W 6 1 X9A ANCHOR F(1*3) 1S1 1 6 1 STEAM TUNNEL VT 3 FW H 6 1 109 SPRikG HANGER F(1 4) ISl 1 6 1 DRYWELL YT 3 YT 4 FW H 6 1 111 SPRING KANGER F(14) 151 l*6-1 DRYLELL VT 3 VT*4 HPCI EB 23 59HLi(4) SUPPORT LUGS C3.40 151 1 23 2 HPCI Ro0M MT 9PCI HE 26 175HL1(1) SUPPORT LUGS C3.40 ISI I 23 4 AUX BAY MT HPCI HB 23 FT3 VALVE TO P!PE C5.11 151 1 23 3 HPCI ROOM MT HPCI HB 23 F74 PIPE TO VALVE C5.11 151 1-23 3 HPCI ROOM MT HPCI EB 23 F13 VALVi TO PIPr C5.21 151 1 23 2 8 RHR VV RM MT UT45 U160 HPCI H 23 1-2SR LATERAL RESTRAINT F(1 3) ISI-1 23 4 HPCI ROOM VT 3 HPCI H 23 1 3SR LATERAL RESTRAINT F(1 3) ISI 1 23 4 HPCI ROOM VT-3 HPCI H 23*1 45R RIG 1D HANGER F(1 3) 151 1 23 4 HPCI ROOM VT 3 HPCl H 23 1 21 RIGlD MANGER F(1 3) ISI t 23 4 TORUS ROOM VT-3 HPCI H 23 1 80 SPRlWG HANGER F(1 4) ist-i 23 1 DRYWELL VT-3 VT 4 HPCI H 23 1 81 SPRING HAWGER F(1-4) ISI I 23 1 DRYWELL VT 3 VT 4 HPCI H 23 1 82 SPRING HANGER F(1 4) 161 1 23+1 DRYVELL VT 3 VT 4 HPCI . H 23 1 73 SPRING HANGER F(1 4) ISlal 23 1 TIP ROOM VT 3 VT 4 HPCI H+23 1 77 SPRING HANGER F(1 4) 151 1 23 1 STEAM TUNNEL VT 3 VT 4 HPCI H 23 1 15 SPRING HANGER F(14) 151 1-23 3 HPCI ROOH VT-3 VT 4 HPCI H 23 1 2 SPRING HANGER F(1 4) 151 1 ?3 5 TORUS ROOM VT 3 VT 4 HPCI H 23 1-4 SPRING HANGER F(1 4) 151 1 23 5 TORUS ROOM VT 3 VT 4 MS 1 A 10HL1(4) HANGER LUGS B10.10 151 1 1 1 DRYWELL MT MS 1 C 10HL1(4) SUPPORT LUG B10.10 ISI t 1 1 DRYWELL MT MS 1 D 10HL1(4) SUPPORT LUG B10.10 ISI t 1-1 DRYWELL MT MS 1 AR 2 WELD TO PIPE B9.11 ISI 1 1 1 DRYWELL MT UT45 UT60 MS 1 AR-3 PIPE TO FLANGE B9.11 151 1 1-1 DRYWELL MT PAGE: 2

ENCLOSURE B PILCRIM NUCLEAR POWER STAilDN ADDil10NAL ASME XI SECOND TEN YEAR INTERVAL EXAMINATIONS TO BE PERFORMED DURING REFUEL DUTAGE 8 SCHEDULE PERMlifikG

.......... .......... SYSTEM ID COMPONENT 1D NO. . COMPONEN T. . . . . . . . . . . . ITEM NO ISOMEIRIC NO LOCAll0N. . . EXAM..

DESCRIPil0N METHOD U145 U160 MS 1 DR1 2 WELDOLET TO PlPE B9.11 ISI-I 1-1 DRYWELL Mi UT45 uf60 MS 1 DR13 PIPE 10 FLANGE B9.11 ISI-l.1 1 DRYWELL MT UT45 U160 MS 1 SD 9 FLUED HEAD TO PlPE B9.21 IS! t 1 1 STEAM TUNNEL MT MS H 1 1 HA3 SPRING HANGER f(14) 151 1 1 1 DRYWELL VT 3 VT 4 MS H 1 1*H82 SPRlWG HANGER f(1 4) l$1 1 1 1 DRYWELL VT 3 VT 4 MS H 1 1-SG2 SNUBBER F(1 4) ISI l 1 1 DRYWELL VT 3 VT-4 RBCCW H 30132 RIGID SUPPORT F(1 3) l$1*l 30 1 TORUS ROOM VT 3 RBCCW H 30 1 64SA ANCHOR f(1 3) 151 I 30 2 PIPEWAY VT 3 RCIC HL 13 F665 FLANGE TO PIPE C5.11 151 1 13 3 TORUS ROOM MT RCIC HL 13 F667 ELBOW TO NO2ZLE C5.11 151 1 13 3 TORUS ROOM MT RCIC H 13 1 49 SPRING HANGER F(14) 1S1 1 13 1 DRYWELL VT 3 VT 4 j- RCIC H 13 1 50 SPRING HANGER F(1 4) 151 1 13 1 DRYWELL VT 3 l- VT 4 4

REClkC H 2 1 H2 SPRING HANGER F(1 4) ISI l*2R B DRYWELL VT 3 VT 4

j. RECIRC H 2 1 H19 SPRING HANGER F(14) ISI 1 2W B DRYWELL VT 3 VT 4 RFR HL 10 152HLi(2) SUPPORT LUGS C3.40 IS1 1 10 5B B RHR QUAD MT RHR GS 10 F164 ELBCW TO VALVE C5.11 151 1 10 3B 0 RHR QUAD MT RHR GB 10 F46A PIPE TO PIPC C5.11 ISI t 10 44 A R.9R VV RM Mi RHR CB 10 16 20 TEE TO REDUCER C5.11 ist-I 10 4A A RHR QUAD Mi RHR HL*10 F105 ELB0s' 10 PIPE C5.11 ISl*l 10 4A A RHR QUAD MT RHR CB 10 F62A PIP 1 TO VALVE C5.11 ISI 1 10 4A A RHR VV RM HT ear GB 10+F67 REDUCER TO VALVE C5.11 IS; I 10 4A A RHR QUAD MT

. RHR CB 10 3 5C PIPE TO ELBOV C5.11 1s1 1 10 48 TORUS ROOM Mi RHR G8 10 3-5E ELBOW TO PIPE C5.11 151-1 10 48 10RUS ROOM Mi RHR CB 10 15 1E TEE TO TEE C5.11 151 1 10 4B CRD ouA0 MT PAGE: 3

ENCLOSURE B

. . o PlLCRIM NUCLEAR POWER STATION j -

ADDITIONAL ASME XI SECOND TEN YEAR IN1ERVAL EXAMikAlloNS 10 BE PERFORMED DURlWC REFUEL OUTAGE 8 SCHEDULE PERMITTING

.......... . . . . . . . . . . SYST EM ID COMPONE NT ID NO. . COMPONE NT . . . . . . . . . . . 11EM NO I SOME TR I C kO. LOCAil0N , . . . EX AM. .

DESCRIPil0N METHOD RHR CB 10 F13 PIPE 10 ELBOW C5.11 151 1-10 4B TORUS ROOM MT kHR GL 10 F102 VALVE TO PENE1RAlloN C5.11 151 1 10 5B TIP ROOM MT RHR HL 10 F76 ELBOW 10 N0ZZLE C5.11 151 1 10 5B 10RUS ROOM Mi RHR HL 10 F73 PIPE TO N0ZZLE C5.11 151 1 10 5B 10RUS ROOM MT RHR H 10 1 44SA ANCHOR F(1 3) ISI !*10 1B TORUS ROOM VT 3 RHR H 10 1 455R CUIDE F(1 3) 151 1 10 1B TORUS ROOM VT 3 RHR H 10 1 495G GulDE F(1 3) 151 1 10 1B A RHR VV RM VT 3 RHR N 10 1 19 Ricl0 HANGER F(1 3) ist i 10-2A TORUS ROOM VT 3 RHR H 10 1 20 RIGID SUPPORT F(1 3) ISI t 10 2A TORUS R00M VT 3 RHR H 10 1*21 RIGID HANGER F(1 3) ISt i 10 2A TORUS ROOM VT 3 RHR H-10 1 22 RIGID SUPPORT F(1 3) ist i-10 2A 10RUS ROOM VT 3 RHR H 10 1-23 RIGID HANGER F(1 3) ist 1 10 2A TORUS ROOH VT 3 RHR H 10127SR LATERAL RESTRAINI F(1 3) 151 1 10 28 B RHR QUAD vi 3 RHR d 10 1 121 RIGID HANGER F(1 3) 151 1 10 28 B RHR QUAD vi 3 RHR H 10 1 142 RIGID HANGER F(1-3) ISI 1 10 3A A RHR QUAD VT 3 RHR H 10 1 99S LATERAL RESTRAINT F(1 3) 151 1 10 38 8 RHR QUAD VI 3 RHR H 10 1 89SA ANCHOR F(1 3) ist i 10 4A A RHR QUAD VT 3 RHR H 10 1 52 RIGID HANGER F(1 3) Isl-1 10 4A TORUS ROOM VT 3 RHR H 10 1 87SA ANCHOR F(1 3) ISI t 10 4A A RHR QUAD VT 3 RPR H 10 1 615A ANCHOR F(1 3) IS!*l*10 48 TORUS ROOM VT 3 RHR H 10 1 62 RIG 10 MANGER F(13) 151 1 10 48 TDRUS ROOM VT 3 RHR H 10 1 41SG GUIDE F(1 3) 131 1 10 50 B RHR QUAD vi 3 RHR H 10 1 111 GulDE F(1 3) ISI t 10 58 B RHR QUAD VT 3 RHR H 26 1 3SA ANCHOR F(1 3) ISl*l 10 5B B RHR QUAD VT 3 RHR H 10-1 134 SPRING MANGER F(1 4) 1S1 1 10 1B A RHR QUAD VT 3 VT-4 RHR H 10 1 355 SPRING HANGER F(1 4) ISt I 10 3A A RHR QUAD vi 3 VT 4 RHR H 10 1 199 SPRING MANGER F(1 4) ISI 1 10 4A RWCU HX RM VT 3 VT 4 RHR H 10-1 82 SPRING HANGER F(14) 151-1 10 48 10RUS ROOM VT 3 VT 4 RWCU H 12 1 1463 CUIDE F(1 3) 151 1 12 1 DRYWELL VI 3 RWCU H 11-1 115 RIGID HANGER F(1 3) l$1-1-12 1 RWCU HX RM VT 3 RWCU H 12 1 111 GulDE F(1 3) ISI t 12 2 A RHR VV RM RWCU H 12 1 112 CulDE F(1 3) ISI t 12 2 A RHR VV RM VT 3 RWCU H 12 1 8 SPRING HANGER F(14) 1S1-1 12 2 A RHR VV RM VT 3 VT-4 SBLC B-11 181A SOCKET 10 PIPE P9.40 151-1 11 1 RB 74' PT fBLC B 11-1818 PIPE 10 SOCKET 89.40 ISI-l-11 1 RB 74' PT PAGE: 4 l

_ .. .- +

ENCLOSURE B

,' PlLCRIM NUCLEAR POWER STA110N

.. _ ADDiflONAL ASME XI SECOND TEN YEAR INTERVAL EXAMINATIONS-TO BE PERFORMED DURING REFUEL'0UTAGE 8 SCHEDULE PERMlTI!NG

........... .......... SYSTEM 10 UOMPONENT 10 No. . COMPONENT. . . . . . ... . . . ITEM NO. ISOMETRIC WO. LOCATION.. . . EXAM..

DESCRIPil0N MEikOO SSW H 291 1D62 GUIDE F(1*3) 151 1 29 1 SCdEEN HS VT 3 SSW H 29 1 1065 GUIDE F(1 3) 151 1 29 1 SCREEN HS VT 3 S$W H+29 1 13 RIGID MANGEP. F(1 3)  !$1 1 29 1 D AUX BAY VT 3 SSW H 29 1 22 RIGID HANGER F(1 3) 151-1 29 1 SCREEN HS VT 3 SSW H 29 1 5$R RIGID HANGER F(1 3) ISI t 29 1 8 AUX BAY VT 3

$$W H 29 1 2 RIGl0 NANCER F(1 3) IS l 29 1 A AUX BAY VT 3 e..

I l

l 1

i PACEt' 5 4

o Exams performed ENCLOSURE C

_. du,ripg 1990 maintenance outage.

PILGRIM NULLEAR POWER stall 0N

.. SAFETY RELATED ICSCC SUSCEPf!BLE WELDS SCHEDULED FOR EXAM! Nail 0N DURING REFUEL DUTAGE 8 IN ACCORDANCE WITH GENERIC LETTER 88 01

. . . . . . . . . . . . . . . . . . . . I GSCC. , . COMPONE NT 10 NO. . COMPONE NT . . . . . . . . . . . . SY ST EM I D 11 EM No I SOME T R I C NO. L OCAil 0N. . . .

CATEGORY DESCRIPil0N ICSCC A 14R A 13 VALVE 10 ELBOW CS B9.11 l$1-1-14 1 - DR Y WEtt ICSCC A 14R B 13 VALVE TO ELBOW CS B9.11 ISI 1 14 1 DRYWELL ICSCC A 2R N18 4 PIPE 10 TEE RECIRC B9.11 ISl 1 2R A DRYWELL IGSCC A 2R N2C-3 CROSS TO PIPE RECIRC B9.11 ISt i 2R A DRYWELL

!GSCC A 2R N1A 14 TEE TO PIPE RECIRC B9.11 IS! I 2R B DRYWE LL

  • IGSCC A 2R N2H 3 CROSS TO PIPE RECIRC B9.11  !$1*l 2R B DRYWELL IGSCC A 10R IA 5 VALVE 10 ELBOW RHR B9.11 1S1 1-10 1 DRYWELL
  • IGSCC A 10R 0 14 PlPE TO PIPE RHR 89.11 ISt i 10 1A DRYVELL ICSCC A 14 8-1 SAFE END TO NO22LE RPV B5.10 ISI-I 14 1 DRYWELL ICSCC A 12R 0 1A SWEEPOLET TO ELBOW RWCU 89.11 ISI 1 12-1 DRYWELL i IGSCC D 14 A 19 VALVE TO PIPE CS 89.11 151 1 14 1 RWCU HX RM I-ICSCC D 14R A 16 PENETRAil0N TO ELBOW CS B9.11 !SI-t-14 1 -DRYWELL DRf4 ELL ICSCC D 14R B 16 PENEIRAil0N TO ELBOW CS B9.11 1S1 1 14 1 DRYWELL 1GSCC D 14R B 21A PIPE TO PIPE CS 89.11 151 1 14 1 RB 51' ICSCC D 10 IA 14 PIPE TO FLUED HEAD RHR B9.11 151-1 10-1 A RHR VV RM ICSCC D 10-IA 15 VALVE TO PIPE RHR 89.11 1S1 1 10 1 A RHR VV RM ICSCC D 10R IA 12 PENETRAil0N TO ELBOW RHR 89.11 ISl*l-10 1 DRYWELL ICSCC D 2R N18 1 NO22LE TO SAFE END RPV B5.10 ISI-l 2R A DRYWELL IGSCC D 2R N2C*1 SAFE END 10 NO22LE RPV B5.10 ISt I 2R A DRYWELL ICSCC D 2R N20 1 SAFE END 10 NO22LE RPV B5.10 ISI 1 2R A DRYWELL IGSCC D 2R N2E 1 SAFE END TO N022LE RPV B5.10  !$1-1 2R A DRYWELL ICSCC D 2R*N2F 1 SAFE END TO NO22tf RPV B5.10 1S1 1 2R 8 DRYWELL IGSCC D 2R N2J 1 SAFE END To kO22LE RPV B5.10 ISI t 2R B DRYWELL IGSCC D 12 0 28 PIPE 10 ELBOW RWCU 89.11 ISI t 12 1 RWCU HX RM IGSCC D 122 0 23 ELBOW TO PENETRATION RWCU 89.11 ISl I 12 1 DRYWELL IGSCC D 12R 0 32 PIPE TO VALVE RWCU B9.11 151 1-12 1 RWCU HX RM IGSCC D 12117 PIPE TO REDUCER RWCU 89,11 ISI t 12 2 A RHR VV RM IGSCC D 12 1 18 ELBOW TO PIPE RWCU 09.11 1S1 1-12 2 A RHR VV RM IGSCC D 12 1 19 PIPE TO ELBOW RWCU 89.11 151 1 12 2 A RHR VV RM IGSCC D 12 1 21 PIPE TO ELBOW RWCU 89.11 ISI-I-12 2 A RHR VV RM IGaCC D 12 I 23 PIPE TO ELBOW RWCU 89.11 151 1 12 2 A RHR VV RM IGSCC D 12 1-23A P!PE TO P!PE RWCU B9.11 1S1-1 12 2 EAST CRD IGSCC D 12 1-24 ELBOW 10 PIPE RWCU 89.11 l$l-1 12 2 EAST CRD IGSCC D 12 1 25 PIPE 10 ELBOW RWCU B9.11 !S1 1-12 2 EAST CRD I IGSCC D 12 I 25A PIPE TO PIPE RWCU 89.11 1S1 !*12 2 EAST CRD IGtCC D 12 I 26 ELBOW TO PIPE PVCU 89.11 ISI I 12 2 EAST CRD ICSCC D 12127 PIPE TO Elf;w RWCU 69.11 1S1-1 12 2 EAST CRD ICSCC 0 12 1 28 ELBOW TO PIPE RWCU 69.11 151 1-12-2 RWCU HX RM IGSCC D 12 1-29 PIPE 10 ELBOW RWCU 89.11 ISI 1 12 2 RWCU HX RM ICSCC D 12 I 32 ELBOW 10 PIPE RWCU 89.11 ISI 1 12 2 RWCU HX RM l ICSCC D 12*I 33 PIPE TO ELBOW RWCU 89.11 ISI 1 12 2 RWCU NX RM l

ICSCC E RPV N9A*1 NO22LE TO SAFE END RPV B5.10 1S1 1 54 4 DRYWELL l

PAGE: 1 l

I l

l l

  • Exams perforned ENCLOSURE C duriticf l990 main,tenance outage. PILcRIM NuctEAR POWER STAfiOH

, SAFETY RELATED ICSCC SUSCEPilBLE WELDS SCHEDULED FOR EXAMINAfl0N DURIN0 REFUEL OUTAGE 8 IN ACCORDANCE WITH GENERIC LETTER 88 01

.......... .......... ICSCC... COMPONENT ID NO.. COMPONENT............ SYSTEM ID ITEM No ISOMETRIC NO. LOCA110N....

CATEGORY DESCRIP110N ICSCC G DB/DC 14 3002 5 1 ELBOW 10 PIPE CS C5.21 ISI t-14 2A RWCU HX RM IGSCC G DC-14 F31 PIPE 10 VALVE CS C5.21 ISt-t 14 2A RWCU HX RM ICSCC G DB/DC 14 3001 4 1 PIPE 10 PIPE CS C5.21 151 1 14 28 RB $18 ICSCC C DC 14 F1 PIPE 10 VALVE CS C5.21 151 1 14 2B/' is $1' ICSCC C DB/DC 10 3002 3 3 PIPE TO PIPE RHR C5.21 IS! I 10 4A A RHR W RM ICSCC G DC-10 F9 PIPE 10 VALVE RHR C5.21 ISI t 10 4A A RHR VV RM ICSCC C 08/DC 10 300121 ELBOW 10 PIPE RHR C5.21 151-1-10 4B B RHR W RM ICSCC G DC-10-F10R PIPE TO VALVE RHR C5.21 1st-1 10 48 8 RHR VV RM ICSCC G 311 NO2ZLE TO CAP RPV B5.10 151 !-3 1 DRYWELL e..

PAGE: 2

1. E ':I-  :

., ENCLOSURE D PILGRIN NUCLEAR P0HER STATION--

MODIFIED IGSCC INSPECTION SCHEDULE (REFERENCE'BECo LETTER 89.084)

CATEGORY DELETED FROM RF0 8 ADDED TO RF0 8 A 14R-A-11A U A 14R-A-13 A 14R-B-13 A 2R-N2C-3 A 2R-NIA D 14-A-17 0 14-A-18:

0- 12-0-29 .,

D ~12-0-30 '

D 12-0-31 D 12-I-23A 0- 12-I-24 0- 12-I-25A D 12-I-25 t'

D- 12-I-26  ;

D- 12-I-27:

.0- 12-I-33:

-- D 12-I-30 I

, D 12-I-31  !

g i

1 i

j :.

<r w -- m, e p ~ _ _ _ _ a-&e -___ n w w --- .%._r, -

. -,----,----,m ,

w**

. o- .

ENCLOSURE E d

PILGRIM NUCLEAR POWER STATION NON-SAFETY RELATED IGSCC SUSCEPTIBLE HELDS SCHEDULED FOR EXAMINATION IN ACCORDANCE WITH GENERIC LETTER 88-01 AND BECO LETTER 2.90.140 DURING REFUEL OUTAGE 8 IGSCC CATEGORY HELD NO, QESCRIPTION S1SlfB JSOMETRIC LOCATION IGSCC D SH-12-6 Pipe to valve RHCU ISI-I-12-3 RHCU HX RH IGSCC D EAl2-1 Pipe to elbow RHCU 1S1-1-12-3 RHCU M RH IGSCC D EA12-2 Elbow to pipe RHCU 151-I-12-3 RHCU HX RH IGSCC D EAl2-3 Pipe to elbow RHCU ISI-I-12-3 RHCU HX RH IGSCC D EA12-4 Elbow to pipe RHCU ISI-I-12-3 RHCU HX RH IGSCC D SH-12-129 Pipe to elbow RHCU 151-1-12-3 RHCU HX RM-IGSCC D EAl2-12 Elbow to pipe RHCU 151-1-12-3 RHCU HX RH t

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