ML20100Q933

Submits Synopsis of ISI Tests & Exams Scheduled to Be Performed During 1996 Unit 2 Refueling Outage,Tentatively Scheduled to Start 960323

ML20100Q933
Person / Time
Site:	Cook
Issue date:	02/14/1996
From:	Fitchuk J AMERICAN ELECTRIC POWER CO., INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9603120177
Download: ML20100Q933 (40)

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(616 465-5901 AAGERfCAN ELECTRCC POWER Donald C. Cook Plant Unit 2 Docket No. 50-316 License No. DPR-74

Subject:

UNIT 2 REFUELING OUTAGE ISI U.S. Nuclear Regulatory Commission Document Control Desk Washington D.C.,20555 Attn.: Document Control Manager February 14,1996 The following is a synopsis of ISI tests and examinations scheduled to be aformed during the 1996 Unit 2 Refueling Outage which is tentatively scheduled to s!u March 23,1996.

Identification of specific valves (i.e. safety valves, check valves, etc.) can be i

obtained by referencing the Cook Plant Valve Test Program for the Second Ten Year inspection Interval.

1. Ten-Year ultrasonic examination eithe reactor vessel welds including 100% of the shell welds. (Will be performed by Southwest Research Institute)

2. Visual examination of the reactor internals including a special remote visual examination and mechanical agitation of selected former plate-core barrel bolts. (Will be performed by Master-Lee /B&W)

3. Eddy Current and ultrasonic examination of selected reactor head penetration welds in addition to repair of penetration #75. (Will be performed by Westinghouse)

4. Visual examination of disassembled check valves to check internal integrity and operability. (Will be performed by American Electric Power Personnel)

5. UT and surface examination of Class 1 and 2 pipe welds. (Will be performed by Southwest Research Institute and American Electric Power Personnel)

6. Visual Examination of Class 1,2, and 3 component supports. (Will be performed by American Electric Power Personnel) 1101nA 9603120177 960214 O

PDR ADOCK 05000316 G

PDR f /

o Synop' sis of Unit 1 ISI/IST Document Control Manager January 16,1996

7. System pressure testing of Class 1,2 and 3 systems. (Will be performed by American Electric Power Personnel)

8. Setpoint test three (3) pressurizer safety valves. (Will be performed by American l

Electric Power Personnel)

9. Setpoint test nineteen (14) class 2 and 3 safety valves. (Will be performed by

)

American Electric Power Personnel)

10. Check valve intemal examinations on a total of sixteen (17) valves in Class 1, 2 and 3 systems. (Will be performed American Electric Power Personnel)

Please see the attached listing for Class 1 and 2 welds scheduled to be examined per the Second Ten Year Interval Long Term Plan.

^

If there are any comments or questions or if further information is needed, please feel free to contact me at (616) 465-5901, extension 1410.

9.n 92Lk J.M. Fitchuk ISI/ Performance Engineer Attachments c: see distribution list 4

i

1 4

o c:

H.J. Miller, Region lli E.E. Fitzpatrick (w/o attachment)

G. Charnoff (w/o attachment)

J.R. Padgett - M1 Public Service Commission (w/o attachment)

D.R. Hahn - NFEM Section Chief (w/o attachment)

W.T. Russell - NRR Director (w/o attachment)

B. Bartlett - D.C. Cook Senior Resident inspector (w/o attachment)

J.R. Sampson - (w/o attachment)

P.G. Schoepf- (w/o attachment)

F.R. Pisarsky - (w/o attachment)

P.A. Barrett - (w/o attachment)

S.J. Brewer - (w/o attachment)

File l

I

i D.C. Cook Unit 2 l

1996 Refueling Outage i nservice Examination of Class 1 and Class 2 Components i

1 t

i s

9

+

g i

9-

s DATE: 02/13 96 COOK NUCLEAR PLANT UNIT 2 PAGE:

1

/

REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECONO INTERVAL CLA$$ 1 COMPONENTS REACTOR PRESSURE VESSEL AND CLOSURE HEAD ASME SEC. XI CALIBRATION BLCCX/

$UMMARY EXAMINATION AREA CATGY NDE

$!!E-SCHEDULE-ACCESS /

NUMBER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS VESSEL CIRCUMFERENTIAL WELDS (FIG NO A.1)

OCC100 2-RPV 8 B-A M-UT RV-1/11-CsCL-5-CCC AUGMENTED EXAMINATICN CN $ HELL UPPER $ HELL TO MIDDLE SHELL B1.11 WELDS PER 10CFR$0.55A.

U. CONT.

000200 2-RPV C B-A M.UT RV-1/11.CSCL-5-DCC EXAMINE IN ACCORDANCE WITH MIDDLE $ HELL TO LOWER SHELL 81.11 REG. GUIDE 1.150, REV.1.

U. CONT.

000300 2-RPV.D S-A M-UT RV-3/11.C$CL.5-DCC AUGMENTED EXAMINATION ON SHELL LOWER SHELL TO LOWER HEAD B1.11 WELDS PER 10CFR50.55A.

U. CONT.

1 VE5SEL LONGITUDINAL WFLDS (FIG NO A-1) 000400 2-RPV-VA1 5.A M-UT 11.CsCL-5.DCC A'UGMENTED EXAMINATION ON SHELL UPPER SHELL AT 22 DEG.

B1.12 WELDS PER 10CFR50.55A.

U. CONT.

000500 2 RPV-VA2 B-A M-UT 11-CSCL-5-DCC AUGMENTED EXAMINATION ON SHELL UPPER SHELL AT 113 DEG.

81.12 WELDS PER 10CFR50.55A.

U. CONT.

000600 2-RPV-VA3 8-A M-UT 11.CSCL-5-DCC AUGMENTED EXAMINATION ON SHELL UPPE'R SHELL'AT 247 DEG.

31.12 WELDS PER 10CFR50.55A.

U. CONT.

j 000700 2-RPV-VB1 B-A M-UT RV-1/11-CSCL-5-DCC EXAMINE IN ACCORDANCE WITH j

REG GUIDE 1.150, REV.1.

MIDDLE SHELL AT 170 DEG.

B1.12 U. CONT.

000000 2-RPV-VB2 8-A M-UT RV-1/11.CSCL-5-DCC AUGMENTED EXAMINATION ON SHELL MIDDLE SHELL AT 350 DEG.

B1.12 WELDS PER 10CFR50.55A.

U. CONT.

1 l

4 DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

2 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIDO, SECOND INTERVAL l

CLASS 1 COMPONENTS REACTOR PRESSURE VESSEL AND CLOSURE HEAD ASME SEC. XI CALIBRATION BLOCK /

SUMNARY EXAMINATION AREA CATGY NDE

$1ZE* SCHEDULE. ACCESS /

NUMBER' IDENTIFICATION ITEM No METH PROCEDURE LOCATION INSTRUCTIONS VESSEL LONGITUDINAL WELDS (8!G NO A-1) 000900 2.RPV.VC1 B.A M.UT RV.1/11.CSCL.5.DCC AUGMENTE3 EXAMINATION ON SHELL LOWER SHELL AT 90 DEG.

B1.12 WELDS PER 10CFR50.!5A.

U. CCNT.

l l

001000 2.RPV.VC2 B.A M-UT RV.1/11.CSCL.5.DCC AUGMENTED EXAMINAT!DN ON SHELL LOWER SHELL AT 270 DEG.

81.12 WELDS PER 1DCFR50.55A.

U. CONT.

l REACTOR VESSEL LOWER HEAD MERIDIONAL WELDS (FIG NO A 1) 001740 2.LHM.03.

B.A M.UT RV.3/11.CSCL.5.DCC EXAMINE ACCES$1BLE LENGTH OF MERIDIONAL WELD AT 129 DEG.

B1.22 WELD IN ACCORDANCE WITH REG.

U. CONT.

GUIDE 1.150, REV. 1.

VESSEL TO FLANGE WELD (FfG NO A.1) 001800 2.RPV.A B-A M.UT CSCL.5.DCC/CSCL.34.DCC EXAMINE 100% FROM SEAL SURFACE VESSEL To FLANGE B1.30 DURING 1ST PER100. EXAMINE l

U. CONT.

100% FROM VESSEL WALL DURING

• 3RD PERIDO. PERFORM EXAMINATIONS IN ACCORDANCE WITH REG. GUIDE 1.150, REV.1.

CLOSURE HEAD TO FLANGE WELD (F16 NO A.2) 001900 2.CHC.01 B.A MT RV.2 EXAMINE 33% (172*) IN HEAD TO FLANGE B1.40 UT B

ACCORDANCE WITH REG. GUIDE U. CONT.

1.150, REV.1 DURING EACH DESIGNATED OUTAGE.

1 l

l N077LE TO SMELL AND SHELL TO N077LE WELDS (FIG NO A.1) 002000 2.N1 1 B.D M-UT CSCL.5-DCC/CSCL.7-DCC EXAMINE FROM THE N0ZILE BORE INLET NCZZLE TO SHELL AT 293 B3.90 AND THE VESSEL WALL IN DEG.

U. CONT.

ACCORDANCE WITH REG. GUIDE 1.150, REV. 1.

1

. e DATE: 02/13/96 Coot NUCLEAR PLANT UNIT 2 PAGE:

3 REVI5!ON:

0 INSERVICE INSPECTION SCHEDULE QUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL class 1 COMPONENTS REACTOR PRESSURf VE$SEL AND CLOSURE HEAD ASME SEC. XI CALIBRATION BLOCK /

$UMMARY EXAMINATION AREA CATGY NDE

$12E. SCHEDULE.ACCES$/

NUMSER IDENTIFICATICN

! TEM NO METH PROCEDURE LOCAT!0N INSTRUCTIONS N0ZZLE TO THELL AND SHEL. 70 N0ZZLE WELDS (FIG NO A.1)

CC21CO 2.N1 0 B-D M.UT CSCL.5.DCC/CSCL 7-DCC EXAMINE FRCM THE N0ZZLE BCRE SHELL TO CUTLET N0ZZLE AT 338 83.90 DURING iST PERICO AND FRCM THE DEG.

U. CCNT.

VES$EL WALL DURING 3RD PERICO.

EXAMINE IN ACCCRDANCE WITH REG. GUIDE 1.150, REV. 1.

002200 2.N2.!

8.D M.UT CSCL-5 DCC/C5CL.7-DCC EXAMINE FROM THE N0ZZLE BORE INLET N0ZZLE To SHELL AT 247.B3.90 AND THE VESSEL WALL IN DEG.

U. CONT.

ACCORDANCE WITH REG. GUIDE 1.150, REY. 1. PERFORM SUPPLEMENTAL UT ON INDICAT!0N DURING 2ND QUTAGE.

002300 2.N2-0 3-D M-UT CSCL.5-DCC/CSCL-7.DCC EXAMINE FROM THE N0ZILE BORE SHELL TO QUTLET N0ZZLE AT 202 83.90 DURING 157 PERIOD AND FROM THE DEG.

U. CONT.

VESSEL WALL DURING 3RD PERICO.

EXAMINE IN ACCORDANCE WITH REG. GUIDE 1.150, REV.1.

002400 2.N3 1 0-D M.UT CSCL-5.DCC/CsCL.7.DCC EXAMINE FROM THE N0ZZLE BCRE INLET N0ZZLE TO SHELL AT 113 83.90 AND THE VESSEL WALL IN DEG.

U. CONT.

ACCORDANCE WITH REG. GUIDE 1.150, REV. 1 002500 2.N3 0 B-D M.UT 11.CSCL.5.DCC EXAMINE FROM THE N0ZZLE BORE SHELL TO QUTLET N0ZZLE AT 158 53.90 AND FROM THE VESSEL WALL.

DEG.

U. CONT.

EXAMINE IN ACCORDANCE WITH REG. GUIDE 1.150, REV. 1.

002600 2.N4 1 30 M.UT CSCL-5.DCC/CSCL.7.DCC EXAMINE FROM THE N0ZZLE BORE INLET N0ZZLE TO SHELL AT 67 B3.90 AND THE VESSEL WALL IN

.DEG.

U. CONT.

ACCORDANCE WITH REG. GUIDE 1.150, REV. 1.

l l

l l

1 i

1 PRGE-01 FEB 13 1996 AGENT-W3 RAM ITIN MulkRSTAUGH/ MIKE FITCHLT/ JIM 28 FEB 96 - WEDNESDAY AMERICAN 4341 COACH CLASS tQUIP-TURBOPROP LV: SOUTH BEND 215P NONSTOP MILES-84 CONFIRMED l

AR: CHICAG0/0 HARE 205P ELAPSED TIME- :50 OPERATED BY-SIMMONS AIRLINES SEAT-9D AMERICAN 1809 COACH CLASS-EQUIP-MD-80 JET LY CHICAGO /0 HARE 250P NONSTOP MILES-1041 CONFIRMED AR: SAN ANTONIO 536P ELAPSED TIME-2:46 l

AVIS 1 INTERMED 2/4 DR DROP-01 MAR CONFIRMED PICKUP-SAN ANTONIO SAN ANTONIO INTL APO RATE-37.95 DAILY GUARANTEED MILEAGE.00/MI CODE-2C CONFIRMATION-39934446056 EMBASSY SUITES' 02 NT/S - OUT 01 MAR CONFIRMED ES SAN ANTONIO INTL 2 ROOM /S / 1 KING GUARANTEE-CREDIT CARD 10110 HWY 281 NORTH RATE-114.00 GUARANTEED SAN ANTONIO TX 76216 PHONE-210 525-9999 FAX-210 525-0626 NAME-FITCHUK JIM CONFIRMATION-86094899

_l 01 MAR 96 - FRIDAY DELTA 552 COACH CLASS EQUIP-BCEING 727 JET LV SAN ANTONIO 250P NONSTOP MILES-1924 CONFIRMED AR: CINCINNRTI 610P ELAPSED TIME-2:20 SEAT-36E DELTA 1014 COACH CLASS EQUIP-BOEING 737 JET LV CINCINNATI 710P NONSTOP MILES-203 CCNF.IRMED 807P ELACSED TIME- :57 AR: SOUTH EEND SEAT-14B PLERAF RECDNFIRM FLIGHTS 72 HRS PRIOR TO FLIGHT DEPARTURE' AIRLINE TICKETS ARE NON-REFUNDABLE AND NON-TRANSFERABLE COO *THANK YOU FOR USING CRUISES AND TOURS ****

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AIR TRANSPORTATION 398.00 TAX 9 00 TTL 407.00 SUB TOTAL 407.00 CREDIT CARD PAYMENT 407.00-T0

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(616 465 5901 AMERfCAN ELECTRDC 90WER Donald C. Cook Plant Unit 2 Docket No. 50-315 License No. DPR-58

Subject:

UNIT 2 REFUELING OUTAGE ISI Arkwright Mutual Insurance Company 225 Wyma'n Street P.O. Box 9198 Waltham, Mass. 02254-9198 January 22,1996

Dear Mr. Muterspaugh:

The following is a synopsis of ISI tests and examinations scheduled to be performed during the 1996 Unit 2 Refueling Outage which is tentatively scheduled to start March 23,1996.

Identification of specific valves (i.e. safety valves, check valves, etc.) can be obtained by referen,cing the Cook Plant Valve Test Program for the Second Ten Year Inspection Interval.

1. Ten-Year ultrasonic examination of the reactor vesselwelds including 100% of the shell welds. (Wil' he performed by Southwest Research Institute)

2. Visual examination of the reactor internals including a special remote visual examination and mechanical agitation of selected former plate-core barrel bolts. (Will be performed by Master-Lee /B&W)

3. Eddy Current and ultrasonic examination of selected reactor head penetration welds in addition to repair of penetration #75. (Will be performed by Westinghouse)

4. Visual examination of disassembled check valves to check internalintegrity and operability. (Will be performed by American Electric Power Personnel)

5. UT and surface examination of Class 1 and 2 pipe welds. (Will be performed by Southwest Research Institute and American Electric Power Personnel)

6. Visual Examination of Class 1,2, and 3 component supports. (Will be performed by American Electric Power Personnel)

{

• 'Synoi5 sis of Unit 1 IS!/IST I

l Mr. M. Muterspaugh January 16,1996

7. System pressure testing of Class 1,2 and 3 systems. (Will be performed by American Electric Power Personnel) l

8. Setpoint test three (3) pressurizer safety valves. (Will be performed by American Electric Power Personnel) l l

9. Setpoint test nineteen (19) class 2 and 3 safety valves. (Will be performed by' American Electric Power Personnel)

10. Check valve internal examinations on a total of sixteen (16) valves in Class 1, 2 and 3 systems. (Will be performed American Electric Power Personnel)

Please see the attached the attached listing for Class 1 and 2 welds scheduled to be examined per the Second Ten Year Interval Long Term Plan.

If there are any comments or questions or if further information is needed, please feel free to contact me at (616) 465-5901, extension 1410.

i J.M. Fitchuk ISI/ Performance Engineer Attachments c: see distribution list 4

e

D.C. Cook Unit 2 1996 Refueling Outage Inservice Examination of Class 1 and Class 2 Components l

l l

r I

I 4

e b

e DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

1 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERICO, SECOND INTERVAL CLASS 1 COMPONENTS REACTOR PRESSURE VESSEL Am CLOSURE HEAD ASME SEC. XI CALIBRATION BLOCK /

SUMMARY

EXAMINATION AREA CATGY NDE SIZE-SCHEDULE-ACCESS /

NUMBER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS VESSEL CIRCUMFERENTIAL WELDS (FIG NO A-11 000100 2-RPV-B B-A M-UT RV-1/11-CSCL-5-DCC AUGMENTED EXAMINATION ON SHELL UPPER SHELL TO MIDOLE SHELL 81.11 WELDS PER 10CFR50.55A.

U. CONT.

000200 2-RPV-C B-A M-UT RV-1/11-CSCL-5-DCC EXAMINE IN ACCORDANCE WITH REG. GUIDE 1.150, REV. 1.

MIDDLE SHELL TO LOWER SHELL B1.11 U. CONT.

000300 2-RPV-D B-A M-UT RV-3/11-CSCL-5-DCC AUGMENTED EXAMINATION ON SHELL LOWER SHELL 70 LOWER HEAD B1.11 WELDS PER 10CFR50.55A.

=

=

U. CONT.

VESSEL LONGITUDINAL WELDS (FIG NO A-1) 000400 2-RPV-VA1 B-A M-UT 11-CSCL-5-DCC AUGMENTED EXAMINATION ON SHELL WELDS PER 10CFR50.55A.

UPPER SHELL AT 22 DEG.

81.12

=

U. CONT.

000500 2-RPV-VA2 B-A M-UT 11-CSCL-5-DCC AUGMENTED EXAMINATION ON SHELL WELDS PER 10CFR50.55A.

UPPER SHELL AT 113 DEG.

B1.12 U. CONT.

000600 2-RPV-VA3 B-A M-UT 11-CSCL-5-DCC AUGMENTED EXAMINATION ON SHELL WELDS PER 10CFR50.55A.

UPPER SHELL AT 247 des.

B1.12 U. CONT.

000700 2-RPV-VB1 B-A M-UT RV-1/11-CSCL-5-DCC EXAMINE IN ACCORDANCE WITH REG. GUIDE 1.150, REV. 1.

MIDDLE SHELL AT 170 DEG.

81.12 U. CONT.

000B00 2-RPV-VB2 B-A M-UT RV-1/11-CSCL-5-DCC AUGMENTED EXAMINATION ON SHELL WELDS PER 10CFR50.55A, MIDDLE SHELL AT 350 DEG.

81.12 U. CONT.

I i

DATE: 02/13/96 Coot NUCLEAR PLANT UNIT 2 PAGE:

2 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PER100, SECOND INTERVAL CLASS 1 COMPONENTS REACTOR PRES $URE VESSEL AND CLOSURE HEAD ASME J

SEC. XI CALIBRATION BLOCK /

SUMMARY

EXAMINATION AREA CATGY NDE

$1ZE-SCHEDULE-ACCESS /

NUMBER IDENTIFICATION ITEM No METH PROCEDURE LOCATION INSTRUCTIONS 1

l VESSEL LONGITUDINAL WELDS (FIG NO A-1) j 000900 2-LPV-VC1 B-A M-UT RV-1/11.aSCL-5-DCC AUGMENTED EXAMINATION ON SHELL i

LOWER SHELL At 90 DEG.

B1.12 WELDS PER 10CFR50.55A.

U. CONT.

001000 2-RPV-VC2 B-A M-UT RV-1/11-CSCL-5-DCC AUGMENTED EXAMINATION ON SHELL LOWER SHELL AT 270 DEG.

B1.12 WELDS PER 10CFR50.55A.

J U. CONT.

l I

REACTOR VESSEL LOWER HEAD MERIDIONAL WELDS (FIG NO A-1) j i

001740 2-LHM-03 B-A M-UT RV-3/11.CSCL-5-DCC EXAMINE ACCESSIBLE LENGTH OF WELD IN ACCORDANCE WITH REG.

MERIDIONAL WELD AT 129 DEG.

B1.22 U. CONT.

GUIDE 1.150, REV. 1.

VESSEL TO FLANGE WELD (FIG NO A-1) 001800 2-RPV-A B-A M-UT CSCL-5-DCC/CSCL-34-DCC EXAMINE 100% FROM SEAL SURFACE DURING iST PERIDO. EKAMINE VESSEL 70 FLANGE B1.30 U. CONT.

1003 FROM VESSEL WALL DURING 3RD PERIOD. PERFORM EXAMINATIONS IN ACCORDANCE WITH REG. GUIDE 1.150, REV. 1.

CLOSURE HEAD TO FLANGE WELD (FIG NO A-2)

B-A MT RV-2 EXAMINE 33% (172*) IN 001900 2-CHC-01 ACCORDANCE WITH REG. GUIDE HEAD TO FLANGE B1.40 UT B

U. CONT.

1.150, REV.1 DURING EACH DESIGNATED OUTAGE.

N0ZILE TO SHELL AND SHELL TO N0ZILE WELDS (FIG N0 A-1) 002000 2-N1.!

B-D M-UT CSCL-5-DCC/CSCL-7-DCC EXAMINE FROM THE N0ZZLE BORE AND THE VESSEL WALL IN INLET N0ZZLE TO SHELL AT 293 B3.90 DEG.

U. CONT.

ACCORDANCE WITH REG. GUIDE 1.150, REV.1.

\\

i DATE: 02/13/96 COOC NUCLEAR PLANT UNIT 2 PAGE:

3 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL class 1 COMPONENTS REACTOR PREjj,URE VESSEL AND CLOSURE HEAD ASME SEC XI CALIBRATION BLOCK /

SUMMARY

EXAMINATION AREA CATGY NDE SIZE-SCHEDULE-ACCESS /

NUMSER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS I

.................................................................==

_= =.............................................

N0ZZLE TO SHELL AND SHELL TO N0ZZLE WELDS (FIG NO A-1) 002100 2-N1-0 B-D M-UT CSCL-5-DCC/CSCL-7-DCC EXAMINE FROM THE N0ZZLE BORE SHELL TO QUTLET N0ZZLE AT 338 B3.90 DURING iST PERIDO AND FROM THE DEG.

U. CONT.

VESSEL WALL DURING 3RD PERICO.

EXAMINE IN ACCORDANCE WITH REG. GUIDE 1.150, REV. 1.

002200 2-N2-1 8-D M-UT CSCL-5-DCC/CSCL-7-DCC EXAMINE FROM THE N0ZZLE BORE INLET N0ZZLE TO SHELL AT 247 B3.90 AND THE VESSEL WALL IN DEG.

U. CONT.

ACCORDANCE WITH REG. GUIDE 1.150, REV.1. PERFORM SUPPLEMENTAL UT ON INDICATION DURING 2ND OUTAGE.

002300 2-N2-0 B-D M-UT CSCL-5-DCC/CSCL-7-DCC EXAMINE FROM THE N0ZZLE BORE ~

SHELL TO OUTLET N0ZZLE AT 202 83,90 DURING iST PERIOD AND FROM THE DEG.

U. CONT.

VESSEL WALL DURING 3RD PERIOD.

EXAMINE IN ACCORDANCE WITH REG. GUIDE 1.150, REV.1.

002400 2-N3-!

B-D M-UT CSCL-5-DCC/CSCL.7-DCC EXAMINE FROM THE N0ZZLE BORE INLET N0ZZLE TO SHELL AT 113 B3.90 AND THE VESSEL WALL IN DEG.

U. CONT.

ACCORDANCE WITH REG. GUIDE 1.150, REV. 1.

002500 2-N3-0 B-D M-UT 11-CSCL-5-DCC EXAMINE FROM THE N0ZILE BORE SHELL 70 OUTLET No!!LE AT 158 B3.90 AND FROM THE VESSEL WALL.

DEG.

U. CONT.

EXAMINE IN ACCORDANCE WITH REG. GUIDE 1.150, REV. 1.

002600 2-N4-1 B-D M-UT CSCL.5-DCC/CSCL-7.DCC EXAMINE FROM THE N0ZZLE BORE AND THE VESSEL WALL IN INLET N0ZZLE TO SHELL AT 67 B3.90 DEG.

U. CONT.

ACCORDANCE WITH REG. GUIDE 1.150, REV. 1.

l

,e DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

4 REVISION:

0 INSERVICE INSPECTION SCHEDULE QUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 1 COMPONENTS REACTOR PRES $UNE VE5SEL Ale CLOSURE HEAD ASME SEC. XI CALIBRATION BLOCK /

f

SUMMARY

EXAMINATION AREA CATGY NDE SIZE-SCHEDULE-ACCESS /

NUMBER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS i

(

N0ZZLE TO SHELL AND SHELL TO N0ZZLE WELDS (FIG NO A-1) l 002700 2-N4-0 B-D M-UT CSCL-5-DCC/CSCL-7-DCC EXAMINE FROM THE N0ZZLE BORD AND FROM THE VESSEL WALL.

SHELL TO OUTLET N0ZILE AT 22 83.90 DEG.

U. CONT.

EXAMINE IN ACCORDANCE WITH REG. GUIDE 1.150, REY.1.

N0ZZLE INSIDE RADIUS SECTIONS (FIG NO A-3) 002800 2-N1-I-IRS B-D M-UT IR-CSCL-8-DCC INLET N0ZZLE AT 293 DEG.

83.100 U. CONT.

l 4

003000 2-N2-I-IRS B-D M-UT IR-CSCL-8-DCC INLET N0ZILE AT 247 DEG.

83.100 U. CONT.

003200 2-N3-I-IRS B-D M-UT IR-CSCL-8-DCC INLET N0ZILE AT 113 DEG.

B3.100 U. CONT.

003300 2-N3-0-IRS B-D M-UT IR-CSCL-8-DCC OUTLET N0!!LE AT 158 DEG.

83.100 U. CONT.

003400 2-N4-I-IR$

B-D M-UT IR-CSCL-8-DCC INLET N0ZZLE AT 67,DEG.

83.100 U. CONT.

003500 2-N4-0-IRS B-D M-UT IR-CSCL-8-DCC OUTLET N0ZZLE AT 22 DEG.

B3.100 U. CONT.

REACTOR VESSEL PENETRATIONS (FIG NO A-3) j 003550 LOWER HEAD PENETRATIONS B-E VT-2 EXAMINE 25% (12 WELDS) DURING j

58 PENETRATIONS B4.13 THE SYSTEM HYDROSTATIC TEST, CONT.

.e DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

5 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 1 COMPONENTS REACTOR PRaaSURE VESSEL Als CLOSURE HEAD ASME SEC. XI CALIBRATION BLDCK/

SUMMARY

EXAMINATION AREA CATGY NOE SIZE-SCHEDULE-ACCESS /

{

NUMBER IDENTIFICATION ITL1 NO METH PROCEDURE LOCATION INSTRUCTIONS REACTOR VESSEL PENETRATIONS (FIG NO A-21 l

l l

003600 CLOSURE HEAD CRD PENETRATIONS B-E VT-2 EXAMINE 25% (20 WELDS) DURING 7B PENETRATIONS B4.12 THE SYSTEM HYDROSTATIC TEST.

CONT.

003610 CLOSURE HEAD VENT LINE B-E VT-2 EXAMINE DURING THE SYSTEM 1 PENETRATION B4.11 HYDR 0 STATIC TEST.

CONT.

N0ffLE TO SAFE-END AND SAFE-END TO N0ffLE WELDS (FIG NO A-3) 003000 2-RPV 1-02 B-F PT PL-3.0.CSCL-4-DCC SAFE-END TO N0ZZLE

• COLD LEG

• B5.10 M-UT I

SNDBX L1CL 004000 2-RPV-2-02 B-F PT PL.3.0-CSCL-4-DCC SAFE-END TO N0ZZLE

• COLD LEG

• B5.10 M.UT I

SNDBX L2CL 004100 2.RPV-3-01 B-F PT PL-3.0.CSCL.4-DCC N0ZZLE TO SAFE-END

• HOT LEG

• B5.10 M-UT I

SNDBX L3HL 004200 2-RPV-3-02 B-F PT PL-3.0-CSCL-4-DCC SAFE-END TO N0ZILE

• COLD LEG

• B5.10 M.UT I

SNDBX L3CL a

004300 2-RPV-4-01 B-F PT PL-3.0-CSCL-4-DCC N0ZZLE TO SAFE-END

• HOT LEG

• B5.10 M-UT I

$NDBX L4HL 004400 2-RPV.4-02 B-F PT PL-3.0-CSCL-4-DCC SAFE-END TO N0ZZLE

• COLD LEG

• B5.10 M-UT I

SNDBX L4CL

,e DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

6 REVISION:

0 INSERVICE INSPECTION SCHEDULE QUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 1 COMPONENTS PEACTOR PRESSURE VESSEL Ale CLOSURE HEAD ASME SEC. XI CALIBRATION BLOCK /

$UMMARY EXAMINATION AREA CATGY NDE SIZE.8CHEDULE-ACCES$/

NUMBER IDENTIFICATION ITEM No METH PROCEDURE LOCATION INSTRUCTIONS RPV INTERIOR SURFACES AND CORE SUPPORT STRUCTURES 006010 RPV UPPER INTERNALS & SURFACES B-N-1 VT.3 EXAMINE EACH PERIOD. AUGMENTED AREAS ACCESSIBLE DURING NORMAL B13.10 VT-1 ON BAFFLE PLATE REFUELING U. CONT.

FASTENERS!N ONE QUADRANT (90 j

DEG.) 0F LOWER INTERNALS.

006021 RPV-CS-LUGS 1 THROUGH 6 B.N-2 VT-3 EXAMINE WHEN CORE BARREL IS CORE SUPPORT LUGS B13.60 REMOVED.

U. CONT.

006040 2-RPV CORE SUPPORT STRUCTURE B-N-3 VT-3 EXAMINE WHEN REMOVED.

(WHEN REMOVED)

B13.70 U. CONT.

CONTROL ROD DRIVE HOUSING WELDS 006060 CONTROL A00 DRIVE HOUSING WELD B-0 PT EXAMINE THE WELD ON 10% (8) 0F 78 WELDS B14.10 B

THE PERIPHERAL CRDS.

U. CONT.

t 0

6 1

1

,e DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

7 REVISION:

O.

INSERVICE INSPECTION SCHEDULE I

OUTAGE 2 (1996), THIRD PERICO. SECOND INTERVAL 1

CLASS 1 COMPONENTS PRESSURIZER (FIGURE A-4)

ASME SEC. XI CALIBRATION BLOCK /

SUMMARY

EXAMINATION AREA CATGY NDE

$1ZE-SCHEDULE-ACCESS /

NUMBER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS N0ZZLE TO SHELL AND SHELL TO N0ZZLE WELDS 006970 14".2-RC 21 B-D MT PL-3.0-CSCL-4-DCC CODE RELIEF GRANTED FIRST SURGE N0ZILE TO LOWER HEAD B2.2 UT B

INTERVAL FROM PERFORMING UT CONT. PRT EXAMINATION FROM N0ZZLE SIDE PROVIDED THAT (1) A FULL VEE VOLUMETRIC EXAMINATION IS PERFORMED FROM THE VESSEL SIDE WHEN ACCESSIBLE AND (2)

SUPPLEMENTAL SURFACE.

N0ZZLE INSIDE RADIUS SECTIONS 007500 14*-2-RC.21.!R$

B-D UT IR-CS.33-DCC SURGE N0ZZLE TO LOWER HEAD B3.120 B

CONT. PRT HEATER CONNECTIONS / INSTRUMENT AND SAMPLE PENETRATI 007600 PRZ HEATER WELL PENETRATIONS B-E VT.2 EXAMINE ALL WELDS DURING 78 PENETRATIONS B4.20 SYSTEM HYDROSTATIC TEST.

CONT. PRT 007700 PRZ INSTRUMENT AND SAMPLE N0ZZ B-E VT-2 EXAMINE 25% (3 WELDS) DURING 9 PENETRATIONS B4.13 SYSTEM HYDROSTATIC TEST.

CONT. PRT N0ZZLE TO SAFE-E m AND SAFE-END TO N0ZZLE WELDS 008500 2-PRZ-26 B-F PT 3379032 (14-55 160 1.40)

AUGMENTED UT EXAMINATION SAFE-END TO N0ZZLE B5.40 UT B

REQUIRED USING 45 DEG.

CONT. PRT REFRACTED LONGITUDINAL WAVE PER NRC I.N. 90-30.

LOWER HEAD TO SUPPORT SKIRT WELD 008505 2-PRZ-20 B-H MT PL.1.5-CS-78 WELD CONFIGURATION REQUIRES VESSEL SUPPORT 88.20 B

SURFACE EXAMINATION ON THE CONT. PRT INSIDE AND OUTSIDE SURFACES.

INSIDE SURFACE EXAMINATION TO BE PERFORMED DURING TEN YEAR ISI 70 COINCIDE WITH OTHER

l l

P DATE: 02/j3/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

8 REVISION:

0 INSERVICE INSPECTION $CHEDULE OUTAGE 2 (1996), THIRO PERIOD, SECOND INTERVAL CLAS$ 1 COMPONENTS STEAM GENERATOR NO. 21 (FIGURE A.5)

ASME SEC. XI CALIBRATION BLOCK /

$UMMARY EXAMINATION AREA CATGY NDE

$1ZE.$CHEDULE. ACCESS /

NUMBER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS CIRCUNFERENTIAL WELDS 008600 STM-21 01 s.B UT RV.3/DCC-41 LOWER HEAD TO TU8E $HEET 82.40

.I CONT..L1 l

l s

I '

e 4

9 9

4 e

DATE: 02/13 96 COOK NUCLEAR PLANT UNIT 2

/

PAGE:

9 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRO PERIDO, SECONO INTERVAL CLASS 1 COMPONENTS STEAM GENERATOR No. 22 (FIGURE A-3)

ASME SEC. XI CALIBRATION BLOCC/

$UMMARY EXAMINAT10N AREA CATGY NDE S!!E.$CHEDULE. ACCESS /

NUMSER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCT!0NS CIRCUMFERENTIAL WELDS l

I 009500 STM.22-01 B.B UT RV.3/DCC.41 LOWER HEAD TO TUBE $HEET B2.40 I

CONT. L2 l

e e

t S

4 I

l

4 a

DATE: 02/13/96 COOK NUCLEAR P uMT UNIT 2 PAGE:

10 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL Cuss 1 COMPONENTS STEAM GENERATOR No. 23 (FIGURE A-5)

ASME SEC. XI CALIBRATION BLOCK /

$UMMARY EXAMINATION AREA CATGY NOE

$12E. SCHEDULE-ACCESS /

NUMBER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS CIRCUMFERENTIAL WELDS 010400 STM-23 01 B-B UT RV.3 LOWER HEAD To TUBE SHEET 82.40 1

3 CONT. L3 4

l l

l

s DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

11 REVISION:

O INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERICO, SECONO INTERVAL CLASS 1 COMPONENTS i

STEAM GENERATOR NO. 24 (FIGURE A.5)

ASME SEC. XI CALIBRATION BLOCK /

SUMMARY

EXAMINATION AREA CATGY NDE

$1ZE-SCHEDULE-ACCESS /

1 NUMBER IDENTIFICATION ITEM No METH PROCEDURE LOCATION INSTRUCTIONS a

N0ZZLE INSIDE RADIUS SECTIONS i

011400 STM-24 1.!R$

8.D UT IR.CSCL.24-DCC INLET N0ZZLE INSIDE B3.140 8

1 RADIUSSECTION CONT. L4 011500 STM-24 0-IRS 80 UT IR.CSCL-24-DCC OUTLET N0ZZLE INSIDE RADIUS B3.140 B

SECTION CONT. L4 N0ZZLE TO ELBOW AND ELBOW 70 N0ZILE WELDS 011600 STM-24 02 B.F PT CSS /CCS. MOCKUP-36-DCC FULL VOLUMETRIC UT EXAMINATION EL90W TO INLET N0ZZLE B5.70 UT B

REQUIRED DUE TO NRC CONT L4 COMMITMENT.

011700 STM.24-03 B.F PT CSS /CCS. MOCKUP.36.DCC FULL VOLUMETRIC UT EXAMINATION OUTLET N0ZZLE To ELBOW B5.70 UT 8

REQUIRED DUE TO NRC CONT. L4 COMMITMENT.

l 4

I i

i i

DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

12 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIDO, SECOND INTERVAL CLASS 1 COMPONENTS REACTOR COOLANT SYSTEM ASME SEC. XI CALIBRATION BLOCK /

SUMMARY

EXAMINATION AREA CATGY NDE

$!ZE-SCHEDULE-ACCESS /

NUMBER IDENTIFICATION ITEM No METH PROCEDURE LOCATION INSTRUCTIONS LINE 2-RC-17 (FIG NO A-6) 016000 2-RC-17-01N B-J PT

~ To BE DETERMINED SCHEDULED PER CONDITION REPORT 6-IN. N02ZLE (BRANCH 89.31 UT B

95-0781.

CONNECTION)

CONT. L1 1

015800 2-RC-17-08N B-J PT TO BE DETERMINED CODE RELIEF GRANTED FIRST 10-IN. N0ZZLE (BRANCH B9.31 UT B

INTERVAL FRON UT ON WELD DUE CONNECTION)

CONT. L1 TO WELD GE0 METRY. SCHEDULED PER CONDITION REPORT 95'-0781.

016200 2-AC-17-12 B.J PT 37-CCSS-X-3.0-9-DCC ELBOW 70 SAFE-ENO B9.11 UT I

SNDSX L1CL LINE 2-RC-18 (FIG NO A-7) 017000 2-RC-18-03N B-J PT TO BE DETERMINED SCHEDULED PER CONDITION REPORT 14.IN. N0ZZLE (BRANCH B9.31 UT B

95-0781.

CONNECTION)

CONT. L2 LINE 2-RC-19 (FIG NO A-8) 019200 2-RC-19-01 B-J PT 37-CCSS-X-3.0-9-DCC SAFE-E.ND TO PIPE 99.11 UT I

SNOBX L3HL LINE 2-RC-22 (FIG NO A-111 026500 2-AC-22 10 B-J PT 3378027 (4-SS-120 430)

ELBOW TO PIPE 99.11 UT B

PRESS. DH LINE'2-RC-28 (FIG NO A-17) 034200 2-RC-28-22 B.J UT 3378027 (4-SS-120.430)

SCHEDULED IN RESPONSE TO NRCB PIPE To TEE B9.11 8

88-08 $UPP. 2. SEE WCAP-12143 CONT. PRT SUPP. 1 FOR AUGMENTED UT REQUIREMENTS.

l

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DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

13 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 1 COMPONENTS REACTOR COOLANT SYSTEM ASME SEC. XI CALIBRATION BLOCK /

SUMMARY

EXAMINATION AREA CATGY NOE

$1ZE. SCHEDULE-ACCESS /

NUMBER IDENTIFI' CATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS LINE 2-RC-28 (FIG NO A-17A) 034300 2-RC-28-23 B-J UT 3378027 (4-55-120. 430)

SCHEDULED IN RESPONSE TO NRCB 88-08'SUPP. 2. SEE WCAP-12143 TEE TO PIPE 99.11 O

CONT. PRT SUPP. 1 FOR AUGMENTED UT REQUIREMENTS.

034400 2-AC-28-24 B-J UT 3378027 (4-55 120.430)

SCHEDULED IN RESPONSE TO NRCB PIPE TO ELBOW 99.11 8

88 08 $UPP. 2. SEE WCAP-12143 CONT. PRT SUPP. 1 FOR AUGMENTED UT j

REQUIREMENTS.

j i

t LINE 2-3C-30 (FIG NO A-19) l 041300 2-RC-30-06 B-J UT 3378027 (4-SS-120. 430)

SCHEDULED IN RESPONSE TO NRCB PIPE TO TEE B9.11 B

88 08 SUPP. 2. SEE WCAP.12143 CONT. PRT SUPP. 1 FOR AUGMENTED UT g

REQUIREMENTS.

]

LINE 2-RC-512 (F!G NO A-24) l 058400 2-RC-512-01 B-J PT j

BRANCH CONNECTION TO PIPE 89.40 B

CONT. L1 1

h 058500 2-RC-512-02 B-J PT PIPE TO ['90W B9.40 B

CONT. Li i

'058600 2-RC-512-03 8-J PT ELBOW TO PIPE 99.40 B

CONT. Li l

058700 2.RC-512-04 B-J PT PIPE TO ELBOW B9.40 B

CONT. L1

s l

l

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l DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

14 I

REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 1 COMPONENTS j

REACTOR COOLANT SYSTER ASME I

(

SEC. XI CALIBRATION BLOCK /

l

SUMMARY

EXAMINATION AREA CATGY NDE

$1ZE-SCHEDULE-ACCESS /

NUMBER IDENTIFIC* TION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS LINE 2-RC-512 (FIG NO A-24) 058800 2-RC-512-05 8-J PT EL30W TO' PIPE 89.40 8

CONT. L1 1

058900 2 RC-512 06 B-J PT PIPE TO ELa0W 89,40 g

CONT. L1 059000 2-RC-512-07 B-J PT EL80W TO PIPE 99.40 g

CONT. L1 059100 2-RC.512-08 B-J PT PIPE TO EL30W 99.40 B

CONT. L1 059200 2-RC-512-09 8-J PT EL90W 70 PIPE 39.40 B

CONT. L1 1

l 1

059300 2-RC-512-10 B-J PT

{

PIPE TO VALVE 89.40 B

CONT. L1 i

059400 2-AC-512-11 3-J PT VALVE TO PIPE 09.40 8

CONT. L1 059500 2-RC-512-12 8-J PT PIPE TO EL90W 89.60 8

CONT. L1 I

~

l It i

f'

^

i DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

15 l

l REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERICO, SECOND INTERVAL j

CLASS 1 COMPONENTS REACTOR COOLANT SYSTEN ASME j

SEC. XI CALIBRATION BLOCK /

SUMMARY

EXAMINATION AREA CATGY NDE SIZE-SCHEDULE-ACCESS /

t NUMBER IDENT!8ICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS LINE 2-RC-513 (FIG No A-25) 064400 2-AC-513-17 P-J PT PIPS TO TEE 89.40 B

j CONT. Li 065000 2-RC-513-22 B-J PT TEE TO PIPE 99.40 B

CONT. L1 06h100 2-RC-513-23 B-J PT PIPE TO MANIFOLD 89.40 8

CONT. L1 i

065200 2-RC-513-24 B-J PT MANIFOLD TO PIPE 59.40 B

CONT. L1 065300 2-RC-513-25 B-J PT PIPE To ELBOW 99.40 B

CONT. L1 i

065400 2-RC-513-26 B-J PT ELBOW TO PIPE 89.40 B

CONT. L1 i

065500 2-RC-513 27 B-J PT PIPE TO REDUCER 99.21 0

CONT. L1 LINE 2-RC-515 (FIG NO A-30) j 0B0700 2-AC-518-15 B-J PT VALVE TO PIPE B9.40 B

CONT. L4 I

e DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

16 REVISION:

0 INSERVICE INSPECTION SCHE 00LE OUTAGE 2 (1996), THIRD PERIG0, SECONO INTERVAL CLASS 1 COMPONENTS REACTOR C00LANT SYSTEM ASME SEC. XI CALIBRATION BLOCK /

SUMMARY

EXAMINATION AREA CATGY NDE SIZE-SCHEDULI-ACCESS /

NUMBER IDENTIFICATION ITEM No METH PROCEDURE LOCATION INSTRUCTIONS

=.... --

.........=-

==

LINE 2-RC-518 UIG No A-30) 080000 2-RC-518-16 8-J PT PIPE TO ELBOW 89.40 B

CONT. L4 080900 2-RC-518-17 B-J PT ELBOW TO PIPE B9.40 B

CONT. L4 a

081000 2-AC-518-18 B-J PT PIPE TO TEE 89.40 8

CONT. L4 081100 2-RC-518-19 B-J PT TEE TO REOUCER 89.40 B

CONT. L4 i

i 081200 2-RC-518-20 B-J PT TEE TO PIPE B9.40 B

CONT.,L4 081300 2-RC-518-21 B-J PT A

PIPE TO MANIFOLD 89.40 8

CONT. L4 081700 2-RC-518-25 B-J PT PIPE TO TEE B9.40 8

CONT. L4 081800 2-RC-518-26 B-J PT

' TEE TO RE00CER 99.40 8

CONT. L4

s.

DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

17 REVIS,0N :

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRO PER100, SECONO INTERVAL CLASS 1 COMPONENTS I

REACTOR COOLANT SYSTEN ASNE l

SEC. XI CALIBRATION BLOCK /

SUNNARY EXANINATION AREA CATGV NDE SIZE-SCHEDULE-ACCESS /

NUNSER IDENTIFICATION ITEN No NETH PROCEDURE LOCATION INSTRUCTIONS I

LINE 2-RC-518 (FIG No A-30) 081900 2-RC-518-27 B-J PT TEE TO PIPE 89.40 B

CONT. L4 082000 2-RC 518-28 8-J PT P!PE TO EL30W 89.40 8

i CONT. L4 082100 2-RC-518-29 B-J PT ELBOW TO PIPE 89.40 B

CONT. L4 i

I 082200 2-RC-518-30 8-J PT 1

1 PIPE TO FLANGE 99.40 B

CONT. L4 082400 2-RC-518-31 B-J PT FLANGE TO PIPE 89.40 8

CONT. L4 LINE 2-RC-519 (FIG NO A-31) 084800 2-RC-519 17 B-J PT PIPE 70 TEE 89.40 8

CONT. L4 084900 2-RC-519-18 S-J PT TEE TO PIPE 89.40 8

CONT. L4 0850b0 2-RC-519-19 B-J PT PIPE '70 VALVE 89.40 B

CONT. L4

i l

,,o DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

18 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECON0 INTERVAL CLASS 1 COMPONENTS l

l l

REACTOR COOLANT SYSTEN ASME j

SEC. XI CALIBRATION BLOCK /

SUNNARY EXANTAATION AREA CATGY NDE SIZE-SCHEDULE-ACCESS /

NUMBER IDE'.4TIFICAT10N ITEN No NETH PROCEDURE LOCATION INSTRUCTIONS i

LINE 2-RC-519 (FIG No A-31) 1 085100 2-RC-519-20 B-J PT VALVE TO PIPE 99.40 B

CONT.'L4 085200 2-AC-519-21 8-J PT PIPE TO FLANGE 89.40 g

CONT. L4 085400 2-RC-519-22 s-J PT l

TEE 70 PIPE 39.40 g

CONT. L4 i

J 1

i 4

I l

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i

i l

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,e DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

19

)

REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 1 CONPONENTS SAFETY INJECTION SYSTEM ASME SEC. XI CALIBRATION BLOCK /

SUNNARY EXAMINATION AREA CATGY NDE SIZE. SCHEDULE. ACCESS /

NUMBER IDENTIFICATION ITEN NO METH PROCEDURE LOCATION INSTRUCTIONS LINE 2.$1 58 (FIC NO A.35) 1 1

095300 2-51 58 06 8-K-1 PT 100% UT NOT FEASIBLE DUE To COLLAR TO PIPE B10.10 B

WELD CONFIGURATION.

CONT. L3 2

i i

S 4

l l

i

..i DATE: 02/13/96 Cook huCLEAR PLANT UNIT 2 PAGE:

20 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 1 COMPONENTS CHEMICAL AND VOLUME CONTROL SYSTEM ASME SEC. XI CALIBRATION BLOCK /

i l

SUMMARY

EXAMINATION AREA CATGY NDE SIZE. SCHEDULE-ACCESS /

NUMBER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS i

l LINE 2-CS-119 (FIG NO A 46) 129600 2-CS-119 12 9.J PT PIPE TO PIPE B9.21 0

CONT. L4 LINE 2-CS-121 (FIG NO A-48) 137200 2.CS.121 10 B.J PT PIPE TO BRANCN CONNECTION 39.21 8

CONT. L4 9

4 e

1 1

I

ae i

i DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

21 REVISION:

O INSERVICE INSPECTION SCHEDULE CUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 1 COMPONENTS i

VALVE PRESSURE RETAINING BOLTING (2* AND LESS) i ASNE SEC. XI CALIBRATION BLOCK /

i SUNNARY EXANINATION AREA CATGY NDE SIZE-$CHEDULE-ACCESS /

l NUMBER IDENTIFICATION ITEM No METH PROCEDURE LOCATION INSTRUCTIONS LINE 2-51-57 (F!G NO A-34) 220700 51-170-L2 B-G-2 VT-1 3

FLANGE BOLTING B7.70 5

CONT. L2 LINE 2-51-59 (FIG NO A-36) i 221200 $1 170-L4 B-G-2 VT.1 FLANGE BOLTING

'B7.70 8

CONT. L4 i

)

pME 2-51-63 (FIG NO A-40) 221800 $1-158-L2 B-G-2 VT-1 FLANGE BOLTING 87.70 8

CONT. L2 4

4 4

e i

.i i

DATE: 02/13/96 C00C NUCLEAR PLANT UNIT 2 PAGE:

22 REV!SION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 1 COMPONENTS WALWORTH MOTOR-OPERATED GATE VALVES (8' NOMINAL)

ASME SEC. XI CALIBRATION BLOCK /

?

SUMMARY

EXAMINATION AREA CATGY NDE SIZE. SCHEDULE.ACCES$/

NUMSER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS LINE 2-St-60 (FIG NO A-37) 225300 $1.IMO.315 s-M-2 VT.3 ONE WALWORTH GATE VALVE TO BE EXAMINED BY !&M PERSONNEL VALVE BODY INTERNAL SURFACE B12.50 ANNULUS DURING THE INTERVAL. THE' CHOICE DEPENDS ON MAINTENANCE REQUIREMENTS.

LINE 2-St.62 (FIG NO A.39) 225400 $1.IMO.325 B-M-2 VT-3 VALVE BODY INTERNAL SURFACE B12.50 ANNULUS l

s i

I l

1

l DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

23 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PER100, SECONO INTERVAL CLASS 2 CONPONENTS STEAN GENERATOR NO. 24 (FIGURE B-4)

ASNE SEC. XI CALIBRATION BLOCK /

i SUNNARY EXANINATION AREA CATGY NDE SIZE-SCHEDULE-ACCESS /

t NUNSER IDENTIFICATION ITEN NO NETH PROCEDURE LOCATION INSTRUCTIONS

]

CIRCUAFERENTIAL UELDS 300390 STN-24-10 C-A UT PL-3.0-CS-22-DCC SHELL TO HEAD C1.20 t

CONT. L4

)

I i

A

g e.o DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

24 REVISION:

O INSERVICE INSPECTION $CHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 2 COMPONENTS CHEMICAL AND VOLUME CONTROL TANK (FIGURE B-61 ASME SEC. XI CALIBRATION SLOCE/

$UMMARY EXAMINATION AREA CATGY NDE SIZE-SCHEDULE-ACCESS /

NUMSER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS INTEGRALLY WELDED VE5SEL SUPPORTS 30b670 2-CVCT.2Vs.10, 11, & 12 C-C PT C3.10 VCT RM i

l I

4 4

i i

. _ _ =.

.s

..'s i

DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

25 REVISION:

0 INSERVICE INSPECTION SCHEDULE l

OUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 2 COMPONENTS CTS HEAT EXCHANGER EAST (FIGURE B-7)

ASME SEC. XI CALIBRATION BLOCK /

SUMMARY

EXAMINATION AREA CATGY NDE SIZE-SCHEDULE-ACCESS /

NUMBER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS N0ZILE TO SHELL AND SHELL TO N0ZZLE WELDS 300674 E-CTSHEX-0UT C-8 PT j

SHELL 70 N0ZZLE C2.11 l

E CTS HXRM

\\

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4

s ee' e DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

26 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL class 2 COMPONENTS BORON 1NJECTION TANK (FIGURE B-9)

ASME SEC. XI CALIBRATION BLOCK /

SUMMARf EXAMINATION AREA CATGY NDE SIZE-SCHEDULE-ACCES$/

NUMBER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS INTEGRALLY WELDED VESSEL SUPPORTS 300920 2-BIT.Vs-3 C-C MT C3.10 BIT RM 300930 2-BIT-Vs-4 C-C MT C3.10 BIT RM e

4 4

4 se*o DATE: 02/13/96 COOK (4UCLEAR PLANT UNIT 2 PAGE:

27 REVISION:

0 INSERVICE INSPECTION SCHEDULE CUTAGE 2 (1996), THIRD PERIOD, SECONO INTERVAL CLASS 2 COMPONENTS EMERGENCY CORE COOLING ASME SEC. XI CALIBRATION BLOCK /

1 SUNNARY (XAMINATION AREA CATGY NDE SIZE. SCHEDULE-ACCES$/

NUMBER IDENTIFICATION ITEN No NETH PROCEDURE LOCATION INSTRUCTIONS 1

LINE 2-St-62 (FIG NO B-19 8 B-2) 311940 2-SI.62-025 C-F PT 3378029 (8-55 160. 81)

PIPE 70 ELB0W C5.21 UT U. CONT.

LINE 2-St-77 (FIG No B-22) 312450 2 51-77-025-PL 1 THROUGH &

C-C PT PIPE LUG C3.20 ANNULUS LINE 2-RH-19 (FIG NO B.31) 314660 2-RH-19-26F C-F PT PIPE TO EL90W C5.11 L

VESTIBULE LINE 2-RH-21 (FIG NO B-33) i 315330 2-RH-21-278 C-F PT 3378029 (8-58 160. 81)

ELSOW TO PIPE C5.21 UT L

VESTIBULE LINE 2-RH-31 (FIG N0 3-37 8 B-3) l 315935 2-RH-31 10F-PS C-C PT PIPE SUPPORT C3.20 I

ANNULUS

ee-,

DATE: 02/13/96 C008: NUCLEAR PLANT UNIT 2 PAGE:

28 REVISION:

0 INSERVICE INSPECTION SCHEDULE OUTAGE 2 (1996), THIRD PER100, SECONO INTERVAL CLASS 2 COMPONEhTS CONTAINMENT SPRAY SYSTEM ASME SEC. XI CALIBRATION BLOCK /

SUMMARY

EKAMINATION AREA CATGY NDE

$12E-SCHEDULE-ACCESS /

NUMBER IDENTIFICATION ITEM No METH PROCEDURE LOCATION INSTRUCTIONS

..........===-

LINE 2-CTS-10 (FIG NO B-44) 316540 2-CTS-10-12F C-F PT 10-SS-40. 365-26-DCC 7.5% AUGMENTED UT REQUIREMENT.

VALVE TO PIPE C5.11 UT TO BE EXAMINED EACH INTERVAL.

W CTS PPRM LINE 2-CTS-11 (FIG NO 8-45) 316970 2-CTS-11-225 C-F PT EL90W TO P!PE C5.11 L

VESTIBULE LINE 2-CTS-13 (FIG NO 8-47) 317360 2-CTS-13-095 C-F PT 10-SS-40. 365-26-DCC 7.5% AUGMENTED UT REQUIREMENT.

TEE TO ELB0W C5.11 UT To BE EXAMINED EACH INTERVALJ E CTS PPRM LINE 2-CTS-14 (FIG NO B-48) 317660 2-CTS-14-01F C-F PT N0ZILE TO REDUCER C5.11 E CTS HXRM l

317680 2-CTS-14-035 C-F PT 10-SS-40. 365-26-DCC 7.5% AUGMENTED UT REQUIREMENT.

j PIPE TO ELB0W C5.11 UT TO BE EXAMINED EACH INTERVAL.

I E CTS HXRM

..m...._m.=__...m e a e'

• DATE: 02/13/96 COOK NUCLEAR PLANT UNIT 2 PAGE:

29 REVISION:

O INSERVICE INSPECTION SCHEDULE CUTAGE 2 (1996), THIRD PERIOD, SECOND INTERVAL CLASS 2 COMPONENTS FEEDWATER SYSTEM ASME SEC. XI CALIBRATION BLOCK /

SUMMARY

EXAMINATION AREA CATGY NDE SIZE. SCHEDULE.ACCES$/

NUMBER IDENTIFICATION ITEM NO METH PROCEDURE LOCATION INSTRUCTIONS l

LINE 2.FW-76 (FIG NO 8-56) 1 319590 2.FW.76-115 C.F NT REDUCER TO ELBOW C5.21 UT 8

CONT. L4 N

e S

6 9