ML20132F675
| ML20132F675 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/26/1996 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20132F673 | List: |
| References | |
| NUDOCS 9612260050 | |
| Download: ML20132F675 (68) | |
Text
PEACH BOTTOM ATOMIC POWER STATION UNIT 2 INSERVICE INSPECTION
SUMMARY
REPORT FOR THE OCTOBER 22,1994 TO OCTOBER 3,1996 PERIODIC INSPECTION DR DO O
77 G
TABLE OF CONTENTS Paaes Form NIS-1 Owners Report For Inservice l
Inspections 2
Introduction 1
Section 1 Sumraary of Examination Legend 1
Summary of in-Service inspection Results Prior to and During Unit 2, 11th Refuel Cycle 55 Sectiori 2 Summary of Reportable Conditions Observed During in-Service inspection 1
Section 3 Summary of ASME XI Repales and Replacements 3
l i
EORM NIS-1 INSERVICE INSPECTION REPORT PECO ENERGY COMPANY I
965 Chesterbrook Blvd.
Wayne, PA 19087-5691 Date: November 26,1996 l
Peach Bottom Atomic Power Station - Unit 2 Inspection Date:
1848 Lay Road October 22,1994 to Delta, Pennsylvania 17314 to October 3,1996 Commercial Service Date: Ju!y 5,1974 Gross Generating Capability: 1150 MWe Pennsylvania State identification Number B122001 (NB 3903)
{
i Component identification ASME Class 1,2, and 3 Components and other Augmented Components.
Abstract of inspections Performed, Conditions Observed, Corrective Measure Recommended and Taken are Attached.
Section 1 - Summary of Inservice inspection Results Section 2 - Summary of Reportable Conditions Observed Section 3 - Summary of ASME XI Repairs and Replacements Name of Inspector. James J. Fuhrman Name of Mailing Address of inspector's Employer:
The Hartford Steam Boiler inspection & Insurance Co.
610 Freedom Business Center Drive i
Suite 300 King of Prussia, PA 19406 j
l certify that the statements made in this report are correct and the examinations and corrective i
measures taken conform to the rules of the ASME Section XI Code, or Generic Letter 88-01, or other augmented requirements as applicable.
I ff f h
/
PECO Energy ISI Engineer - Nuclear Maintenance Division Date
FORM NIS-1 INSERVICE INSPECTION REPORT l
PAGE 2 i
l CERTIFICATE OF INSERVICE INSPECTION l
l 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of P5nnsylvania and employed by Hartford Steam Boiler inspection & Insurance Company of Hartford. Connecticut have inspected the components described in this Owners Data Report during the period 10/22/94 to 10/03/96 and state that to the best of my knowledge and belief the Owner has performed examinations and taken corrective measures described in this Owners Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, conceming the examinations and corrective measures described in this Owners Data Report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.
Date: ///A /%
i wM CommissionstD%RL hraw3 g1 sictors Signature National Board, State, Province & No.
1
INTRODUCTION During the period from October 22,1994 through October 03,1996 in-Service inspections were perforrried at Peach Bottom Atomic Power Station, Unit 2. Unit 2 was shutdown for a scheduled refuel outage during the period from September 13,1996 through October 3,1996. The inspections performed during this period were credited towards the third period of the second ten year interval.
Examinations completed during this period were performed by PECO Energy Company and General Electric Company in accordance with the requirements of ASME Section XI,1980 Edition with Addenda through Winter 1981.
4 in addition to ASME Section XI, other examinations were performed to meet the augmented inspection requirements of the following:
j l.E.Bulletin 80-13 Cracking in Core Spray Spargers NUREG-0619 BWR Feedwater Nonle and Control Rod Drive Retum Line Nonle Cracking Generic Letter 88-01 NRC Positiori on IGSCC in BWR Austenitic Stainless Steel Piping (including Supplement 1)
Generic Letter 94-03 Core Shroud Cracking SIL 474 Steam Dryer Drain Channel Cracking SIL 551 Jet Pump Riser Brace Cracking SIL 574 Jet Pump Adjusting Screw Tack Weld Failures SIL 588 Top Guide and Core Plate Cracking
- l i
a R
l Section 1 1
1 t
4 d
i a
SUMMARY
OF IN-SERVICE INSPECTION RESULTS l-PRIOR TO AND DURING UNIT 2,11TH REFUEL OUTAGE i
i PEACH BOTTOM ATOMIC POWER STATION 1
1 UNR 2 OCTOBER 22,1994 TO OCTOBER 03,1996 i
e i
J t
i l
e
l l
PEACH BOTTOM ATOMIC POWER STATION PAGE: 0 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, SECOND PERIOD, FIRST OUTAGE (1991)
REAC70R PRESSURE VESSEL i
q
\\/
ASME S 0EGE
()
SEC. XI T RCEF SLMMARY EXAMINATION AREA CATGY EXAM A E o 0 0 REMARKS NLMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T C R M R " CALIBRATION BLOCK "
SUMMARY
OF EXAMINATION LEGEND 1
Identification of system.
2.
Component identification and description.
3.
ASME Section XI Category and item Number applicable to the component. If there is an augmented requirement to perform an examination, then *N/A" will appear in this location.
l 4
Exam method (NDE) applicable to the component.
l 5.
NDE procedure used to perform the examination on the component.
6.
Exam Status:
a)
C-Completed b)
U=
Unscheduled Complete c)
P=
Preservice Complete d)
A=
Augmented Complete e)
E=
Expanded Scope Complete 7.
Examination resuits broken down into 5 categories described below:
)
a)
NOREC =
No recordable indications detected b)
RECOR =
Recordable indications detected c)
GEOM =
Geometric indications detected 1
d)-
REPOR =
Reportable indications which require corrective action to maintain structural adequacy 8.
Remarks field which contains specific information conceming the component examination or evaluation of examination result..
l
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DATE: 11/26/96 PEACH BOTTOM ATOMIC K 4R STATION UNIT 2 PAGEr 1
REVISION:
5 INSERVICE INSPECTION SUP94ARY I
SECOND INTERVAL, THIRD PERIOD, SECOND OtTTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS REACTOR PRESSURE VESSEL NR R M6 S OEGE SEC. XI T RCEP CUMMARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDElfrIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCX**
FEACTOR PRESSURE VESSEL (REF. DWG. NO. ISI-203-RV-21) 003250 CORE PLATE BOLTS B-N-2 VT-3 VT-PBM-202VC R1 C X--
- EXAMINED BOLT 5 AT PERIPHERAL CELL 8 B13.22 16-57 AND ANNL".,US REGION AT 0 & 270 DEG U, IWESSEL AZ.
l REACTOR PPESSURE VESSEL (RFF. DWG. NO. NONE) 003255 CORE PLATE BOLTS N/A VT-3 VT-PBM-202VO R1 A X
.- EXAMINED PER AUG-10, GE SIL NO 588 AT N/A PERIPHERAL CELL 8 16-57 AND ANNULUS FF,1NVESSEL REGION AT 0 & 270 DEG AZ.
VESSEL SUPPORTS (REF. DWG. NO ISI-203-RV-04) 008015 SUPPORT-1 F-A,B,C VT-3 MAG-CG-407 R5 C X--
STAB BAR e O DEG FO.00 DW, EL 195-0, 0 AZ 008025 SUPPORT-2 F-A,B.C VT-3 MAG-CG-407 R5 C X---
STAB BAR e 45 DEG F0.00 DW, EL 195 0, 45 AZ INTEGRALLY-WDED VSL SUPTS (REF. DWG. NO. ISI-203-RV-04) 008030 SUPPORT-3 (I A)
SUPPLEMENTAL VT-1 EXAM PERFORMED IN STAB EAR e 90 DEG B8.10 VT-1 MAG-CG-407 R5 X--.
AREAS INACCESSIBLE FOR MT.
DW, EL 195-0, 90 AZ VESSEL SUPPORTS 'REF. DWG. NO. ISI-201-RV-04) i 008035 SUPPORT-3 F-A,B,C VT-3 MAG-CG-407 R5 C X---
j STAB BAR e 90 DEG FC.00 l
DW, EL 195-0, 90 AZ l
!NTEGRALLY-WOED VSL SUP'S (REF. DWG. NO ISI-203-RV-04)
OC8040 SUPPORT-4 (IA)
B-H PT IP-PE.001 R4 C X---
SUPPLEMENTAL VT-1 EXAM PERFORFID IN STAB RAR e 135 DEG B8.10 VT-1 MAG-CG-407 R5 X---
AREAS INACCESSIBLE FOR MT DW, EL 195-0, 135 AZ 1
.s..
I I
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DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PACE:
2 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RT) f CLASS 1 CAEP STATUS COMPONENTS REACTOR PRESSURF VESSEL NR R
l MM S OEGE SEC. XI T RCEP j
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDUkE T CRMR " CALIBRATION BLOCK **
VECSEL SUPPORTS f9EF. DWG. NO ISI.203-PV-04) l 009045 SUPPORT-4 F-A,B.C VT-3 MAG-CG 407 RS C X. - -
STAB BAR e 135 DEC FO.00 DW, EL 195-0, 135 AZ CRD HOUSINGS fPEF. DWG. NO ISI-203-RV-03) l 011205 CRD HOUSING BOLTING B-G-2 VT 1 MAG-CG-407 R5 C X--X EXAMINED BOLTING FROM CELLS:06-31, FLANGE DOLTING B7.80 10-35, 10-43, 18-15, 18-35, 26 11, DW, SUB FILE ROOM 26 39, 26-47, 26-51, 30 19, 30 23, 1
DW, SUB-PILE ROOM 30-47, 34-43, 38-19, 38-43, 42-19, 42-27, 42 35, 46-31. SEE SECTION NO.2 FOR REPORTABLE CONDITIONS.
I JET PLHP NO 1 (P EF, DWG. NO. ISI-203-PV-14.15) 011252 JP201 ALL COMPONENTS B.N-1 VT.3 VT-PBM-202VC R1 C
- - EXAM INCLUDED VT-1 OF ADJUSTING SCREW B13.10 TACK NELDS PER GE SIL 574 AND AR #
I FF,INVESSEL,157.5 AZ A0789892, EVAL-01.
1 l
JET PLHP NO 1 fRFF. DWG. NO. ISI-203-RV-14) 011253 JP#01 BRACE ARM /VESS B-N-2 VT-1 VT-PBM-202VD R1 C X---
EXAMINED PER GE SIL 551 AND INCLUDED B13.20 BRACE ARM TO RISER PIPE WELD.
FF,INVESSEL,137.5 AZ JET PUMP NO 3 fPEF. DWG NO. IS!-203-RV-14.15) 011256 JP#03 ALL COMPONENTS B.N-1 VT-3 VT-PBM-202VO R1 A X. - - EXAMINED PER AR # A1048180, EVAL-01 B13.10 WHICH INCLUDES NCR # 94 00355.
FF,INVESSEL,127.5 AZ l
JET PLHP NO 4 (REF. DWG NO
'SI-203-RV-14.15) 011253 JPN04 ALL COMPONENTS B-N-1 VT-3 VT-PBM-202V0 R1 A X. - - EXAMINED PER AR # A1048160, EVAL-01 B13.10 WHICH INCLUDES NCR # 94 00355.
FF INVESSEL,112.5 A2 f
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
3 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 CAEP STATUS COMPONE!rIS PEAC*0R PRESSURE VESSEL NR R
ASME S OEGE SEC XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO RhWARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK
JET PUMP NO 9 (FEF. DWG. NO. !SI-203-RV-14.15) 011364 JPk07 ALL COMPONENTS B-N.1 VT-3 VT-PBM.202VO R1 A X---
EXAMINED PER AR # A1048180, EVAL-01 913.10 WHICH INCLUDES NCRS # 94-00355 &
FF,INVESSEL,67,5 AZ.
94 00352.
JET PUMP NO 10 (REF DWG, NO. ISI-203-RV-14.15) 01127D JPN10 ALL COMPONE!fIS B-N-1 VT-3 VT-PBM-202VO R1 A X...
EXAMINED PER AR # A1048180, 1 VAL-01 B13.10 WHICH INCLUDES NCR # 94-00355.
FF,INVESSEL,22.5 AZ.
JET PUMP NO 11 (REF. DWG. NO. ISI.203-RV 14.15) 011272 JPN11 ALL COMPONENTS B-N 4 VT-3 VT-PBM-202VD R1 C X..-
EXAM INCLUDED VT-1 OF ADJ' STING SCREW J
B13.10 TACK WELDS PER GE SIL 574 AND AA #
FF IWESSEL,337.5 AZ A0789892, EVAL.01.
JET P'.NP NO 11 IREF, DWG. NO ISI-203-RV-14) 011273 JP#11 BRACE ARM /VESS B-N-2 VT-1 VT-PBM.202VO R1 C X..-
EXAMINED PER GE SIL 551 AND INCLUDED B13.20 BRACE ARM TO RISER PIPE WELD.
FF,INVESSEL,337.5 AZ JET PUMP NO 12 (REF DWG. NO ISI-203 PV-14.15) 011274 JPW12 AI.L COMPONENTS B-N-1 VT-3 VT PBM-202VO R1 C X..-
EXAM INCLUDED VT-1 OF ADJUSTING SCREW B13.10 TACK WELDS PER GE SIL 574 AND AR #
FF,INVESSEL,322.5 AZ A0789892, EVAL-01.
JET PUMP NO 17 fREF. DWG. NO ISI-203-RV-14) 011275 JPS12 BRACE ARM /VESS B-N 2 VT-1 VT-PBM-202VO R1 C X-.
- EXAMINED PER GE SIL 551 AND INCLUDED B13.20 BRACE ARM TO RISER PIPE WELD.
FF,INVESSEL.322.5 AZ l
l
!LTE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
4 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL. THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS P E AC"f0R PRESSURE VESSEL NR R
ASME S OEGE SEC. XI T RCEP 1
SUPNARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHQD PROCEDURE T CRMR " CALIBRATION BLOCK" i
JET PUMP NO 13 fNEF, DWG. NO ISI.203-PV-14.15) 1 011376 JP813 ALL COMPONENTS B-N-1 VT-3 VT-PBM-202VO R1 C X..
. - EXAM INCLUDED VT-1 OF ADJUSTING SCREW B13.10 TACX WELDS PER GE SIL 574 AND AR #
FF,INVESSEL,307.5 AZ A0789892, EVAL-01.
JET PUvP NO 13 (REF. DWO. NO. ISI-203-PV-1g 011377 JP#13 BRACE ARM /VESS B.N.2 VT.1 VT-PBM-202VD R1 C X...
EXAMINED PER GE SIL 551 AND INCLUDED B13.10 BRACE ARM TO RISER PIPE WELD.
FF,INVESSEL,307.5 AZ l
JET PUMP NO 14 (REF. DWG. NO. TSI-203-RV-14,15) 011278 JPW14 ALL COMPONENTS B-N-1 VT-3 VT-PBM-202VD R1 C X-.. EXAM INCLUDED VT-1 OF ADJUSTING SCREW B13.10 TACX WELDS PER GE SIL 574 AND AR #
FP,INVESSEL,292.5 AZ A0789892, EVAL-01.
l JET PUMP NO 14 (REF. DWG. NO. ISI-203-RV.14)
J i
i 011279 JP#14 BRACE ARM /VESS B-N-2 VT-1 VT-PEM-202VO R1 C X..-
EXAMINED PER GE SIL 551 AND INCLUDED B13.20 BRACE ARM TO RISER FIPE WELD.
FF,INVESSEL,292.5 AZ JET POMP NO 15 (REF. DWG. NO. ISI.203-RV-14.15) 011280 JP#15 ALL COMPONENTS B-N-1 VT-3 VT-PBM.202V0 R1 C X- -- EXAM INCLUDED VT-1 OF ADJUSTING SCREW B a.10 TACK WELDS PER GE SIL 574 AND AR W FF,INVESSEL,277.5 AZ A0789892, EVAL-01.
JE' PUMP NO 15 fREF. DWG. NO ISI-203-PV-14) 011281 JP#15 BRACE ARM /VESS B-N 2 VT-1 VT-PEM 202VD R1 C X.-.
EXAMINED PER GE SIL 551 AND INCLUDED B13.20 BRACE ARM TO RISER PIPE WELD.
FF,INVESSEL,277.5 AE
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I DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
5 REVISION:
5 INSERVICE INSPECTION SUWARY SECOND INTERVAL, THIRD PERIOD, SECOND OUIAGE (96RF) i CLASS 1 CAEP STATUS COMPONENTS REACTOR PRESSURE VESSEL NR R
ASME S OEGE SEC. XI T. R C E P SUt9tARY EXAMINATION AREA CATGY EXAM AEOOO REMARKS
'5 t
NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRHR ** CALIBRATION BICCK'*
I
}
l I
JET PUMP NO 16 (REF. tWG. NO. ISI-203-RV-14 3 i
011282. JP#16 ALL COMPONENTS B-N.1 VT-3 VT-PBM-202VD R1 C X.-.
EXAM INCLUDED VT-1 OF ADJUSTING SCREW f
B13.10 TACK WELDS PER GE SIL 574 AND AR #
FF,INVESSEL.262.5 AZ A0789892, EVAL-01, j
f
?
)
JET PUMP NO 16 (REF. DWG. NO. ISI-203-PV-14) f 011283 JP816 BRACE ARM /VESS B-N-2 VT-1 VT-PBM-202VO R1 C X-..
EXAMINED PER GE SIL 551 AND INCLUDED B13.20 BRACE ARM TO RISER PIPE WELD.
FF,INVESSEL,262.5 AZ f
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)
?
JET PUMP NO 17 (REF. DWG. NO. ISI-203-RV-14.15)
I i
I 011284 JP817 ALL COMPONENTS B-N-1 VT-3 VT-PBM-202VD R1 C X...
EXAM INCLUDED VT-1 OF ADJUSTING SCREW B13.10 TACK NELDS PER GE SIL 574 AND AR #
_ I FF,INVESSEL,247.5 AZ.
A0789892, EVAL.01.
l i
i JET PUMP NO 17 (REF. DWG. NO. ISI-203-RV-14)
+
011285 JPf1? BRACE ARM /VESS B-N-2 VT-1 VT-PBM-202VD R1 C X---
EXAMINED PER GE SIL 551 AND INCLUDED l
B13.20 BRACE ARM TO RISER PIPE NELD.
FF,INVESEL,247.5 AZ.
'I l
l JET PUMP NO 18 IREF. DWG. NO. ISI-203-RV-14.15) 011286 JP#18 ALL COMPONENTS B-N-1 VT-3 VT-PBM-202VD R1 C X...
EXAM INCLUDED VT-1 OF ADJUSTING SCREW B13.10 TACK NELDS PER GE SIL 574 AND AR #
FF.INVESSEL,232.5 AZ A0789892, EVAL-01.
JET PUMP NO 18 IREF. DWG. NO. ISI-203-RV-1Q t
l l
011287 JPW18 BRACE ARM /VESS B-N-2
'Tb 1 VT-PBM-202VO R1 C X..-
EXAMINED PER GE SIL 551 AND INCLUDED B13.20 BRACE ARM TO RISER PIPE WELD.
i l
l FF,INVESSEL,232.5 AZ 4
I 1
5 l
1 l
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i DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
6 REVISION:
5 INSERVICE INSPECTION SLM4ARY SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 C JP STATUS COMPONENTS REACTOR PRESFORJ VESSEL NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK'*
JET PLHP NO 19 (REF. DWO. NO. ISI-203-RV-14.15) 011280 JP#19 ALL COMPONENTS B-N-1 VT-3 VT-PBM 202VD R1 C X. -. EXAM INCLUDED VT-1 OF ADJUSTING SCREW B13.10 TACK WELDS PER GE SIL 574 AND AR #
FF,1NVESSEL,217.5 AZ A0789892, EVAL-01.
JET Pf.HP NO 19 (REF. DWG. NO. ISI-203-RV-14) l 011289 JPS19 BRACE ARM /VESS B N-2 VT-1 VT-PBM-202VD R1 C X---
EXAMINED PER GE SIL 551 AND INCLUDED I
B13.20 BRACE ARM TO RISER PIPE WELD.
FF,INVESSEL,217,5 AZ i
JET PUMP NO 20 (RFF. DWG. NO. ISI-203-RV-14.15) j 011200 JP820 ALL COMPONENTS B-N-1 VT.3 VT-PBM-202VD R1 C X-..
EXAM INCLUDED VT-1 OF ADJUSTING SCREW B13.10 TACK WELDS PER GE SIL 574 AND AR #
FF,INVESSEL,202.5 AE A0789892, EVAL-01.
JET PUMP NO 20 fRFF. DWG. NO. ISI-203-RV-14) 011391 JP#20 BRACE ARM /VESS B.N 2 VT-1 VT-PBM-202VO R1 C X-EXAMINED PER GE SIL 551 AND INCLUDED B13.20 BRACE ARM TO RISER PIPE WELD.
FF,INVESSEL,202.5 AZ fREF. DWG. NO. NONE) 011293 STM DYR DRN CHNL WLD N/A VT-1 VT PBM 202VC R1 A X.-
- EXAMINED PER AUG-07, GE SIL NO 474, DRAIN CHANNEL WELDS N/A WELDS A,B,C & D.
FF,INVESSEL l
Ih*TERIOR (REF DWG. NO. ISI-203-RV-16) j 011204 SHROUD ANNULUS AREA B-N-1 VT-3 VT-PBM-202VO R1 C X..-
EXAMINATION INCLUDED ACCESSIBLE PORTIONS B13.10 OF SHROUD WELDS H7 AND H8.
FF,INVESSEL l
a l
DATEi 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
7 REVISIOWs 5
INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL THIRD PERIOD, SECOND OLTAGE ($6RF)
CLASS 1 CAEP STATUS COMPONENTS REACTOR PRESSURE VESSEL NR R ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARXS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCX**
i FEACTOR PRESSURE VESSEL (REF. DWG. NO. ISI-203-PV-16) 011395 EHRD SUP PLATE WELD B-N-2 VT-3 VT-PBM 202VD R1 C X---
EXAMINED ACCESSIBLE PORTIONS OF THIS H9 813.21 WELD.
FF.INVESSEL CORE SPRAY PIPING (PEF DWG. NO. ISI-203-RV-08) 011700 B SPRGR RPR CLAMP N/A VT-1 VT-PBM-202VD R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13, REPAIR CLAMP ON B-SPRGR T-BOX N/A USING BWRVIP-18 CUIDELINES.
B-SPRGR T. BOX, 7.5AZ CORE SPRAY PIPING TREF. DWG. NO. ISI-203-RV-07) 011701 PIA N/A EVT-1 VT-PBM-202VD R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13, THRML SLV/TJNCT-TEX WELD 240AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,24CAZ l
011702 PIB N/A EVT-1 VT-PBM-202VD R1 A X--
- EXAMINED PER AUG-03, IE BULLETIN 80-13, THRML SLV/JUNCT-TBX WELD N/A USING BWRVIP-18 GUIDELINES.
120AZ.
FF,INVESSEL,120 AZ 011703 P2A N/A EVT-1 VT-PBM-202VO R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13.
JUNCT-TBX CVR PLATE WELD 240 N/A USING BWRVIP-18 GUIDELINES.
AZ FF,INVESSEL,240 AZ 011704 P2B N/A EVT-1 VT-PBM-202VO R1 A
.--X EXAMINED PER AUG-03, IE BULLETIN 80-13 JUNCT-TBX CVR PLATE WELD 120 N/A USING BWRVIP-18 GUIDELINES. SEE SECTION AZ 2 OF NIS-1 REPORT FOR DETAILS OF FF,INVESSEI,,120 AZ REPORTABLE CONDITIONS. DISPOSITI3NED "USE-AS-IS' PETt NCR # PB 96-03414, i
011705 P3Al N/A EVT-1 VT-PBM-202VC R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80 13, I
HDR PIPE /JUNCT-TEX WELD 240 AZ N/A USING BWRVIP-18 GUIDELINES.
l FF.INVESSEL,240 AZ l
DQTEt 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
8 REVISIONS 5
INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 CAEP STATUS COMPONEFTS PEACTOR PRESSURE VESSEL 4
NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK" CORE SPRAY PIPING (REF. DWG, NO. ISI-203-RV-07) 011706 P3A2 N/A EVT 1 VT-PBM-202VD R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80 13, HDR PIPE /JUNCT-TBX WELD 240 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,240 AZ F
011707 P3B1 N/A EVT-1 VT-PBM-202VO R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13, OR PIPE /JUNCT-TBX WELD 120 AZ N/A USING BWRVIP-18 CUIDELINES.
FF,INVESSEL,120 AZ l
011708 P3B2 N/A EVT-1 VT-PBM-202VC R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13,
@ R PIPE /JUNCT TBX WELD 120 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL.120 AZ 011709 P4aA N/A EVT-1 VT-PBM-202VD R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13,
@ R PIPE / ELBOW WELD 352.5 AZ N/A USING BWRVIP-18 CUIDELINES.
FF,INVESSEL.352.5 AZ 1
011710 PeaB N/A EVT-1 VT-PBM-202VD R1 7.
X---
EXAMINED PER AIX3-03, IE BULLETIN 80-13,
@R PIPE / ELBOW WELD 7.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,1NVESSEL,7.5 AZ j
011711 P4aC N/A EVT-1 VT-PBM-202VD R1 A X- -- EXAMINED PER AUG-03, IE BULLETIN 80-13, HDR PIPE / ELBOW WELD 187.5 AZ N/A USING BWRVIP-18 GUIDELINES.
i FF,INVESSEL.187.5 AZ i
011712 P4aD N/A EVT-1 VT-PBM-202VO R1 A X--
- EXAMINED PER AUG-03, IE BULLETIN 80-13, HDR PIPE / ELBOW WELD 172.5 AZ N/A USING BWRVIP-18 GUIDELINES.
q FF.INVESSEL,172.5 AZ 011713 P4bA N/A EVT-1 VT PBM-202VD R1 A X--
- EXAMINED PER AUG-03, IE BULLETIN 80-13, ELBOW /DWNCMR WELD 325.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,325.5 AZ 1
l 4
.. ~. _ -. - - ~
~.
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
9 QEVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL. THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS REACTOR PRESSURE VESSEL j
NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCX**
j CORE SPRAY PIPING fREF. DWG. NO. ISI-2 f13 - RV. 07 )
]
011714 P4bB N/A EVT-1 VT.PBM.202VO R1 A X...
EXAMINED PER AUG.03, IE BULLETIN 80 13, ELBOW /DWNOMR WELD 7.5 AZ N/A USING BWRVIP.18 GUIDELINES.
FF,1NVESSEL,7.5 AZ 011715 P4 bC N/A EVT-1 VT PBM-202VD R1 A X...
EXAMINED PER AUG-03, IE BULLETIN 80 13, ELBOW /DWNCMR WE* O ' 't 7. 5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,1NVESSEL,187.5 a 011716 P4bD N/A EVT.1 VT.PBM-202VO R1 A X... EXAMINED PER AUG.03, IE BULLETIN 80 13, ELBOW /DWNOMR WELD 172.5 AZ N/A USING BWRVIP.18 GUIDELINES.
FF,INVESSEL,172.5 AZ 011717 P4eA N/A EVT.1 VT.PBM-202VD R1 A X...
EXAMINED PER AUG-03, IE BULLETIN 00 13, DWNCMR/ ELBOW WELD 352.5 AZ N/A USING BWRVIP.18 GUIDELINES.
FF,INVESSEL,352.5 AZ 011718 P4cB N/A EVT.1 VT.PBM.202VD R1 A X...
EXAMINED PER AUG.03, IE BL"LETIN 80 13, DWNCMR/ ELBOW WELD 7.5 AZ N/A USING BWRVIP.18 GUIDELINES.
I FF,INVESSEL,7.5 AZ 011719 P4cC N/A EVT-1 VT.PBM-202VO R1 A X-..
EXAMINED PER AUG.03, IE BULLETIN 80 13.
DWNCMR/ ELBOW WELD 187.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,187.5 AZ l
011720 P4cD N/A EVT-1 VT.PBM-202VO R1 A X... EXAMINED PER AUG 03, IE BULLETIN 80 13, DWNCMR/ ELBOW WELD 172.5 AZ N/A USING BWRVIP.18 GUIDELINES.
i FF.INVESSEL.172.5 AZ i
l 011731 P4dA N/A EVT.1 VT-PBM-202VO R1 A X
.. EXAMINED PER AUG.03, IE BULLETIN 80 13, I
l ELBOW / SHROUD WELD 352.5 AZ N/A USING BWRVIP-18 GUIDELINES.
\\
FF INVESSEL,352.5 AZ I
I l
i DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGEr 10 4
REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OLTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS REAC*0R PRESSURE VESSEL NR R ASME S OEGE SEC. XI T RCEP SUht4ARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION DLOCK'*
I CORE SPRAY PIPING 'REF. DWG. NO ISI-203-RV-0H 011722 P4dB N/A EVT-1 VT PBM-202VO R1 A X.-
- EXAMINED PER AUG-03, IE BULLETIN 80 13, j-ELBOW / SHROUD WELD 7.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL.7.5 AZ 011723 P4dC N/A EVT-1 VT-PBM-202VO R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13.
ELBOW / SHROUD hTLD 187.5 AZ N/A USING BWRVIP-18 GUIDELIhTS.
FF,1NVESSEL,187.5 AZ n
011724 P4dD N/A EVT-1 VT-PBM-202VC R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13, ELBOW / SHROUD WELD 172.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,1NVESSEL,172.5 AZ 011725 PSA N/A EVT-1 VT PBM-202VO R1 A X- -- EXAMINED PER AUG-03, IE BULLETIN 80-13, DWNCMR/SLDG-SLV WELD 352.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,352.5 AZ a
4 011726 PSB N/A EVT-1 VT PBM-202VC R1 A X- -- EXAMINED PER AUG-03, IE BULLETIN 80-13, DWNCMR/SLDG-SLV WELD 7.5 AZ N/A USING BWRVIP.18 GUIDELIhTS.
]
FF,INVESSEL,7.5 AZ d
011727 PSC N/A EVT-1 VT-PBM-202VO R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13, DWNCMR/SLDG-SLV WELD 187.5 AZ N/A USING BWRVIP-18 GUIDELIhTS.
l FF,INVESSEL,187.5 AZ 011728 P5D N/A EVT-1 VT-PBM-202VD R1 A X*--
EXAMINED PER A33-03, IE BULLETIN 80-13, DWNCMR/SLDG SLV WELD 172.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,172.5 AZ 011719 P6A N/A EVT-1 VT-PBM-202VO R1 A X-.-
EXAMINED PER AUG 03, IE BULLETIN 80-13, 3
SLDG-SLV/OUIR-SLV WELD 352.5 N/A USING BWRVIP-18 GUIDELINES.
4 AZ FF,INVESSEL,352.5 AZ z
1 DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE 11 REVISION:
INSERVICE INSPECTION SUM 4ARY SECOND INTERVAL, THIRD PERIOD, SECOND OUIAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS PEACTOR PRESSURE VESSEL NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EX'#!INATION AREA CATGY EKAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK **
COPE SPRAY PIP!NG (PEF. DWG. NO. ISI-203-RV-07) 011730 P6B N/A EVT-1 VT-PBM-202VD R1 A X---
EXAMINED PER AUG-03, IE BUI1ETIN 80 13, SLDG-SLV/OUTR-SLV WELD 1.5 AZ N/A USING BWRVIP-18 GUIDELINES.
t FF,INVESSEL,7.5 AZ 011731 P6C N/A EVT-1 VT-PBM-202VD R1 A X---
EXAMINED PER AUG-03, IE BUI1ETIN 80-13, SLDG-SLV/OL*rR-SLV WELD 187.5 N/A USING BWRVIP.18 GUIDELINES.
AZ FF,INVESSEL,187.5 AZ 011732 P6D N/A EVT-1 VT-PBM-202VO R1 A X---
EXAMINED PER AUG-03, IE BUL".ETIN 80-13, i
SLDG-SLv/OUTR-SLV WELD 172.5 N/A USING BWRVIP-18 GUIDELINES.
AZ FF INVESSEL,172.5 AZ 011733 P7A N/A EVT-1 VT-PBM-202VD R1 A X---
EXAMINED PER AUG-03, IE BUILETIN 80-13, OUTR-SLV/DWNCMR WELD 352.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,352.5 AZ r
011734 P78 N/A EVT-1 VT-FBM-202VD R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13, OUTR-SLV/DWNCMR WELD 1.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,7.5 AZ
\\
011735 P7C N/A EVT-1 VT-PBM-202VD R1 A X
-- EXAMINED PER AUG-03, IE BULLETIN 80-13, OL'TR SLV/DWNCMR WELD 187.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,187.5 AZ 011736 P7D N/A EVT-1 VT-PBM-2C2VO R1 A X-
-- EXAMINED PER AUG 03, IE BULLETIN 80-13, OU"'R-SLV/DWNCMR WELD 172.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,112.5 AZ 011737 P9aA N/A EVT-1 VT-PBM-202VD R1 A X-EXAMINED PER AUG-03, IE BUI4ETIN 80-13, COLLAR /SHRD-PIPE WELD 352.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,I N T.L,3 52. 5 AZ l
i
4 DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
12 REVISION:
5 INSERVICE INSPECTION SUh84ARY SECOND INTERVAL, THIRD PERIOD, SECOND OtTTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS FEACTOR PRESSURE VESSEL l
NR R
ME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCX**
COPE SPPAY PIPING (PEF. DWG. NO. IST-203-PV-07) 01173Q P8aB N/A EVT-1 VT-PBM-202VO R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80 13, COLLAR /SHRD-PIPE WELD 7.5 AZ N/A USING BWRVIP-18 GUIDELINES.
)
1 FF,INVESSEL,7.S A2 011739 P8aC N/A EVT-1 VT-PBM-202VD R1 A X--.
EXAMINED PER AUG-03, IE BULLETIN 80-13, COLLAR /SHRD-PIPE WELD 187.5 AZ N/A USING BWRVIP-18 CUIDELINES.
FF,1NVESSEL,187.5 AZ l
i 01174G P8aD N/A EVT-1 VT-PBM-202VD R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13, i
COLLAR /SHRD-PIPE WELD 172.5 AZ N/A LSING BWRVIP-18 GUIDELINES.
}
FF,INVESSEL,172.5 AZ 1
011741 P8bA N/A EVT-1 VT-PBM-202v0 R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13, i
COLLAR /SHRD WELD 352.5 AZ N/A USING BWRVIP-18 GUIDELIhT.S.
FF,1NVESSEL,352.5 AZ 4
i J
011742 P8bB N/A EVT-1 VT-PBM-202VO R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13, COLLAR /SHRD WELD 7.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,7.5 AZ i
1 a
b 011743 P8bC N/A EVT-1 VT-P6M-202VD R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13, COLLAR /SHRD WELD 187.5 AZ N/A USING BWRVIP-18 GUIDELINES.
FF,INVESSEL,187.5 AZ i
/
011704 P8bD N/A EVT-1 VT-PBM-202VO R1 A X---
EXAMINED PER AUG-03, IE BULLETIN 80-13, COLLAR /SHRD WELD 172.5 AZ N/A USING BWRVIP-18 GUIDELIhTS.
FF,1NVESSEL,172.5 AZ a
GU!DE POD 0 AZ (PET DWG. NO. ISI-203-PV-12) a 011805 GUIDE ROD CAZ BN1 VT 3 VT-PBM-202VD R1 C X---
1 B13.10 FF,INVESSEL,0 AZ
.~
DATER 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
13 7
. REVISION:
INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS REAO*OR PRESSURE VESSEL NR R ASME S OEGE SEC. XI T RCEP SLM4ARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK **
GUIDE ROD 180 AZ (PEF. DWG. NO. ISI-203-RV-12) 011820 GUIDE ROD 180AZ B N-1 VT-3 VT-PBM-202VD R1 C X-..
B13.10 FF,INVESSEL,180 AZ I
FEEDWATER SPARGER 30 AZ fREF. DWG. NO. ISI-203-RV-11) 011835 FW SPARGER 30A2 B-N-1 VT-3 VT-PBM-202VD R1 C X...
s B13.10 FF,INVESSEL,30 A2 FEEDWATER SPARGER 90 A2 (REF DWG. NO. ISI-203-RV-11) 011845 FW SPARGER 90AZ B-N-1 VT-3 VT-PBM-202VD R1 C X-..
B13.10 FF,INVESSEL,90 A2 FEEDWATER SPARGER 150 AZ fREF. DWG. NO. ISI-203-RV-11) 011055 FW SPARGER 150AZ B-N-1 VT-3 VT-PBM-202VD R1 C X.--
1 813.10 FF,INVESSF.L,150 AZ FEEDWAM R SPARGER 210 AZ (REF. DWG. NO. ISI-203-RV-1Q 011865 TW SPARGER 210AZ B-N-1 VT-3 VT-PBM 202VD R1 C X. --
813.10 FF,INVESSEL,210 AZ FEEDWAR R SPARGER 270 AZ (REF. DWG. NO. ISI-203-RV-11) 011875 FW SPARGER 270AZ B.N-1 VT-3 VT-PBM-2C2VG R1 C X...
B13.10 l
rr,1NvESSEI.,270 Az 1
4
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
14 REVISION:
INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
C*. ASS 1 CAEP STATUS COMPONEttrS PEACTOR PRES $URE VESSEL NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BICCK**
FEEDWATER SPARGER 330 A2 (PEF. DWG. NO. ISI-203 RV-11) 011885 FW SPARGER 330AZ B-N-1 VT 3 VT-PBM-202VO R1 C X- -.
B13.10 FF.INVESEL.330 AZ l
i TOP CUIDE (REF. DWG. NO. NONE) 011001 ALIGNER PIN O D'"
N/A VT-3 VT.PBM-202VD R1 A X---
EXAMINED PER AUG-10, GE SIL NO 588.
N/A FF,INVEGSEL 011003 ALIGNER PIN 270 DE N/A VT-3 VT-PBM-202VC R1 A X---
EXAMINED PER AUG-10 GE SIL NO $88, f
N/A I
FF,INVESSEL 1
I SORVEIL SAM HOLDER 30 A2 (REF. DWG. NO ISI-203-RV-17) l
\\
011905 SURVL SAM HLDR 3CAZ B-N-1 VT-3 VT-PBM-202VO R1 C X-..
B13.10 FF,INVESSEL,30 AZ SURVTEL SAM HOLDEF 120 AZ (REF. DW3. NO. ISI-203-RV-17) 011920 SURVL SAM KLDR 120AZ B-N-1 YT-3 VT-PBM-202VD R1 C X I
)
B13.10 FF,1NVESSEL,120 AZ
{2RVETL SAM HOLDER 300 AZ (REF. DWO. NO. ISI-203-RV-17) 011935 SURVL SAM HLDR 300AZ B-N-1 VT-3 VT PBM-202VD R1 C X-..
B13.10 l
FF.INVESSEL,300 AZ REACTOR PRESSURE VESSEL (PEF. DWG. NO. ISI-203-RV-21) 011072 PERIPHERAL FUEL SUP B-N-2 VT-3 VT-PBM-2C2VO R1 C X---
EXAMINATION PERFORMED IN CELL 16-57.
B13.22 FF,INVESSEL f
l l
l t
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
15 REVISION:
5 INSERVICE INSPECTION
SUMMARY
j SECOND INTERVAL, W IRD PERIOD, SECOND OUTAGE (96RF)
CLASS 2 CAEP STATUS COMPONENTS PEATTOR PRESSUPE VESSEL NR R
ASME S OEGE SEC. XI T RCEP S*JiMARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BIDCK'*
l
}
COPE SMROUD (DEF. DWG NO. FTUURE 1-2) 011974 H-1 IN/OUT N/A UT-45LKUP UT-PBM-503V4 R0 A
--XX EXAMINED WITH SMART 2000 SYSTEM USING SHROUD SUPPORT RING TO PLATE N/A UT-6CLKUP UT-PBM-503VS R0
.-XX 45S, OD CREEP'G & 60RL WAVES. TOTAL WELD UTODCRLKUP UT PBM-503V5 R0
--XX LENGTH SCAtMED =56.3% OF WHICH 29.4% WAS FOUND FLAWED ON SHROUD *D, PLATE SIDE.
4 REMAINING 43.7% NOT ACCESSIBLE.
DISPOSITION. 'USE-AS-IS" PER NCR# PB 96-03492.
011089 H-6 IN/OUT N/A UT45LKUP UT-PBM-503V4 R0 A
--XX EXN11NED WITH SMART 2000 SYSTEM USING CORE PLTE SUPPORT RING TO N/A UT60LKUP UT-PBM-503V5 R0
--XX 45S, CD CREEP'G & 60RL WAVES. TOTAL WELD j
PLATE UTODCRLKUP UT-PBM-503V5 RO
--XX LENGTH SCANNED = 85.6% OF WHICH 5.4% WAS FOUND FLAWED OF SHROUD ID, PLATE SIDE.
REMAINING 14.4% NOT ACCESSIBLE.
DISPOSITION, 'USE-AS-IS' PER NCR2 PB i
96-03492, i
i 011992 H-7 IN/OUT N/A UT45LKDN UT-PBM-503V4 R0 A
--XX EXAMINED WITH SMART 2000 SYSTEM USING PLATE TO PLATE N/A UT60LKDN UT-PBM-503V5 R0
..XX 45S, OD CREEP'G 1 60RL WAVES. TOTAL WELD UTODCRLXDN UT-PBM-503V5 R0
..XX LENGTH SCANNED e 86.7% OF WHICH 2.7% WAS FOUND FLAWED ON SHROUD ID, PLATE SIDE.
REMANININ 13.3% NOT ACCESSIBLE.
]
DISPOSITON, 'USE.AS.IS* PER NCR#
96 03492.
4 e
1 6
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
16 REVISIONS 5
INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL. THIRD PERIOD, SECOND OUTAGE (96RFl CLASS 1 CAEP STATUS COMPONENTS VRIN STENA NR R
ASME S OEGE SEC. XI T RCEP I
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK'*
LOOP A fREF. DWG. NO. DBN-01-MI-201-1-A) 018700 1-A-10LUI B-J MT MT-PE-001 R2 C X--.
LONG SEAM UPSM EL IR 89.12 UT-45S UT-PBM-106VO R0 X..-
DW, EL 157, 170 AZ
- 26-CS-X-1.06-28-PEB**
018000 1-A-1CUDO B-J MT MT-FE-001 R2 C X...
LONG SEAM UPSM EL CR B9.12 UT 45S UT.PBM-106VD R0 X. -.
DW, EL 157, 170 AZ
- 2 6 - CS -X 1. 0 6 2 8 -PEB *
- I 018900 1-A-10 B-J MT MT-PE-001 R2 C X.-.
ELBOW TO PIFE B9.11 UT-45S UT-PBM-106V0 R0 X--
DW, EL 157, 170 AZ
- 26-CS-X-1,06-28 PEB**
j l
1 019000 1-A-10LD B-J MT MT-PE-001 R2 C X.--
LONG SEAM DNSM B9.12 UT-45S UT-PPM-106VD R0 X--.
DW, EL 157, 170 AZ
- 26-CS-X-1.06-28-PEB**
RELIEF VALVE DISORARGE (REF. DWG. NO. CG-01-MI-271-K) 021656 1GG-H716 F-A.B.C l'T-3 MAG-CG-407 R5 C X.--
EXAMINATION PERFORMED DIRECTLY FROM ANCHOR FO.00 CATWALK WITH $00. WATT AUXILIARY LIGRT.
DW, EL SAFETY & RELIEF RISERS (AS) (REF. DWG. NO. DBN-01-MI-201-1-Al C21900 1-ASC-1 B-J MT MT-PE-001 R2 C X- - - ITT EXAM PERFORMED FROM DOWNSTREAM (PIPE)
BRANCH CONN TO PIPE B9.11 UT.0 ITT-PBM-106VD RD X-.
- SIDE DUE *.T BRANCH CONhTCTION DW, EL 157 UT.45S UT-PBM-106VD R0 X..
. CONFIGURATION.
- 6-CS-160.718-6A-PEB**
...._~-..
... -~ - - -.
_ ~. -
I EATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PACE:
17 REVISION:
5 INSERVICE INSPECTION SUPNARY SECOND INTERVAL, THIRD PERIOD, SECOND OITTAOE (96RF) i CLAES 1 CAEP STATUS COMPONENTS MAIN STEAM NR R
ASME S OEGE l
SEC. XI T RCEP S'JPNARY EXAMINATION AREA CATCY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK"
]
SAFETY & RELTEF RISEPSfAS) f P.EF. DWG. NO. DBN-01-MI-201-1-A) 023351 1-ASC-2FB B-C-2 VT-1 MAG-CG-407 RS C X---
l FLANGE BOLTING B7.50 DW, EL 157 AZ 105 LOOP B (REF. DWG NO. DEN-01-MI-201-1-B) 035000 1-B-17 B-J MT MT-PE-001 R2 C X---
EXAM PERFORMED FROM DOWNSTREAM (PIPE)
PENT. N-7B TO PIPE B9.11 UT-0 UT-PBM-106VC R0 X---
SIDE ONLY DUE TO PIPE PENETRATION OBMSIV UT-45S UT-PBM-106VD R0 X---
CONFIGURATION.
"26-CS X-1.06 28-PEB" 035100 1-B-17LD B-J Mr MT-PE-001 R2 C X---
LONG SEAM DNSM B9.12 UT 0 UT-PBM-106VD RO X---
OEMSIV UT-455 UT-PBM-106VD R0 X---
"2 6 -CS-X-1. 06 -2 8 - PEB" LOOP C fpEF. DWG. NO. CBN-01-MI-201-1-C) f 045700 1-C-7/CSC B-J MT MT-PE-001 R2 C X-EXAM PERFORMED FROM UPSTREAM (PIPE) SIDE l
6" BRANCH CONN B9.31 UT-45S UT-PBM-106VD R0 X-
- ONLY DUR TO BRANCH CONNECTION DW, EL 157 CONFIGURATION-
- 2 6 - CS -I-1. 0 6 - 2 8 - PEB" LOOP D (REF. DWO. NO. CBN-01-MI-201-1-D) 055200 1-D-3LU B-J MT MT-PE-001 R2 C X---
LONG SEAM UPSM B9.12 UT 45S UT-PEM-106VC R0 X---
DW, EL 199, 288 AZ l
- 26-CS-X-1.06-28-PEB**
i 055300 1-D-3 B-J Prr MT-PE-001 R2 C X---
l PIPE TO ELBOW B9.11 UT-453 ITT-PBM-106VD R0 X---
DW, EL 199, 288 AZ
- 2 6 -CS-X-1. C 6 -2 8 - PEB"
1 l
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
18 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS MAIN STEAM NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY E7.AM A EOOO REMARKS N',,NBER IDENTITICATION ITEM NO METHOD PROCEDURE T CRHR " CALIBRATION ELOCK**
l LOOP D (REF. DWG. NO DBN-01-MI-201-1-D) i I
055400 1-0-2LDI B-J MT MT-PE 001 R2 C X. -.
LONG SEAM DNSM EL IR B9.12 UT-45S UT-PBM-106VD RD X..-
DW, EL 199, 288 AZ "26 -CS-X-1. 06 - 2 8 - PEB *
- 055500 1-D-2LDC B-J MT MT-PE-001 R2 C X---
LONG SEAM DNSM EL OR B9.12 UT-4SS UT-PBM-106VO R0 X.--
DW, EL 199, 288 AZ
- 26-CS-X-1.06-28-PEB**
l 051400 HD2(IA)
B-K-1 MT MT PE-001 R2 C X---
INTEGRAL ATTACHMENT B10.10 DW, EL 156-8, 278 AZ l
059900 HD3(IA)
B-K-1 MT MT-PE-001 R2 C X---
INTEGRAL ATTACHMENT B10.10 l
DW, EL 156-8, 235 AZ
.e...
{
i 051100 HD4 (IA)
B-K-1 MT MT-PE-001 R2 C X---
INTEGRAL ATTACHMENT B10.10 DW, EL 156-8, 215 AZ 061500 1-D-9LU B-J Kr Mr-PE-001 R2 C -.-- NO EXAMINATION PERFORMED DLT TO TOTAL LONG SEAM UPSM B9.12 UT-45S UT.PBM-106VC R0 OBSTRUCTION OF WELD BY A SADDLE SUPPORT DW, EL 157, 200 AZ PERMANENTLY ATTACHED TO THE PIPE.
"2 6 -CS-X.1. 06 -2 8 - PEB" 061600 1-D-9 B-J MT MT-PE-001 R2 C X.
EXAMINATION LIMITED TO 79% DUE TO A PIPE TO ELBOW B9.11 UT-45S UT-PBM-106VD R0 X... SADDLE SUPPORT PERMANENTLY ATTACHED TO I
DW, EL 157, 200 A2 PIPE.
l
- 26-CS-X-1.06-28-PEB**
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DATE 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
19 REVISIONt S
INSERVICE INSPECTION SUb94ARY SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE 196RF)
CLASS 1 CAEP STATUS COMPONEW S MAIN STEAM I
NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDE!CIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK" LOOP D fREP DW1 NO. DBN-01-MI-201-1-D) 061700 1-D-9LDI B.J MT MT-PE-001 R2 C X-LONG SEAM DNSM EL IR B9.12 UT-45S UT-PBM-106VO R0 X---
DW, EL 157, 200 AZ "2 6 -CS-X-1. 0 6 -2 8 - PEB*
- 061800 1-D-9LDO B-J MT M -PE-001 R2 C X---
LONG SEAM DNSM EL OR E9.12 UT-455 ITr-PBM-106VD RO X---
DW, EL 157, 2 0') AE
- 26 -CS-X-1. 06 -2 8 - PEB" 063500 GDi(IA)
B-K-1 MT MT-PE-001 R2 C
-X--
LIMITED EXAM TO 16.7 % CODE COVERAGE DUE INTEGRAL ATTACHAENT B10.10 "N SUPPORT, REFERENCE RR-06. 1/4" LINEAR DW, EL 138-1, 183 AZ INDICATION RECORDED AND IS ACCEPTABLE DW, EL 138-1, 183 AZ PER IWB-3516-1.
l I
064200 1-D-12LU B-J MT MT-PE-001 R2 C X---
LIMITED EXAM TO 11 % CODE COVERAGE DUE LONG SEAM UPSM 99.12 UT-45S ITI-PBM-106VD R0 X-TO PIPE SUPPORT, DW, EL 138, 190 AZ
" 2 6-CS-X-1. 0 6 -2 8 - PEB" 064300 1-D-12 B-J MT MT-PE-001 R2 C X---
LIMITED EXAM TO 92 % CODE COVERAGE DUE PIPE TO VALVE B9.11 UT-45S UT-PBM-106VD R0 X---
TO PIPE SUPPORT. EXAM PERFORMED FROM DW, EL 138, 190 AZ UPSTREAM (PIPE) SIDE ONLY DUE TO PIPE TO DW, EL 138, 190 AZ VALVE CONFIGURATION.
"2 6 -CS-X-1. 0 6 - 2 8 - PEB" 064Q00 1 D-14 B-J MT MT PE-001 R2 C X--.
EXAM PERFORMED FROM DOWNSTREAM (PIPE)
PE!C. N 7D TO PIPE B9.11 UT-0 UT-PBM-106VD R0 X---
SIDE ONLY DUE TO PIPE PENETRATION OBMSIV UT-45 UT-PBM-106VO R0 X---
CONFIGURATION.
- 2 6 - CS-X-1. 0 6 - 2 8-PEB" 034900 1-D-14LD B-J MT MT-PE-001 R2 C X--
LONG SEAM DNSM 89.12 UT-C UT-PBM-106VO R0 X- --
g OBMSIV ITT-4 5S UT-PBM-106VO R0 X- - -
8
- 26-CS-X-1.06-28-PEB**
DQTE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
20 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND I!CERVAL THIRD PERIOD, SECOND OUTAGE (96RF)
CIASS 1 CAEP STA7US COMPONENTS MA!N STEAM NR R
ASME S OEGE SEC. XI T RCEP SL7HutY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK **
SAFETY & PELIEF RISERSfDS) fREF DWG. NO. DBN-01-MI-201-1-0) 065300 1-DSA-1 B-J MT K!-PE-001 K2 C X...
EXAM PERFORMED FROM DOWNSTREAM (PIPE)
BRANCH CONN TO PIPE B9.11 UT 0 UT-PBM ~,06VD R0 X-..
SIDE ONLY DUE TO BRANCH CONNECTION DW, EL 157, 281 AZ UT-45S UT-PBM-106VC R0 X--.
CONFIGURATION.
- 6.CS-160. 718 6A-PEB**
065400 1 DSB-2FB B-G-2 VT-1 MAG-CG-407 R5 C X...
FLANGE BOLTING B7.50 DW, EL 157 067051 1 DSC-2FB B-G 2 VT-1 MAG-CG-407 RS C X---
FLANGE BOLTING B7.50 DW, EL 157 067100 1 CSE-2FB B-G-2 VT-1 MAG-CG-407 R5 C X-*
FLANGE BOLTING B7.50 DW, EL 157 067200 1-DSF.2FB B-G-2 VT-1 MAG-CG-407 R5 C X-..
FLANGE BOLTING B7.50 DW, EL 157
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE 21 REVISION:
5 INSERVICE INSPECT!DN SUMKARY SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS MAIN FECIRCULATION NR R
ASME S OECE SEC. XI T RCEP Subt4ARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK" 28 INCH DISCHARGE (REF. DWG. NO, R CS - 0 2 -MI-2 01 A) 094400 H9A(IA)
EXAM LIMITED TO 92.4% CODE COVERAGE DUE INTEGRAL A*"fACHMENT B10.10 TO PIPE CLAMP INTERFERENCE.
DW, EL 134-2, 270 AZ 096450 H9A F-A,B,C VT 3 4AG-CG-407 R5 C X---
SPRING HANGER FO.00 VT-4 MAG-CG-407 R5 X
DW, EL 138-2, 270 AZ 22 INCH MANIFOLD (REF. DWG NO RC$-02-MI-201-1-A) 101050 2-AM-8 B-J PT LP-PE-001 R4 C X-.-
CROSS TO PIPE B9.11 UT-45S PDI-UT-PBM-2VO X---
DW, UT-60RL PDI-UT-PBM-2VD X-
- 22-SS-X-1.750-57-PEB.**
101100 2 AM-8LD B-J PT LP-PE-001 R4 C X---
LONG SEAM DNSM B9.12 UT-45S PDI-UT-PBM-2VO X---
DW,
- 22-SS-X-1.750-57-PEB.**
28 INCH SUCTION (REF DWG. NO. RCS-02-MI-201-I-B) 110100 H1B (IA)
EXAM LIMITED TO 92.9% CODE COVERAGE DUE INTEGRAL ATTACHMENT B10.10 TO PIPE CLAMP INTERFERENCE. NO GUSSETTED DW, EL 144-2, 180 AZ RISER CLAMP WELDS WERE FOUND.
28 INCH DISCHARGE (REF DWG. NO. RCS-02-MI-201-1-B) l 112850 2-BD-26 B-J PT LP PE-001 R4 C X-,-
EXAM PERFORMED FROM DOWNSTREAM (PIPE)
[
PUMP TO PIPE 89.11 UT-455 PDI-UT-PBM-2VD X---
SIDE ONLY DUE TO PUMP / PIPE l.
DW, UT-60RL PDI-UT-PBM-2VD X--
- CONFIGURATION.
l
- 28-SS-X-1.575-59-PEB.**
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CATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
22 REVISION:
5 INSERVICE INSPECTION SUf94ARY SECOND INTERVAL. THIRD PERIOD, SECOND OLTA0E (96RF)
CLASS 1 CAEP STATUS COMPONE1rfS MAIN RECIRCULATION 4
NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CAT 3Y EXAM A EOOO REMARKS j
NUMDER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRHR ** CALIBRATION BLOCK **
28 INCH DISCHARGE fREF. DWG. NO. RCS-02-MI-201-1-B)
+
112900 2.BD-26LD B-J PT LP-PE-001 R4 C X---
LONG SEAM DNSM B9.12 Li-45S PDI-UT-PBM-2VO X--
4 DW,
- 29-SS-X-1.575-59-PEB.**
i 114900 H9B(IA)
EXAM LIMITED TC v3.9% CODE COVERAGE DUE INTEGRAL ATTACHMENT B10.10 TO PIPE CLAMP Ih'rERFERENCE. NO GUSSETTED DW, EL 138-2, 90 AE RISER CLAMP WELDS WERE FOUND.
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DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
23 REVISION:
5 INSERVICE INSPECTION SU>f4ARY SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS FrTDWATER NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGy EXAM A EOOO REMAArs NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK **
12-INL"H RISER-LEG A (REF. DWG. NO. DDN-0 6 -MI-2 01 M 133600 6-AA-10 B-J KT MT-PE-001 R2 C X---
CODE EXAM COVERAGE ACHIEVED.
TRANS PIECE TO NOZZ B9.11 UT-458 UT-PBM-213VD RO
-.X-DW, EL 189-10, 30 AZ
- 12-CS-160-1.308-18A-PEB**
133650 AA 10 N/A 07-45S UT-PBM-213VD R0 A
--X-EXAMINED PER AUG-02, NUREG-0619.
TRANS PIECE TO NOZZ N/A DW.EL 189,AZ 30 "12 -CS-16 0 1. 3 08 -18 A-PEB*
- 12-tNCH RISER-LEG C (REF DWG. NO DDN-06-MI-201-2-Al 135500 6-AC-9 B-J MT MT-PE-001 R2 C X,--
CODE EXAM COVERAGE ACHIEVED.
TRANS PIECE TO NOZZ B9.11 UT-45S UT-PBM-213VC RO X-DW,EL 189-10, 150 AZ
- 12-CS-360-1.308-18A-PEB**
\\
135550 6-AC-9 N/A UT-45S UT-PBM-213VD R0 A
--X-EXAMINED PER AUG-02, NUREG-0619.
TRANS PIECE TO NOZZ N/A DW.EL 189,AZ 150 "12 CS-16 0 - 1. 3 0 8 - 18 A-PEB *
- l i
12-INCH RISER-LEG D (REF. DWG, NO. DDN-06-MI-201-2-B) 139900 6-BD-9 B-J MT MT-PE-001 R2 C X---
MANUAL EXAM PERFORMED BE7 WEEN 9.3" TO TRANS PIECE TO NOZZ 29.11 UT.45S UT-PBM-213VC RO
--X-29.2" DUE TO THERMOCOUPLE.
DW, EL189-10, 210 AZ UI-45S UT-PBM-106VO RO X---
- 12-CS-160 1.308-18A-PEB**
139950 6 BD-9 N/A UT 45$
UT-PBM-213VD R0 A
--X-EXAMINED PER AUG-02, NUREG-0619.
TPANS PIECE TO NOZZ N/A DW,EL 189 AZ 210 I
- 12 - CS - 16 0 - 1, 3 08 - 18 A-PEB "
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DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
24 l
e REVISION:
5 INSERVICE INSPECTION
SUMMARY
l l
SECOND INTERVAL, THIRD PERIOD, SECOND OUTACE (96RP)
{
CIASS 1 CAEP STATUS COMPONENTS h
FECPWATER NR R
l, ASME S OEGE I
SEC. XI T RCEP l
l SUP94ARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS J
I NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK'*
j i
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l L
12-INCH RTSER-LEG E fREF. DWG NO. DDN-06-MT-201-2-B) 140700 6-EE-6 B-J MT MT-PE -001 R2 C X-
- CODE EXAM COVERAGE ACHIEVED.
l TRANS PIECE TO NOZZ 89.11 ITI-4 5 S ITI-PBM-213VD R0
..X-I DW, EL189-10, 270 AZ
- 12-CS+160-1.308 18A-PEB**
t i
140750 6 BE-6 N/A ITT-4 5S tff-PBM-213VD R0 A
--X=
EXAMINED PER AUG-02, NUREG 0619.
[
TRANS PIECE TO NOZZ N/A DW,EL 189,AZ 270
- 12-CS-160-1.308-18A-PEB**
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DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
25 I
t REVISION:
5 INSERVICE INSPECTION
SUMMARY
]
SECOND INTETVAL, THIRD PERIOD. SECOND OUTAGE ( 96RF) l l
CLASS 2 CAEP STATUS COMPONENTS l
I ME S DEGE j
SEC XI T RCEP SUh94ARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCX**
l RESIDUAL HEAT PEMOVAL (REF. DWG NO. DCN-10-MI-206-15) 143100 10 RS+3 C-F PT LP-PE-001 R4 C X-.*
PENT PIPE TO PENT C5.11 i
l KEAD SPRAY fREF. DWG. NO DCN-10-MI-206-15) 144700 10DCN-H156 (IA)
EXAM LIMITED TO 87.5% CODE COVERAGE DUE INTEGRAL ATTACHMENT B10.10 70 PIPE CLAMP REFERENCE RR-06.
DW,'EL 202 11
)
IN-LOOP A (PEF DWG. NO DE-10-MI-203-9-A) l 151150 10-IA-25 B-F PT LP-PE-001 R4 C X--
EXAMINATION LIMITED IN AREAS BETWEEN 30' PIPE TO TEE B5.130 UT-45S UT-PBM-106VO R0 X...
TO 43' AND 64* TO 7* DUE TO TEE DW UT-458 PDI-UT-PBM-2VD X*
CONFIGURATION.
]
DW UT-60RL PDI-UT-PBM-2 VD X. -
j
- 24-SS-80 1.218-54.PEB.**
IN-LOOP B f9ET. DWO NO DE-10-MI-203-9-B) l 155650 10-IB 25 B-F FT LP-PE-001 R4 C X...
EXAMINATION LIMITED IN AREAS BETWEEN PIPE TO TEE B5.130 UT-45S UT-PBM-106VD RD X.-.
2 8. 5
- TO 4 5' AND 64. 5
- TO 10' DUE TO TEE DW UT-45$
PDI-UT-PBM-2VO X--.
CONFIGURATION.
DW UT-45RL PDI UT-PBM-2VD X+..
- 24-SS-80-1.218-54.PEB.**
CUT fREF. DWG NO. DON-10-MI-207-16) 159150 10-0-27 B-J MT MT-PE-001 R2 C X...
EXAMINATION PERFORMED FROM UPSTREAM i
PIPE TO VALVE
$9.11 UT-45S UT-PBM-106VO RC X.-.
(PIPE) SIDE ONLY DUE TO PIPE TO VALVE
{
DW UT-60S UT-PBM-106VO R0 X..-
CONFIGURATION.
- 20-CS-100-1.281-53-PEB.**
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l DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGEs 26 REVISION:
5 INSERVICE INSPECTION SIM4ARY SECOND INTERVAL. THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS REAMOR WATER CLEAN-UP NR R ME S CEGE
)
SEC. XI T RCEP i
SLHMARY EXAMINATION AREA CATCY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK" OUT fREF DWC. NO. DCA-12-MI-201-1) 164000 12DCN-H149 F-A.B.C VT-3 MAG-CG-407 R5 C X..-
SPRING HANGER FO.00 VT-4 MAG-CG-407 R5 X---
DW, EL 176-6,90-120A 1G5390 12-0-36LU B-J PT LP-PE-001 R4 C X..
LONG SEAM UPSM B9.12 ITI-455 PDI-tTI-PBM-2VO X--.
- 6-SS-80.432-50-PEB.**
1 165295 12-0-36 B-J PT LP-PE-001 R4 C X-..
EXAM PERFORMED FROM UPSTREAM (PIPE) SIDE PIPE TO VALVE 89.11 UT-45$
PDI-UT-PBM-2VD X-..
ONLY DUE TO PIPE TO VALVE CONFIGURATION.
UT-70S PDI-ITI-PBM-2VD X-..
EXAM SATISFIES AUG-01 PROGRAM AND NRC CL 88-01 REQUIREMENTS.
- 6-SS-80. 432-50-PEB.**
i PEACTOR WATER CLEAN-t'P (RET DWG NO DE-12-MI-203-6) 165338 12-13-9C N/A UT 455 UT PB-002V9 R1 A X...
EXAMINED PER AUG-01, CL 88-01.
N/A
- 4-SS-80.337-65A-PEB**
165339 12-13 9D N/A UT-45S UT-PB-002V9 R1 A X-..
EXAMINED PER AUG-01, CL 88-01.
N/A "4-SS-8 0.337-65A-PEB" 165366 12-14-19 N/A UT-455 PDI-UT-PBM-2VD E X-.-
EXPANDED SCOPE AS RESULT OF REPORTABLE VALVE TO PIPE N/A UT.7CS PDI-tTT-PBM-2VD
..X.
INDICATION FOUND IN WELD 8 12 14-5. EXAM OBMSIV, EL 158-6 PERFORMED FROM DOWNSTREAM SIDE ONLY DUE OBMSIV, EL 158-6 TO VA*VE CONFIGUliATION.
- % -SS 8 0.337-6 5 A-PEB**
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DaTE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
27 REVISION:
5 INSERVICE INSPECTION SUb91ARY SECOND INTERVAL THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS CAEP STATUS COMPONENTS REACTOR WATEP CLEAN-UP NR R
ASME S OEGE SEC. XI T RCEP SU>91ARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS t
i NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK **
l REACTOR WATER CLEAN-UP (REF. DWO. No. DE-12-MI-203-6)
L l
l 165367 12 14-5 N/A ITT.6 0S PDI-UT.PBM-2VD A..
X EXAMINED PER AUG.01, CL 88-01 AND PIPE TO ELBOW N/A UT.70S PDI-UT.PBM.2VD X CONCERN RAISED BY NRC DURING 2R10 CBMSIV, EL 158 6
- --- IN3PECTION. SEE SECTION 2 OF WIS-1 l
OBMSIV, EL 158 6 LTI. 0 PBM.UT-103 R0 X-..
REPORT FOR DETAILS OF REPORTABLE UT.45RL PBM-tTT-IC3 RD X..-
CONDITION. REPAIRED BY WLLD OVERLAY AND
[
EXAMINED SAT.
- 4-SS-80. 337 65A-PEB**
165371 12 14 6 N/A UT.0 UT-PBM-102VD R0 E X-..
EXPANDED SCOPE AS RESULT OF REPORTABLE N/A UT.45S PDI.UT.PBM-2 VOX X... INDICATION TOUND IN WELD 12-14-5.
l
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__m DATE; 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PACE:
28
. REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RP) i CLASS 1 CAEP STATUS COMPONENTS CORF SPRAY NR R
ASME S OEGE SEC XI T RCEP CUMMARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIPICATION ITEM NO METHOD PROCEDURE T CRMR *
- CALIBRATION BIDCK*
LONG SEAM UPSM EL IR B9.12 UT 45S PDI UT-PBM-2VD X---
- 12-SS-80.687-12-PEB**
l 169555 14 A-33LUO B-J PT LP-PE 001 R4 C X---
LONG SEAM UPSM EL OR 89.12 UT-455 PDI-UT-PBM-2VD X.-.
DW l
- 12 SS-80.687-12-PEB**
169560 14 A 33 B-J PT LP-PE-001 R4 C X---
EXAM LIMITED ON DOWNSTREAM (PIPE) SIDE i
l ELBOW TO PIPE B9.11 UT-45S PDI-UT-PBM 2VD X--
- DUE TO WELDED PIPE SUPPORT.
DW, EL 160-5, 120 AZ
- 12-SS-80.687-12-PEB**
l 169565 14-A-33LD B-J PT LP-PE-001 R4 C X---
LONG SEAM DNSM B9.12 UT-45$
PDI UT-PBM-2VD X-DW
- 12-SS-80.687-12-PEB**
I 16D635 14-A-39LU B-J PT LP-PE-Col R4 C X---
LONG SEAM UPSM B9.12 UT-45S PDI-UT-PBM-2VD X.--
- 12-SS-80..C87-12-PEB**
169640 14-A-39 B-J PT LP-PE-001 R4 C X---
EXAM SATISPIES AUG-01 & NRC GL 88-01 PIPE TO REDUCER 89.11 L'I 45S PDI-UT-PBM-2VD X--.
REQUIREMENTS.
DW, EL 181-0, 120 AZ
- 12-SS-80.687-12 PEB**
l 169641 14-A-39LD B-J PT LP PE-001 R4 C X---
LONG SEAM DNSM B9.12 UT-45S PDI UT-PBM-2VD X---
- 12 SS-80.667-12 PEB**
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l DSTE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
29 REVISION:
5 INSERVICE INSPECTION SUh94ARY SE':OND INTERVAL THIRD PERIOD, SECOND OITTAGE (96RF)
CIAS$ 1 CAEP STATUS COMPONENTS CORE $ FRAY NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARXS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCX" LOOP A (REF. DW3. NO. DCN-24-MT-203-5-B) 160601 14-A-43 N/A UT-455 UT-PBM-208V0 R0 A
.-X-EXAMINID PER AUG-01, CL 88 01.
PIPE TO SAFE-END N/A UT-60RL UT-PBM-208VD R0
-X.
DW,EL 189,AE 120
- 10-SS-80.594-34-PEB**
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DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
30 f
' REVISION:
5 INSERVICE INSPECTION SUMVARY
[
SECOND INTERVAL THIRD PERIOD, SECOND OLTTAGE (96RF)
CLASS 1 CAEP ETATUS COMPONENTS i
PEACTOR PRESSUPE VESSEL i
NR R
ME S DEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION block **
LOOP A fpEr DW3. NO, DCN-14-MI-203-5-B) 169G95 14.A-27 N/A UT.4 5S UT-PBM 209VD R0 A
..X.
EXAMINED PER AUG.01, GL B6 01.
SAFE-END TO NOE NSA N/A UI.45RL UT-PBM.209VD RC
..X-DW,EL 189,AZ 120 UT.6 0RL UT-PBM-209VO R0
..X.
- 11.5.SS/CS.XX-1.59 67.PEB**
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DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 FAGE:
31 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS CORE SPRAY NR R
ASME S OEGE SEC, XI T RCEP i
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARXS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCX" LOOP B (REF. DWG, NO. DCN MI-2 0 3 M 170G00 14-B-11 8-F PT LP PE-001 R4 C X--*
PIPE TO PIPE B5.130 UT 0 UT-PBM-102VD R0 X---
DW,EL 135.AZ 245 UT-45S UT PBM-102VD RO X
DW.EL 135,AZ 245 UT-45S PDI*UT-PBM-2VO X---
- 12-CS-100.843-3-PEB**
l 170800 14DCN-H73 F-A,B.C VT-3 MAG-CG.407 RS C X-..
SPRING HANGER F0.00 VT-4 MAG-CG-407 R5 X.-
DW, EL 146-0 l
172810 14 B-28LD B-J PT LP-PE-001 R4 C X LON3 SEAM DNSM 89.12 UT-0 UT-PBM-102VO R0 X.--
DW,EL 140,A3 245 UT-45S PDI-UT-PBM-2VD X-.-
- 12-SS-80.687 12-PEB**
172815 14 B-29LU B-J PT LP-PE 001 R4 C X-..
EXAM LIMITED TO 9' DUE TO PROXIMITY OF LON3 SEAM UPSM B9.12 UT-0 UT-PBM-102VO RD X-.-
BOX BEAM.
DW UT-45S PDI-UT-PBM-2VD X..-
- 12-SS-80.687-12-PEB**
173820 14 B-29 B-J
'T LP-9E-001 R4 C X PIPE TO PIPE B9.11 UT=0 UT-PBM-102VD RD X-.-
DW.EL 153 11, 260 AZ UT-455 PDI-UT-PBM-2VD X-.-
LONC SEAM DNSM 89.12 UT-0 UT-PDM-102VD R0 X-DW UT-45S PDI-UT-PBM-2VD X-
14NG SEAM UPSM EL IR B9.12 UT-45S PDI-UT-PBM 2VD X---
DW "12 - SS-8 0. 6 8 7 12 - PEB"
. ~. - _
...~. -
DATEp 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PACE:
32 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL. THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 1 CAEP STATUS COMPONENTS COPE SPRAY l
NR R
ASME S OECE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK
1 1
LOOP B (REF DWC NO. DON-14 MY-203-5-A)
I 172887 14-B.33LUO B-J PT LP-PE-001 R4 C X.--
LONG SEAM UPSM EL OR 89.12 UT-453 PDI-UT-PBM-2VD X-DW l
- 12-SS-80.687-12-PEB**
l 172800 14 B-33 B-J PT LP-PE-001 R4 C X.
EXAM SATISFIES AG-01 PROGRAM & NRC GL i
I ELBOW TO PIPE B9.11 UT-45S PDI-UT-PBM-2VD X...
88 01.
DW, EL 159 9, 240 AZ
\\
- 12-SS-80.687-12 PEB**
1 172805 14 B-33LD B-J PT LP-PE.001 R4 C X*-.
LONG SEAM DNSM B9.12 UT-45S PDI-UT-PBM-2VD X-DW l
l
- 12-SS-80.687-12-PEB**
LIMITED EXAM TO 76% CODE COVERAGEDUL TO l
INTEGRAL ATTACHMENT B10.10 PIPE CLAMP CONFIGURATION. SEE RR-06.
)
l DW, EL 175-0, 240 AZ 172975 14-B-41 N/A UT-45S UT-PBM-208VD R0 A
--X-EXAMINED PER AU3-01, GL 88-01.
l PIPE TO SAFE-END N/A UT-60RL UT-PBM-208V0 R0 X-.-
DW,EI 189,AZ 240 "10-SS-8 0. 5 94 PEB**
a l
i
__m 1
1 1
1 DATE: 11/26/96 PEACH BOITOM ATOMIC POWER STATION UNIT 2 PAGE:
33 REVISIONS 5
INSERVICE INSPECTION Stht4ARY SECOND INTERVAL THIRD PERIOD, SECOND OUTACE (96RP)
CLASS 1 CAEP STATUS COMPONENTS PEACTOR PRESS *SE VESSEL NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BIDCK**
LOOP B (REF DWG. NO. DCN-14.M!.203.$.A)
\\
172978 14.B-27 N/A UT.455 UT.PBM-208VO RO A
-.X.
EXAMINED PER AUG.01, CL 88 01, j
SAFE.END TO NOZ NSB N/A L*f.45RL UT.PBM.208VD RO
-.X-DW,EL 184,AZ 240 UT.60RL UT.FBM-208VD RD
-.X.
"11.5.SS/CS.XX-1.59 67.PEB**
1 l
l I
1 s
I
.m I
I DATE 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAOEs 34 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND O!7TAGE (96RF)
CIASS 1 CAEP STATUS COMPONENTS SYSTEM PRtSSUP.E TESTS NR R
l MM S OEGE l
SEC, XI T RCEP l
StRHARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NLHBER IDENTIFICATION ITCA NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCX**
l RPV: Pininor Pumes; Valves 178550 CLASS 1 LEAKAGE TEST B-P VT.2 ST-0 C80-675 2 C
.X..
INITIAL EXAMINATION REVEALED MINOR PRESSURE RETAINING BOUNDARY B15.50*
LEAKAGE AT SEAL AREAS OP SEVERAL COMPONENT LOCATIONS. AFTER MINOR CORRECTIVE MAINTENANCE, ALL LOCATIONS WERE EXAMINED SAT.
l i
1 I
h
__.- _. ~
+..
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
35 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 2 CAEP STATUS COMPONENTS PESIDUAL HEAT REMOVAL I
NA R
l ME S OEGE l
SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK **
l TORUS-IN-LOOP A (REF. DWG. NO. GB-10-MI-204-11-A) 311500 10MO-8101 F-A,B.C VT-3 MAG-CG-407 RS C X---
i RIGID RESTRAINT FC.00 SHITTDOWN COOL SUCT LOOP A (REF. DWG. NO. HB-10-MI-201-2-A) 213700 10HB-H37 F-A.B,C VT-3 MAG-CG-407 R5 C
.X--
VT-3 EXAM REVEALED 1 LOOSE IDCK NUT &
I SPRING HANGER F0.00 VT-4 MAG-CG-407 R5
-X.-
VT-4 EXAM REVEALED 1 OF 2 SPRING CAN TC-SEG 2, EL 127-6 14AD SETTINGS OUT OF SCALE. REWORK PFR l
TC-SEC 2 EL 127 6 ARN A-1031840, I
315000 1 CHB-H17 F-A,B,C VT-3 MAG-CG-407 R5 C X..-
RIGID RESTRAINT FO.00 l
TC-SEG 16. EL 127-6 315500 10HB-H15 F-A,B,C VT-3 MAG-CG-407 R5 C X*..
SPRING MANGER FO.00 VT-4 KhG-CG-407 R5 X---
i TC-SEG 15, EL 127-6 l
216050 10HB-H14 F-A.B.C VT-3 MAG-CG-407 R5 C X..-
SPRING HANGER F0.00
- 4 MAG-CG-407 R5 X---
TC-SEG 14, EL 122-6 SHITTDOWN COOL SUC"P LOOP A fREF. DWG. NO. HB-10-MI-201-1-A) 216950 10HB-H2O F-A,B,C VT-3 MAG-CG-4 07 R5 C X-.-
SPRING HANGER FO.00 VT-4 MAG-CG-407 RS X---
l A RHR RM, EL 109-3 SWJrDOW*i COOL SUCT LOOP C (PFF. DWG. NO. HB-10-MI-201-1-C) 230250 10HB-R19 F-A,B,C VT.3 MAG-CG-407 R5 C X---
SPRING HANGER F0.00 VT-4 MAG-CG-407 RS X...
C RRR RM, EL 123-0 a
l l
DATE 11/26/96 PEACH BOTTOM ATOMIC POWER STATIO1 UNIT 2 PAGE:
36 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND CLTIAGE (96RF)
CLASS 2 CAEP STATUS COMPONENTS RESIDUAL HEAT REMOVAL NR R
$ 0EGE SEC. XI T RCEP j
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS
{
i NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK"
)
I SHfffDOWN COOL SUCT LOOP C (REF. DWG. NO. HB-10-MI-201-1-C) 330400 10HB-S5 F-A,B,C VT-3 MAG-CG-407 R5 C X-.-
RIGID RESTRAINT F0.00
)
C RHR RM, EL 121 6 320b00 10HB $4 P-A,B,C VI-3 MAG-CG-407 R5 C X-.-
RIGID RESTRAINT F0.00 C RHR RM, EL 122 0 i
f I
SHL*:"DOWN COOL SUCT LOOP D fREF. DWG. NO. HB-10-MI-201-2-D) i 221400 10HB-H33 (I A)
C-C KI MAG.CG-403 R5 C X..-
PIPE LUGS C3.20 i
TC-SEG 4, EL 122-6
(
DISCHAROE-LOOP '" fREF DWG. NO. GB-10-MI-202-3.CS l
327000 10GB H47 F-A,B,C VT-3 MAG-CG-407 R5 C X SPRING HANGER F0,00 VT-4 MAG-CG-407 R$
X
[
C RHR RM, EL 94-6 328100 10GB-H48 F-A,B,C VT-3 MAG-CG-407 R5 C X---
SPRING HANGER F0.00 VT-4 MAG-CG-407 R5 X---
l C RHR RM, EL 94-6 CONTAINMNT SPPAY IN LOOP A (REF. DWG. NO GB-10-MI-203-1-A) 240200 10GB-H50(IA)
C-C MT MAG-CG-4 03 R5 C X.--
PIFE LUGS C3.20 TC-SEG 13, EL 111-4 CONTAINMNT SPRAY IN LOOP B (PEF. DWG NO CB-10-MI-203-6-B) 742100 10-2CSIB24-9 C-F MT MAG-CG-403 R$ C X---
]
PIPE TO ELBOW C5.11
i l
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
37 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 2 CAEP STA%fS COMPONENTS PESIDUAL HEAT PEMOVAL NR R
l i
ASME S OEGE i
SEC. XI T RCEP l
SIM1ARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK **
CONTAINMNT SPRAY IN LOOP B (REF. DWGJ NO CB-10-MI-203-5-B) 345000 10-2CSIB24-24 C-F MT MAG-CG-403 R$ C X..
PIPE TO ELBOW C5.11 i
I I
i INJECT *0N LOOP A (REF DWG. NO. DDN-10-MI-203-8-A) 247500 10DDN-H66 F-A,B,C VT-3 MAG-CG-407 R5 C X---
SPRING HANGER FO.00 VT-4 MAG-CG-407 R$
X.
TC-SEG 13, EL 128-4 SHUTDOWN COCLING SUCTION (REF DWG. NO. HB-10-MI-207-17) l 351000 10-2SCS24-2 c.F KT MAG-CG-403 RS C X-.-
TEE TO PIPE C5.11 s
253650 10HB-H40 F-A,B,C VT.3 MAG-CG-407 R5 C X..-
SPRING HANGER FO.00 VT-4 MAG-CG-407 R5 X-.-
TC SEG 3, EL 127-6 353600 10HB-H38 P-A,B,C VT-3 MAG.CG-407 R5 C X-..
SPRING HANGER FO.00 VT-4 MAG-CG-407 R5 X---
TC-SEG 3, EL 127-6 1
2537C0 10HB-S6 F-A,B,C VT-3 MAG-CG 407 R5 C
-X-.
EXAM REVEALED DISPLACED SPHERICAL RIGID RESTRAINT F0,00 BEARING. PER ENGR'G EVAL (SEE AT#
TC-SEG 2, EL 127 6 A1031856) SUPPORT IS ACCEPTABLE FOR TC-SEG 2, EL 127-6 CONT'D SERVICE & TO BE REWORKED.
TOPUS SUCTION LOOP A (REF. DWG. NO. HB-10 WI-201-1-A) l 253250 10HB-52 F-A,B,C VT-3 MAG-CG-407 R5 C X- --
RIGID RESTRAI!ff FO.00 TC-SEG 14, EL 94 6
I I
I t
i l
l DATE: 11/26/96 PEACH BO N ATOMIC POWER STATION UNIT 2 PAGE:
38 l
REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 2 CAEP STATUS COMPONENTS RESIDUAL l' EAT REM %*AL 1
NR R
l ASME S OEGE l
SEC. XI T RCEP 1
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION B'J CK**
TCRUS SUCTION LOOP A (REF. DWG. NO. HB-10-MI-201-1-A) l 356300 10-2TSA24-4 C-F MT MAG-CG-40)
R5 'c X---
PIPE TO ELBOW C5.11 1
1 356550 10HB H11 F-A,B,C VT-3 MAG-CG-407 R5 C X-.-
SPRING CAN ON RIGHT SIDE MISSING ID/ LOAD SPRING HANGER FO.00 VT-4 MAG-CG 407 R5 X-SCALE TAG. AS-FOUND LOAD CALCULATED PER PROCEDURE.
l t
l TOR'JS SUCTION @ P C 'REF. DWG. NO. HB MI - 2 01 C) 359750 10HB-S1 F-A,B,C VT-3 MAG-CG-407 R5 C X--
- EXAM ALSO SATISFIES AUG-05 REQUIREMEMT.
HYDRAULIC SNUBBER F0.00 TC-SEG 16 EL 94 6 259950 10HB-H4 F-A,B,C VT-3 MAG-CG-407 RS C X...
SPRING CAN MISSING ID/LCAD SCALE TAG.
SPRING HANGER F0.00 VT-4 MAG-CG-407 RS X-..
AS-FOUND LOAD CALCULATED PER PROCEDURE, TORUS-IN-LOOP A (REF DWG. NO GB-10-MI-204-11-A) 364700 10-2TIA6-8 C-F MT MAG-CG-403 RS C X---
PIPE TO ELBOW C5.11 I
l l
1 l
i 1
i DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
39 I
REVISIOWs 5
INSERVICE INSPECTION SUtHARY SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96ftF)
CLASS 2 CAEP STATUS COMPONENTS MAIN STEAM NR R
ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS trJMBER IDENTIFICATION ITEM NO METHOD PROCEDUKE T CRMR " CALIBRATION BLOCK" MAINLINE LOOP C (PEF. DWG. NO, DB-01-MI 201-2 3),
374400 1-2C26-23 C-F MT MAG-CG-403 R5 A X..
- EXAMINATION PERFORMED AFTER ADDITIONAL PIPE TO ELBOW C5.21 SURFACE PREPARATION TO DISPOSTION A M SEP AREA,EL 152-6 NON-CODE AREA INDICATION RECORDED IN M SEP AREA,EL 152-6 2R10.
"2 6 -CS-X-1. 0 6 -2 8 + PEBe e MAINLINE LOOP D (P.EF. DWG. NO DB-01-MI-201-2-D) 277060 1DB-H12 F-A,B,C VT+3 MAG-CG-407 R5 C X...
LOAD SETTING FOUND OUT OF RANCE. REWORK SPRING RANGER FC.00 VT-4 MAG-CG-407 RS
.X..
PER AR 8 A1050842.
M SEP AREA, EL 14 9 4 277310 1DB-H13 F-A,B,C VT-3 MAG-CG-4 07 RS C X-
- LOAD SETTING FOUND OUT OF RANGE. REWORK SPRING HANGER FO.00 VT-4 MAG-CG 407 R5
.X..
PER AR # A1050859.
M SEP AREA, EL 14 9 4 BYPASS-LINE LOOP A fREF DWG. NO. DB-01-MI-222-5-A) 278350 7DB-510 F-A.B,C VT-3 MAG-CG-407 R5 C X-..
HYDRAULIC SNUBBER FC.00 M SEP AREA, EL 155-8 270400 1-2MSA18-5 C-F MT MT-PE-001 R2 C X-..
ELBOW TO MANIFOLD C5.21 UT-0 UT-PBM 106VD RO X-.-
UT.4 5 S UT-PBM-106VO RC
..X.
"14-CS-80 750-15-PEB" BYPASS-LINE LOOP B (PEP. DWG. NO. DB-01-MI-222-5 B) 2B1000 1-2MSB14-1 C-F MT MT-PE-001 R2 C X- --
TEE TO ELBOW C5.21 UT-0 UT-PSM-106VO R0 X..-
UT-45S UT-PBM-106VD R0 X..-
- 14-CS-80.750-15-PEB**
1 1
I 1
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
40 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL. THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 2 CAEP STATUS COMPONENTS MAIN STEAM NR R ASME S OEGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK" BYPASS-LINE LOOP B fREF. DWG NO DB-01-MI-222-5-B) 881150 7DS-H78 F-A,B.C VT-3 MAG-CG-407 RS C X..-
PER AR # A1050876, U/3 HANGER DWG IS SPRING HANGER F0.00 VT-4 M\\G-CG-407 R5 X---
APFLICABLE TO U/2. EC-ECR CREATED FOR M SEP AREA, EL 155-2 FINAL RESOLUTION.
i RX FEED PD TURB IN ' P.E F. DWG NO DP-01-MI-221-3) 284350 1DB H167 F-A,B C VT-3 MAG-CG-407 RS C X.--
j SPRING KANGER F0.00 VT-4 MAG-C3-407 R5 X---
FW HT MEZZ, EL 157-0 284500 1-2MSA6-6 C-F MT MT-RE-001 R2 C X---
TEE TO REDUCER C5.11 i
i I
)
284750 1DB-H172 F-A,B.C VT-3 MAG-CG-407 R5 C X...
ONE OF TWO LOAD SCALES MISSING. REWORK i
SPRING HANGER FO.00 VT-4 MAG-CG-407 R$
-X-.
PER AR # A1050882.
FW HT MEZ2,EL 159-11 t
I i
i
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
41 REVISIONt 5
INSERVICE INSPECTICN
SUMMARY
SECOND INTERVAL, THIRD PERIOD. SECOND OUTAGE (96RF)
CLASS 2 CAEP STATUS COMPONENTS SCRAM DISCHARGE VQLUMT NR R
ASME S OEGE SEC. XI T RCEP sue 99JtY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATICN ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK" NORTH fREF, DWG NO. CS-03-MI-201-1-A) 384854 S34 F-A,B,C VT-3 MAG-CG-407 R5 C X---
RIGID RESTRAINT FO.00 N RX BLDG, EL 151 6 880872 S1 F-A,B,C VT-3 MAG-CG-407 R5 C X---
RIGID AESTRAINT F0.00 N RX BLDG, EL 149 8 NORTH (REF, DWG. NO. CS-03-MI-201 2 A) 284883 E5 F-A,B.C VT 3 MAG-CG-407 R5 C X--.
RIGID RESTRAINT F0.00 N RX BLDG, EL 14 9-3 284890 57 F-A,B,C VT-3 MAG-CG-401 R5 C X---
RIGID RESTRAINT F0,00 N RX BLDG, EL 148-11 i
l 284892 3-2NSV6 27 C-F MT MAG-CG-403 R5 C X.--
ELBON TO PIPE C5.11 N RX BLDG, EL 148-11 i
1 284003 58 F-A,B.C VT-3 MAG-CG-407 RS C X---
RIGID RESTRAINT F0.00 N RX BLDG, EL 148 11 l
i 1
l
[
m..
m l
l
\\
1 DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
42 l
REVISION:
5 INSERVICE INSFECTION
SUMMARY
j SECOND INTERVAL, THIRD PERIOD, SECOND OITTAGE (96RF)
)
CLASS 2 CAEP STATUS COMPONENTS
)
COPE SPRAY NR R
ME S OEGE I
SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS i
NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK **
4 d
DISCHARGE LOOP A&C IREF. DWG. NO. GB 14-MT-203-4-A) 399250 14GB.H4 0 F-A.B.C VT.3 MAG.CG.407 R5 C X...
LOAD SETTING FOUND OITI OF RANGE. REWORK SPRING HANGER F0.00 VT.4 MAG.CG.407 R5
-X..
PER AR # A1031793.
SIVR, EL 136 4 4
^ 3D9275 14GB.H4 0 (I A)
C-C MT MAG CG 407 R5 C X...
LOAD SETTING FOUND OUT OF RANGE. REWORK INTEGRAL ATTACHMENT C3.20 PEF. AR S A1031793.
SIVR, EL 136 4 DISCHAPGE LOOP BED (REF DWG NO. GB-14-MI.203 4-B) 300940 14CB-H58 (IA)
C.C MT MAGrCG-403 RS C X INTEGRAL ATTACHMENT C3.20
)
NIVR, EL 136-5 DISCHARGE LOOP A fREF DWG. NO, GB.14-MI-202-2.A) 301275 14GB.H47 F-A,B,C VT.3 MAG-CG-407 RS C X.-.
SPRING HANGER F0.00 VT.4 MAG.CG.407 R5 X...
l 301500 14 2DA12 6 C.F MT MAG.CG.403 R5 C X-.-
2 VALVE TO PIPE C5.11 COPE SPRAY (REF. DWG, NO. GB 14-MI.202-2-A) 301550 14GB.S32 F.A,B,C VI-3 MAG.CG.407 R5 C X...
RIGID RESTRAINT F0.00 9
CORE SPRAY (REF DWG. NO. GB-14-MI-202-2-C) 304550 140B-833 F.A.B.C VT-3 MAG.CG-407 R5 C X--.
RIGID RESTRAINT FO.00 4
i DATE: 11/26/96 PEACH BOTIOM ATOMIC POWER STATION UNIT 2 PAGE:
43 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OLTIAGE (96RF)
I CLASS 2 CAEP STAWS COMPONENTS CORE SPRAY NR R
ME S OEGE j
SEC. XI T RCEP SUt94ARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS
{
NUMBER IDENTIF4 CATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK'*
j
)
l DISCHAPGE LOOP A&C (PEF DWG. NO. GB-14-MI 203-4-A) 307050 14MO-H59A F-A,B,C VT-3 MAG-CG-407 R5 C X---
SPRING KANGER FO.0D VT-4 MAG-CG-407 R5 X-.-
307100 14-2DAC12-16 C-F PT MAG-CG-4C2 R4 C X---
VALVE TO ELBOW C5.21 (Tf. 0 UT-PB-002V9 R1 X-.-
UT-45 UT-PB-002V9 R1
..X-UI-60 UT-PB 002V9 R1
.-X-
"12.SS-8 0. 6 87-12.PEB" TCPUS.IN-LOOP B ' PEF. DWG. NO CB-14 ->'I-2 0 3 B )
311700 14-2TIB10-8 C-F MT MAG-CG-403 R5 C X.--
ELBOW TO VALVE C5.11 1
I 1
DCTE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
44 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 2 CAEP STATUS COMPONENTS HICH PPESSUPE COOLANT TNJECTION NR R
MN 3 OECE SEC. XI T RCEP SUtNARY EXAMINATION AREA CATGY EXAM A EOOO REMARXS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCX**
I TORUS-SUCTION (REF. DWG. NO. HB-23-MI-201 1) 315300 23 27S16 13 C.F MT MAG.CG.403 R5 C X--
3 VALVE TO ELBOW C5.11 1
315300 23-2TS16-14 C-F MT a4AG-CG-4 03 R5 C X-..
j ELBOW TO PIPE C5.11
)
HPCI, EL 93-3 DISCHARGE (REF. DWG. NO. DON-23-MI-202-3) 318350 23MO-H47 F-A,B.C VT-3 MAG.CG.407 R5 C
.X-
- ROD FOUND BENT APF*0XIMATELY 0.15* AND SPRING HANGER F0.00 VT-4 MAG-CG-407 R5 X...
EVALUATED ACCEPTABLE AS.IS PER ARN HPCI RM. EL 109-0 A 1047248.
310800 23 2D14 19 C.F MT MAG.CG.403 R5 C X...
I ELBOW TO PIPE C5.21 UT-0 UT PB.002V9 R1 X...
UT.45 UT-PB.002V9 R1 X.
- *14.CS 100. 9 3 8 -8 A-PEB*
- 318050 23DDN-H17 F-A, B, C VT-3 MAG.CG-407 R$ C X...
SPRING HANGER F0.00 VT.4 MAG.CG-407 R5 X-..
TC.SEG 6, EL 109 0 310225 23DDN-H18 F-A,B,C VT 3 MAG.CG.407 R5 C X...
SPRING HANGER F0.00 VT.4 MAG.CG.407 RS X.-.
TC.SEG 7, EL 128-8 l
DISCHARGE (P EF DWG NO DDN-23.MI.202-4) l 310450 23DDN-H2O F.A,B,C VT.3 MAG CG-407 R5 C X..
SPRING HANGER FC.00 VT-4 MAG-CG.407 R5 X...
TC-SEG 9. EL 128 8 4
l p
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
45 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (S6RF)
CLASS 2 CAEP STATUS COMPONEN*3 HIGh PRESSUPE COOLANT INJECTION NR R
ASME S 0EGE SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARXS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK" DISCHARGE (REF. DWG, NO. DDN-23-MI-202-4) 319840 23DBN-H63 F-A,B.C VT-3 MAG-CG-407 R5 C X---
SPRING HANGER FC.00 VT-4 MAG-CG-407 R5 X---
C-C MT MT-PE-001 R2 C
-X--
INITIAL EXAM REVEALED A LIhT.AR INTEGRAL ATT7.CHMENT C3.20 INDICATION AND AFTER REWORX PER AR #
OBMSIV A1049474 WAS EXAMINED SAT.
0t77 (P.FF. DWG. No DBN-23-MI-203-7) 320740 23DBN S29 F-A,B,C vt-3 MAG CG-407 R5 C x---
HYDRAULIC SNUBBER F0.00 TC-SEG 4, EL 129-6 320750 23DBN-S29 (IA)
C-C MT MT-PE-001 R2 C X...
INTEGRAL ATTACHMENT C3.20 TC-SEG 4, EL 129 6
)
330760 23DBN-S28 F-A,B,C VT-3 MAG-CG-407 RS C
-X-.
INITIAL EXAM REVEALED LOOSE LOCK NCS HYDRAULIC SNUBBER F0.00 VT-4 MAG-CG-407 R5 X-..
AND AFTER REWORX PER AR # A1050870 WAS TC-SEG 4, EL 123-0 EXAMINED SAT.
320000 23-0-30 C-F IT*- 0 UT PBM-106VD RD C 7---
UT EXAM ONLY, MT NOT PERFORMED 2R11 AND j
ELBOW TO PIPE C5.21 ITI-4 5S UT-PBM-106VO RO
--X-WILL BE COMPLETED IN 2R12, i
"10-CS-8 0. 5 93-7A-PEB" 320950 23DBN-H43 F-A,B C VT-3 MAG-CG-407 RS C X-..
SPRING HANGER FC.00 VT-4 MAG-CG-407 RS X---
TC-SEG 4 EL 117-0 I
321400 23-0-35 C-F MT MT-PE.001 R2 C X--
- UT EXAM TO BE PERFORMED DURING 2R12.
PIPE TO ELBOW C5.21 "10-3 80. 593-7A-PEB" I
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
46 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTERVAL, THIRD PERIOD, SECOND OUTA0E (96RF)
CLASS 2 CAEP STATUS COMPONENTS HIGH PRESSURE CDOLANT INJECTION NR R
ASME S OEGE SEC, XI T RCEP l
SUb94ARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK'*
OUT (PEP DWO, NO. DBN-23-MI-203 *O 331500 23 0-36 C-F MT MT-PE-001 R2 C X..
MT EXAM ONLY IN 2R11, UT TO BE PERFORMED ELBOW TO PIPE C5.21
- 2R12,
- 10-CS-80.593 7A-PEB**
I 321525 23DDN-S27 F-A,B C VT-3 MAG-CG-407 RS C X...
HYDRAULIC SW 2BER F0,00 HPCI BM, EL U 2-0 333150 23DBN-53 F-A,B,C VT 3 MAO-CG-407 R5 C X...
HYDRAULIC SNUBBER FC.00 HPCI RM, EL 97 0 1
)
i J
I l
i
1 DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
47 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECCfD INTERVAL, THIRD PERIOD, SECOND OUIAGE (96RF)
CLASS 2 CAEP STATUS COMPONENTS l
SYSTEM HYDROSTATIC TEST l
NR R ASME S OEGE SEC. XI T RCEP S'.M4ARY EXAMINATION AREA CATOY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR ** CALIBRATION BLOCK *+
j PRESS VESS, PIPING.VLVS, pes 323075 CORE SPRAY SYSTEM C.H VT-2 ST.0-014 611-2 C X-..
EXAMINATION PERPORMED PER CODE ITEM PRESSURE RETAINING COMPONENTS VT-2
$7-0-014 616-2 X...
C7.40, 1
1 1
1 l
l l
f i
l
DATEt 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
48 REVISION:
5 INSERVICE INSPECTION SQ4 MARY j
f SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 3 CAEP STATUS COMPONENTS EMERGENCY SERVICE WATER NR R ASME S OEGE SEC. XI T RCEP CUMMARY EXAMINATION AREA CATCY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK **
DIESEL GENERATOR (REF. DWG. NO. HB-33-MI-201-3) 651350 33HB-521 F-A,B,C VT-3 MAG-CG-407 RS C X---
)
RIGID RESTRAINT F0.00 A DIESEL, EL 129 10 l
051375 33HB-S21 (I A)
D-B VT-3 MAG-CG-407 RS C X---
INTEGRAL ATTAC104ENT D2.20 A DIESEL, EL 129-10 DIESEL CENERATOR (REF. DWG. NO. HB-33-MI-201-2) 651500 33HB-S24 F-A,B,C VT-3 MAG.-CG-407 R5 C X---
RIGID RESTRAINT F0.00 I
CARDOX RM, EL 124-8 651650 33HB+S26 F-A,B,C VT-3 MAG-CG-407 RS C
.X--
EXAM REVEALED INSUFFICIENT THREAD RIGID RESTRAINT F0.00 ENGAGEMENT IN 1 OF 6 ANCHOR BOLTS. PER DIESEL, EL 121-9 ENGR'G EVAL (SEE ARS A-1036896) SUPPORT DIESEL, EL 121-9 IS ACCEPTABLE FOR CONTINUED / INTENDED SERVICE.
)
1 651675 33HB 526 (IA)
D-B VT-3 MAG-CG-407 RF C X.--
INTEGRAL AITACHMEFT D2.20 DIESEI., EL 121-9 G51800 33HB-5278 F-A.B.C VT-3 MAG-CG-407 R5 C X---
RIGID RESTRAINT F0.00 DIESEL, EL 124-8 051950 33HB-S30 F-A,B,C VT-3 MAG-CG-407 RS C X---
RIGID RESTRAINT FO.00 DIESEL, EL 125-11 4
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION IJNIT 2 PAGE:-
49 REVISION:
5 INSERVICE INSPECTION SUt91ARY SECOND INTERVAL, THIRD PERIOD, SECOND OITTAGE (96RF)
CLASS 3 CAEP STAWS COMPONENTS EMERGENCY SERVICE WATER NR R
ME S OEGE SEC. XI T RCEP
)
l SID99.RY EXAMINATION AREA CATGY EXAM A EOOO PEMARKS NUMBER IDENTIFICATION ITEM NO, METHOD PROCEDURE T CRMR " CALIBRATION BLOCX" DIESEL GENERATOR (REF. DWG. NO, HB-33-MI-2 Q 651975 33HB-S30 (IA)
D-B VT-3 MAG-CG-407 R5 C X---
I INTEGRAL ATTAw W D2.20 DIESEL, EL 125-11 (REF. DWG. NO. WP-33-MI-201-01 654450 33HB H114 F-A,B,C VT-3 MAG-CG-407 R5 C X---
SPRING HANGER F0.00 VT-4 MAG-CG-407 R5 X---
j RBCCW RM, EL 125-9 650475 33HB H114 (IA)
D-B VT-3 MAG CC-407 RS C X---
{
IrrrEGRAL ATTAM-D2.40 RBCCW RM, EL 125-9 654600 33HB-5138 F-A,B.C VT 3 MAG-CG-407 R5 C X---
RIGID RESTR4IliT F0.00 RBCCW RM, EL 129-13 i
D-B VT 3 MAG-CG-407 R5 C X-INTEGRAL ATTACHMENT D2.20 RBCCW RM, EL 129-10 (REF, DWG. NO. HB-33-MI-201-12) 655150 33HB-S63 F-A,B.C VT-3 MAG-CG-4 07 R5 C X---
RIGID RESTRAINT F0.00 RBCCW RM, EL 130-0 I
L G53300 33HB-S66 F-A,B,C VT-3 MAG-CG-407 R5 C X---
l RIGID RESTRAINT FO.00 RBCCW RM, EL 125-6
-I a
1
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.. -... _ = -
. _.~
1 1
i i
DATES 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
50 REVISION:
5 INSERVICE INSPECTION
SUMMARY
e SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
CLASS 3 CAEP STATUS COMPONENTS EMERGENCY SERVICE WATER NR R
AS4 S OEGE J
SEC. XI T RCEP
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BIDCK**
1
]
(REF. DWG. NO. HB-33-MI-201-12) 655450 33HB-S69 F-A,B,C VT-3 MAG-CG-407 R5 C X---
RIGID RESTRAINT F0.00 4
2 655750 33HB-5157 F-A,B,C VT-3 MAG-CG-407 RS C X---
4 RIGID RESTRAINT F0.00 RBCCW RM, EL 125-6
$F DWG NO HB-33-MI-201 H 1
656000 33HB 574 F-A,B,C VT-3 MAGrCG-407 R5 C X---
RIGID.',FS % INT FO.00 RBCCW RM, EL 128-0 1
+
t i
D-B VT-3 MAG-CG-407 R5 C X..-
INTEGRAL ATTACHMENT D2.20 RBCCW RM, EL 128-0 656110 33HB-S77 F A,B,C VT-3 MAG-CG-407 R5 C X...
RIGID RESTRAINT FC.00 RBCCW RM, EL 128-0 i
i I
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1
. _. ~.
~~...
~..
l 1
DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER bi'ATION UNIT 2 PAGE:
51 REVISION:
5 INSERVICE INSPECTION SU WARY SECOND INTERVAL, THIRD PERIOD, SECOND OLTIAGC (96RF)
CLASS 3 CAEP STATUS COMPONENTS EMERGENCY COOLING WATER NR R
I ASME S OEGE SEC. XI T RCEP SU MARY EXAMINATION AREA CATGY EXAM A EOOO REMARKS 1
WUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK **
i EMERGENCY M LING WATER (REF, DW3. NO, HB-48-MI-001-1) 656275 48HB.H60 F A B,C VT-3 MAG-CG-4*'
P 5 "a X...
RIGID RESTRAINT F0.00 EMRGNCY COOL TOWERS 5
656280 4 8HB-H60 (IAI D-B VT-3 MAG-CG-4 07 R5 C X INTEGRAL ATTACHMENT D2.20 EMRGNCY COOL TOWERS EMERGENCY COOLING WATER (PEF DWG. FO HB-49 MI 001-4) 656600 48HB-H36 F.A,B,C VT.3 MAG;CG-407 RS C X-..
RIGID RESTRAINT FC.00 EMRGNCY COOL TOWERS I
D-B VT-3 MAG-CG-407 RS C X...
INTEGRAL ATTACHMEhi D2.20 t
EMRGNCY COOL TOWERS 656627 48CB-838A F-A,B,C VT-3 MAG-CC.407 R5 C X...
CUIDE F0.00 1
EMRGNCY COOL TOWERS 656634 48HB-H11 F-A,B,C VT.3 MAG-CG-407 RS C 1-..
RIGID HANGER FC.00 EMRGNCY COOL TOWERS EMERGENCY COOLING WATER (REF DWG. NO GB 48-MI.001-2) j 657010 4 8GB-H25 (I A)
]
INTEGRAL ATTACHMEtTI' D2.20 i
EMRGNCY COOL TOWERS
DATER 11/26/96 PEACH BOTIOM ATOMIC POWER STATION UNIT 2 PAGE:
52 REVISION:
5 INSERVICE INSPECTION SIM4ARY
)
SECOND INTERVAL, THIRD PERIOD, SECOND 07FAGE (96RF) i CIASS 3 CAEP STATUS COMPGNENTS EMERGENCY COOLING WATER NR R
ASME S OEGE SEC. XI T RCEP I
SUWARY EL*,;4INATION AREA CATGY EXAM A EOOO REMARKS I' UMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCX**
l
]
EMERGENCY COOLING WATER fREF. DWG. NO, GB-48-M!-001-2) 657438 48CB-H45 F-A,B,C VT-3 MAG-CG-407 RS C X*.
l RIGID RESTRAINT F0.00 EMRG COOL TWR,EL 219 l
D-B VT-3 MAG-CG-407 R5 C X.--
INTEGRAL ATTACHMENT D2.20 EMRCNCY COOL TOWERS 657450 48GB-H23 F.A,B C VT-3 MAG-CG-407 RS C X.--
RIGID HANGER FO.00 EMRG COOL TWR,EL 119 l
EMEPGENCY COOLING WATFR (REF. DWG. NO HB-48-MI-001-3) 657070 48HB-HF1 F-A,B,C VT-3 MAC-CG-407 R5 C X.
SPRING HANGER FO.00 VT-4 MAG-CG-4 07 R5 X..-
CARDOX RM, DIES BLDG G57973 48HB-HF1(IA)
D-B VT-3 MAG-CG-407 RS C I.-.
INTEGRAL ATTACHMENT D2.20 EMRGNCY COOL TOWERS j
658035 48HB-HF3A F-A,B.C VT-3 MAG-CG-407 R5 C X*..
RIGID RESTRAIrrt F0.00 CARDOX RM, DIES BLDG 658026 48HB-HF3A(IA)
D-B VT.3 MAG CG-407 RS C X---
INTEGRAL ATTACHMENT D2,20 EMRGNCY COOL TOWERS EMERGEN"Y COOLING WATER (REF. DWG. NO. GB-48-MI-001-3) 654083 48CB 523 F-A,B,C VT-3 MAG-CG-407 RS C X.--
GUIDE F0.00 EMRG COOL TWR,EL
DATE: 11/26/96 PEACH SOTTOM A M IC POWER STATION UNIT 2 FACE:
53 REVISION:
5 INSERVICE INSPECTION StJMMARY SECOND !srTERVAL, THIRD PERIOD, SECOND OITIAGE (96RF)
CLASS 3 CAEP STATUS COMPONENTS EMERGENCY COOLING WATER NR R ASME S OEGE SEC. II T RCEP 7
SUMMARY
EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK **
EMERGENCY COOLING WATER (REF. DWG. NO. CB-49-MI-001-3) 658088 48GB-S17 F-A,B,C VT-3 MAG-CG-407 RS C X..-
RIGID RESTRAINT FO.00 EMRG COOL TWR,EL 6580C0 48CB-S17 (IA)
D-B VT-3 MAG-CG-407 RS C X---
INTEGRAL ATTACHMENT D2.20 EMRCNCY COOL TOWERS i
I 658096 40GB-54 F-A,B,C VT-3 MAG-CG-407 R5 C X.--
RIGID RESTRAINT FC.00 EMRG COOL'!WR,EL l
D-B VT-3 MAG-CG-407 R5 C X--.
INTEGRAL ATTACHMENT D2.20 EMRGNCY COOL TOWERS 658104 48CB-H18 F-A,B,C VT-3 MAG-CG-407 RS C X.-.
RIGID RESTRAINT FC.00 EMRG COOL TWR,EL 658106 48CB-H18 (IA)
D-B VT-3 MAG-CG.407 R5 C X..
INTEGRAL ATTACHMENT D2.20 EMRCNCY COOL TOWERS I
G58113 48GB-H64 F-A,B,C VT-3 MAG-CG-407 R5 C X...
RIGID RESTRAINT F0.00 EMRG COOL TWR,EL 65C114 48GB-H64 (IA)
D-B VT-3 MAG-CG-407 R5 C X---
INTEGRAL ATTACHMENT D2.20 EMRCNCY COOL TOWERS
. -.. ~. -
~.
i DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGE:
54 REVISION:
5 INSERVICE INSPECTION SUP9%RY SECOND INTERVAL, THIRD PERIOD, SECOND OUTAGE (96RF)
C:J4S 3 CAEP STATUS COMPONENTS EMERGENCY COOLING WATER NR R
ASME S OEGE SEC. XI T RCEP StM%RY EXAMINATION AREA CATGY EXAM A EOOO REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK" EMERGEN N COOLING WATER (REF. DWG, NO. CB-48-MI-001-3) 658120 48CB-332 F-A.B.C VT-3 MAG-CG-407 R5 C X---
RIGID RESTRAINT F0.00 EMRG COOL TWR,EL 658133 48GB 532(IA)
D-B VT 3 MAG-CG-407 RS C X---
INTEGRAL ATTACHMENT D2.20 EMRGNCY COOL TOWERS EMERGEN N COOLING WATER fREF. DWG, NO. MB-48-MI-001-5%,
659070 48HB-511 F-A,B,C VT-3 MAG CG-407 RS C X.--
RIGID RESTRAINT FO.00 EMRG COOL TWR,EL 659072 48HB-S11(IA)
D-B VT-3 MAG CG-407 R5 C X---
INTEGRAL AITACHMENT D2.20 EMRGNCY COOL TOWERS 659078 48HB-E8 F.A,B,C VT-3 MAG-CG-407 R5 C X---
RIGID RESTRAINT F0.00 EMRG COOL TWR,EL l
050080 48HB-H8 (I A)
D-B VT-3 MAG-CG-407 R5 C X---
INTEGRAL ATTACHMENT D2.20 EMRGNCY COOL TOWERS 650083 48HB-H6 F-A.B C VT-3 MAG-CG-407 RS C X.--
l RIGID RESTRAINT FC.00 SMRG COOL TWR,EL i
t i
D-B VT-3 MAG-CG-407 R5 C X INTEGRAL ATTACHMENT D2.20 EMRGNCY COOL TOWERS I
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I I
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DATE: 11/26/96 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 PAGEs 55 REVISION:
5 INSERVICE INSPECTION
SUMMARY
SECOND INTE*"\\L, THIRD PERIOD, SECOND OUTAGE (96RF)
CL.JiS 3 CAEP STATUS COMPONE3rTS EMERGEN"Y COOLING WATER
)
NR R
ASME S OEGE SEC. XI T RCEP
)
SIR 91ARY EXAMINATION AREA CATUY EXAM A EOOO UMARKS NUMBER IDElfrIFICATION ITEM NO METHOD PROCEDURE T CRMR " CALIBRATION BLOCK" i
EMERGENCY COOLING WATER (REF. DWG. NO. NB-46-MI.001-5) 659090 48HB-H5 F-A,B.C VT-3 MAG-CG-407 R5 C X.-.
l RIGID RESTRAINT F0.00 I
EMRG COOL TWd,EL 659092 48HB-H5(IA)
D-B VT-3 MAG-CG-4 07 R5 C X...
INTEGRAL ATTACHMENT D2.20 EMRGNCY COOL TOWERS 659098 48HB-H3 F.A,B,C VT 3 MAG-CG-407 R5 C X RIGID RESTRAINT F0.00 EMRG COOL TWR,EL 659100 4 BHB-M3 (IA)
D-B VT-3 MAG-CG-407 RS C X.-.
INTEGRAL ATTACHMENT D2.23 EMRCNCY COOL TOWERS 659106 4BKB-833 F-A.B,C VT-3 MAG-CG-407 R5 C X.-.
RIGID RESTRAINT F0.00 EMRG COOL TWR,EL 659108 48KB-S33(IA)
D-B VT 3 MAG-CG.407 RS C X--.
INTEGRAL ATTACHMENT D2.2 0 EMRGNCY COOL TOWERS i
i e
i l
l
i Section 2 4
)
a
-i 4
t 4
i
SUMMARY
OF REPORTABLE CONDITIONS OBSERVED DURING IN-SERVICE INSPECTION PEACH BOTTOM ATOMIC POWER STATION UNIT 2 OCTOBER 22,1994 TO OCTOBER 03,1996 l
I
Section 2 Page 1 of 1 i
SUMMARY
OF REPORTABLE CONDITIONS OBSERVED As a result of examinations performed prior to and during the Unit 2,11th Refuel Outage, numerous conditions were reported. Subsequent examinations and/or evaluations determined most conditions to be either insignificant or geometric in nature. However, several reportable conditions were recorded and are summarized below-10-35.18-15.26-11.26-39.26-47.26-51.30-19 CRD Flange Bolting During the exchange of Control Rod Drives, damaged threads were found on: 4 bolts on CRD #10-35, 3 bolts on CRD #18-15,7 bolts on CRD #26-11,1 bolt on CRD #26-39,4 bolts on CRD #26-47,4 bolts on CRD #26-51 and 3 bolts on CRD #30-19.
P2B Weld "B" Core Spray Supply Pipe On the T-Box cover plate weld #P28, cracking was observed in 2 areas, from 2 to 4 o' clock approximately 38 deg in length and from 8 to 10 o' clock approximately 48 deg in length. An engineering evaluation was performed and concluded that the T-Box cover plate will maintain its integrity through the next operating cycle. Reference NCR #96-03414.
H-1. H-6. H-7 Core Shroud Welds On weld H-1,14 - IGbCCliASCC associated indications totaling 114.54 in. were reported in the 389.27 in. of weld length examined. On weld H-6, 6 -IGSCC/lASCC associated indications totaling 29.42 in.
were repo ted in the 540.46 in. of weld length examined. On weld H-7,4 - IGSCC/lASCC associated indication!, tvaling 14.70 in. were reported in the 547.16 in. of weld length examined. Details of these reportable ind ;ations can be found in the PB 2R11 ISI Summary Report. An engineering evaluation of these indications was made using the approach outlined in the "BWR Core Shroud Inspection and Flaw Evaluation Guidelines." This evaluation concluded that the subject welds can support continued operation for at least 2 operating cycles of 24 months at power rerate conditions. Reference NCR #96-03492.
i 12-14-5 Weld Reactor Water Clean-up Piping On augmented pipe to elbow weld 12-14-5, an approximate 0.625 in. long crack characteristic of IGSCC was reported. Previous examination of the weld revealed recordable I.D. geometric indications.
An engineering evaluation was performed and the decision was made to repair the weld. Reference NCR #96-03344.
i Section 3 i
d 1
4 i
f 4
1 t
SUMMARY
OF ASME REPAIRS 4
AND REPLACEMENTS COMPLETED P
FOR PEACH BOTTOM ATOMIC POWER STATION a
i UNIT 2 OCTOBER 22,1994 TO OCTOBER 3,1996 i
4 i
a f
4 k
8
SECTION 3 Paga 1 of 3
SUMMARY
OF ASME SECTION XI REPAIRS AND REPLACEMENTS System 01:
Main Steam LOG #
WORK ORDER #
COMPONENT ID DESCRIPTION OF WORK 95-114 C0166478 RV-2-02-071 C Installed new valve 96-005 R0467879 1-GG-S-9 Installed new pressurized reservoir snubber 96-006 R0467878 1-GG-S-5 Installed new pressurized reservoir snubber 96-007 R0467881 1-GG-S-15 Installed new pressurized reservoir snubber 96-009 R0467883 1-GG-S-25 Installed new pressurized reservoir snubber 96-010 R0467888 1-GG-S-30 installed new press. res, snubber and clamp bushings96-011 R0468214 1-GG-S-31 Installed new press. res. snubber and clamp bushings96-018 C0167502 1-GG-S-104-A installed new pressurized reservoir snubber 96-037 R0600765 RV-2-02-071F Installed new valve 96-038 R0600766 RV-2-02-071G Installed new valve 96-039 R0600767 RV-2-02-071 E Installed new valve 96-040 R0600769 RV-2-02-071 H Installed new valve 96-041 R0600773 RV-2-02-071 B Installed new valve 96-042 R0600775 RV-2-02-070B installed new valve 96-045 R0467886 1-GG-S-28 Installed new pressurized reservoir snubber 96-047 R0467880 1-GG-S-13 Installed new pressurized reservoir snubber 96-048 R0468234 1 GG-S-77 Installed new pressurized reservoir snubber 96-077 C0172388 RV- (S/N 1095)
Repaired gouge on flange face seating surface 96-081 C0172756 HV-2-01 A-83A Installed new valve bonnet 96-082 C0172760 HV-2-01 A-84C Installed new valve bonnet 96-083 C0172776 1-GG-S-32 Reworked snubber load pin hole and bushings96-084 C0172780 1-GG-S-17 Reworked snubber load bearing paddle
. _ _. _.=
i SECTION 3 Page 2 of 3 System 03:
Control Rod Drive
[
t LOG #
WORK ORDER #
COMPONENT ID DESCRIPTION OF WORK 96-044 R0617003 Replaced 19 CRD's housing bolting System 06:
Feedwater System LOG #
WORK ORDER #
COMPONENT ID DESCRIPTION OF WORK j
94-178 C0157280 CHK-2-06-28B Welded new seal plate in valve body i
System 10:
Residual Heat Removal System i
LOG #
WORK ORDER #
COMPONENT ID DESCRIPTION OF WORK 94 137 C0153793 PB-2-10-2DE024 Seal weld floating head 94-152 C0155236 10-HB-2-3 Install sway strut shims94-158 C0149015 2-10MO-H98 Rework hanger support 96-016 C0161643 RV-2-10-072B Installed new relief valve l
96-025 R0470777 10-DCN-S-73 Installed new pressurized reservoir snubber
)96-067 C0169716 10-GB-S-48 Installed new pressurized reservoir snubber 96-074 C0170532 RO-2789A Installed and removed blank flange to isolate MO-089A i
96-075 R0480861 RV-2-10-181C Installed new relief valve 1
i System 11:
Standby Liquid Control System LOG #
WORK ORDER #
COMPONENT ID DESCRIPTION OF WORK 96-033 R0598035 RV-2-11-39B installed new relief valve i
System 12:
Reactor Water Cleanup System LOG #
WORK ORDER #
COMPONENT ID DESCRIPTION OF WORK 96-091 C0172742 Weld #12-14-05 Performed weld overlay on weld #12-14-05 i
System 13:
Reactor Core isolation Cooling System 1
LOG #
WORK ORDER #
COMPONENT ID DESCRIPTION OF WORK
{
96-055 R0468347 13-HB-S-14 Installed new pressurized reservoir snubber j
Mod C0168841 2" SCH 80 Extended piping per NCR #95-00090 I
- PB !
2R11M l
l
I SECTION 3
]
Page 3 of 3 j
System 14:
Core Spray System LOG #
WORK ORDER #
COMPONENT ID DESCRIPTION OF WORK 96-026 R0470782 14-DCN-S-23 Installed new pressurized reservoir snubber 96-050 R0468261 14-DCN-S-24 installed new pressurized reservoir snubber 96-051 R0468285 14-DCN-S-27 Installed new pressurized reservoir snubber 3
i System 23:
High Pressure Coolant injection LOG #
WORK ORDER #
COMPONENT ID DESCRIPTION OF WORK 96-003 C0167929 23-HB-S-30 Replaced snubber pipe clamp bolting i
96-014 C0158006 23-DBN-H64 Replaced hanger rod 3
96-052 R0468310 23-DBN-S-23 Installed new pressunzed reservoir snubber 96-056 R0468352 23-DBN-S-27 Installed new pressurized reservoir snubber 1
96-057 R0649937 23-DBN-S-4 installed new pressurized reservoir snubber Mod C0168840 2* SCH 80 Extended piping per NCR #95-00090 f
- PB l 2R11M System 32:
High Pressure Service Water LOG #
WORK ORDER #
COMPONENT ID DESCRIPTION OF WORK 4
94-131 R0464141 RV-2-32-180D installed new valve i
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