ML20113B053
| ML20113B053 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/29/1995 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20113B021 | List: |
| References | |
| PROC-951229, NUDOCS 9606260153 | |
| Download: ML20113B053 (80) | |
Text
i COOPER NUCLEAR STATION BECOND TEF YEAR INTERVAL INS RVICE 7.NSPECTION PROGRAM kMVISION 4.1 DATE OF ISSUE: December 29, 1995 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION l
SECOND TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM for ASME Class 1, 2 and 3 Components l
Revision 4.1 4
l f
This aumendment to revision 4 of the Second Ten-Year Interval i
i Inservice Inspection Program addresses minor editorial changes, I
makes adjustments to the weld examination lists, incorporates NRC l
comments, and adds new relief requests identified during RFO-16.
i i
SECTION PAGE(S)
DESCRIPTION
.i j
Introduction 1&2 Revised the and date for the second l
interval.
2 Category B-A All Added Relief Request RI-06 Rev. 2 Category B-D All Added Relief Request RI-21 Category B-F NBI Added Relief Request RI-20 Category B-J MS Deleted weld MED-BJ-51, field examination determined that weld j
reputed to be on the Main Steam i
system does not exist.
Category B-J NBI Revised examination schedule I
Category C-F RCIC Added Relief Request RI-23 Category C-G All Deleted welds PNC-CG-20A/B and PNC-CG-23A/B, field examination j
determined that there are no welds i
present on the 20 inch valves.
Category D-A SW &
Deleted welds, field examination REC determined that there are no i
integral attachment welds present on the SW Booster pumps or REC pumps.
3 Augmented Tab 14 2 - 15 Revised REC Wald Examination Table i
for substituted welds l
Page 1 of 2 1
9606260153 960620 i
g
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM REVISION 4.1 SECTION PAGE(8)
DESCRIPTION Augmented Tab 21 All Revised response to SIL 571.
Relief Requests All Revised RI-06, deleted RI-17, added RI-20, 21, 22, and 23, revised note 6,
and added notes 7, 8,
9, and 10.
RI-06 All Revised to add access restrictions for bottom head circumferential weld and shall to flange circumferential weld RI-07 All Re-issued to correct typographical errors RI-17 All Deleted RI-20 All Added relief request for access restictions on RVD-BF-14 RI-21 All Added relief request for eccess restrictions on RPV Nossle-to-vessel Welds RI-22 All Added relief request for access restrictions on Branch Connection Welds RI-23 All Added relief request for access restrictions on submerged RCIC Pinine Welds Page 2 of 2
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM REVISION
4.1 INTRODUCTION
1.0 BASIS FOR THE INSERVICE INSPECTION PROGRAM This revision to the Second Interval ISI Program was required as a result of deficiencies in the boundary classification of essential components identified in NRC Inspection Report 93-17, LER 94-11, and LER 94-032.
A comprehensive review of the Program identified certain other additions, corrections, and deletions.
The Cooper Nuclear Station (CNS), Inservice Inspection Program (ISI) is required by 10CFR50.55a(g) and the plant Technical Specifications.
Burns and Roe, the Architect Engineer for Cooper Nuclear Station during construction, was NPPD's agent.in determining the ASME Code classifications of plant components.
NRC Regulatory Guide 1.26 was not yet published; hence, it was not used during construction.
NPPD has since developed a procedure for equipment safety classification and an ISI Boundary Basis document, CCFMD-1.
This ISI Boundary Basis document and the following guidance documents were used in developing this program:-
Regulatory Guide 1.26, Revision 3, February 1976, Quality Group Standards for Water, Steam, and Radioactive-Waste-Containing Components of Nuclear Power Plants Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division I Updated Final Safety Analysis Report, Cooper Nuclear Station Technical Specifications, Cooper Nuclear Station 2.0 THE SECOND TEN YEAR INSPECTION INTERVAL 2.1 The commercial operation date for Cooper Nuclear Station is July 1, 1974.
The end of the first interval was extended from June 30, 1984, to June 1, 1985, due to the 1984/85 pipe replacement outage.
This was allowed by IWA-2400/12 00 (c).
The end of the second interval was originally scheduled for May 31, 1995.
Due to extended outage of 1994, the end of the second interval was extended to February 29, 1996, as allowed by IWA-2400(c).
Page 1 of 6 A
m W
tM*-W-T
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM REVISION 4.1
{
(
INTRODUCTION l
2.2 The three inspection periods during the t.econd interval
]
are as follows:
i l
First Period From June 1, 1985, to August 31, 1988 Second Period: From September 1, 1988, to December 31, i
1991 i
Third Period:
From January 1, 1992, to February 29, 1996 3.0 APPLICABLE ASME CODE i
3.1 Inservice Inspection of ASME ClEps 1, 2,
and 3 components and their supports is performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, l
1980 Edition through Winter 1981 Addenda, except as l
allowed by 10CFR50 or where specific written relief from l
examinations and tests. determined to be impracticable has been granted by the NRC pursuant to 10CFR Part 50, Section 50.55a (g) (6) (i).
3.2 ASME Code Cases that have been approved by the NRC per Regulatory Guide 1.147 and have been adopted for use at the Cooper Nuclear Station are identified in the Program.
4.0 INSERVICE INSPECTION PROGRAM 4.1 The. Inservice Inspection (ISI) Program is a detailed living document which is available to the regulatory i
authorities for audit.
4.2 The ISI Program provides:
4.2.1 ASME Section XI examination category and item listing.
4.2.2 Specific examination identification and location.
4.2.3 Weld joint configurations.
4.2.4 Nondestructive examination-procedures.
4.2.5 Ultrasonic calibration standards list.
4.2.6 Applicable list of isometric drawings.
Page 2 of 6 1
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM REVISION 4.1 AUGMENTED INSERVICE INSPECTIONS INSTRUMENT NOZZLE SAFE ENDS Augmented supplemental volumetric examinations of the entire instrument nozzle safe end for nozzles N10, NilA/B, N12A/B, and N16A/B will be performed when flaws are detected during the scheduled surface examination in accordance with the ISI l
program.
The surface examination will be extended to cover the entire instument nozzle safe end.
These examinations will begin in 1995 as recommended in GE SIL No. 571.
l l
l l
Page 1 of 1
l IWB-2500-1 CAT:
B-A COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL PI PE.................. SYSTEM.. CNT. ITEM.NO. CF I G... SIZE.. TILMS..... MAT... W81. CAL.. 150................. MT.. UTD.. UT45.... UT60.... PER.... RELREQ REMARKS................
l l VCB-BA-2 NB 1
B1.11 VE-C 218 7.2/6.2 RPV 1 16 GE.BN-3 1
1 1
3 RI-06 RI-06
- NOT ACESSIBLE.
BELTLINE REGION WELD...
VCB-BB-1 NB 1
B1.11 VE-C 218 3.2/7.2 RPV 1 15/16 GE.BN-3 1
1 1
3 RI-06 j
VCB-BB-3 NB 1
B1.11 VE-C 218 6.2 RPV 1 16 GE.BN-3 1
1 1
NOT ACCESSIBLE VCB-BB-4 NB 1
B1.11 VE-C 218 6.2 RPV 1 16 GE.BN-3 1
1 1
4 ***
VLA-BA-S NB 1
B1.12 VE-LS 218 7.2 RPV 1 16 GE.BN-3 1
1 1
3 RI-06 RI-06
- PARTIALLY ACCESSIBLE... BELTLINE REGION WELD...
ULA-BA-2 NB 1
B1.12 VE-LS 218 7.2 RPV 1 16 GE.BN-3 1
1 1
RI-06 RI-06
- PARTIALLY ACCESSIBLE... BELTLINE REGION WELD...
VLA-BA-3 NB 1
81.12 VE-LS 218 7.2 RPV 1 16 CE.BN-3 1
1 1
RI-06 RI-06
- PARTIALLY ACCESSIBLE... BELTLINE REGION WELD...
VLB-BA-1 NB 1
81.12 VE-LS 218 6.2 RPV 1 16 GE.BN-3 1
1 1
RI 36 RI-06
- NOT ACCESSIBLE.
BELTLINE REGION WELD...
VLB-BA-2 NB 1
B1.12 VE-LS 218 6.2 RPV 1 16 GE.BN-3 1
1 1
RI-06 RI-06
- NOT ACCESSIBLE.
BELTLINE REGION WELD...
VLB-BA-3 NB 1
B1.12 VE-LS 218 6.2 RPV 1 16 GE.BN-3 1
1 1
RI-06 RI-06
- WOT ACCESSIBLE.
BELTLINE REGION WELD...
VLC-BB-1 NB 1
81.12 VE-LS 218 6.2 RPV 1 16 GE.BN-3 1
1 1
PARTIALLY ACCESSIBLE VLC-BB-2 NB 1
B1.12 VE-LS 218 6.2 RPV 1 16 GE.BN-3 1
1 1
PARTIALLY ACCESSIBLE VLC-BB-3 NB 1
B1.12 VE-LS 218 6.2 RPV 1 16 GE.BN-3 1
1 1
PARTIALLY ACCESSIBLE VLD-BB-1 NB 1
B1.12 VE-LS 218 6.2 RPV 1 16 GE.BN-3 1
1 1
3 RI-06 VLD-BB-2 NB 1
B1.12 VE-LS 218 6.2 RPV 1 16 GE.BN-3 1
1 1
VLD-BB-3 NB 1
B1.12 VE-LS 218 6.2 RPV 1 16 GE.BN-3 1
1 1
3 RI-06 28 DECEMBER 1995 PAGE 1
IWB-2500-1 CAT: B-A COOPER NUCLEAR STATION IhSERVICE INSPECTION PROGRAM REY: 4.1 SECOND INTERVAL P I PE.................. SYSTEM.. CNT. I TEM.NO. CFI G... SIZE.. TKNS..... MAT... W81. CAL.. 1 S0................. MT.. UT0.. UT45.... UT60.... PER.... RELREQ REMARKS................
12 ***
HMC-BB-1 NB 1
B1.21 BHD-C 218 3.5 RPV 1 15 GE.BA-3,BA-4 1
1 1
2 RI-06 0 70 360 DAZ...
HMD-BB-1 NB 1
81.21 BMD-C 218 7.1 RPV 1 16 GE.BA-3,BA-4 1
1 1
- NOT ACCESSIBLE...
HMD-BB-3 NB 1
81.21 THD-C 218 3.2 RPV 1 15 GE.BA-3,BA-4 1
1 1
3 0 TD 360 DA2
'3 HMA-BB-1 NB 1
B1.22 BMD-M 218 3.5 RPV 1 15 GE.BA-3,BA-4 1
1 1
HMA-BB-2 NB 1
B1.22 BHD-M 218 3.5 RPV 1 15 GE.BA-3,BA-4 1
1 1
HMA-BB-3 NB 1
B1.22 BMD-M 218 3.5 RPV 1 15 GE.BA-3,BA-4 1
1 1
MMA-BB-4 NB 1
81.22 BMD-M 218 3.5 RPV 1 15 GE.BA-3,BA-4 1
1 1
HMA BB-5 NB 1
B1.22 BMD-M 218 3.5 RPV 1 15 GE.BA-3,BA-4 1
1 1
HMA-BB-6 NB 1
B1.22 BMD-M 218 3.5 RPV 1 15 GE.BA-3,BA-4 1
1 1
HMA-BB-7 NB 1
B1.22 BHD-M 218 3.5 RPV 1 15 GE.BA-3,BA-4 1
1 1
1 1
3 HMA-BB-8 NB 1
B1.22 BMD-M 218 3.5 RPV 1 15 GE.BA-3,BA-4 HMB-BB-1 NB 1
B1.22 BHD-M 218 7.1 RPV 1 16 GE.BA-3,BA-4
~
1 1
1 RI-06 RI-06 ** PARTIALLY ACCESSIBLE HMB-BB-2' NB 1
B1.22 BMD-M 218 7.1 RPV 1 16 GE.BA-3,BA-4 1
1 1
1 RI-06 RI-06 ** PARTIALLY ACCESSIBLE HMB-88-3 NB 1
81.22 BHD-M 218 7.1 RPV 1 16 GE.BA-3,BA-4 1
1 1
2 RI-06 RI-06 ** PARTIALLY ACCESSIBLE HMB-BB-4 NB 1
B1.22 BHD-M 218 7.1 RPV 1 16 GE.BA-3,BA-4 1
1 1
2 RI-06 RI-06 ** PARTIALLY ACCESSIBLE HMB-88-5 NB 1
B1.22 BHD-M 218 7.1 RPV 1 16 GE.BA-3,BA-4 1
1 1
3 RI-06 RI-06 ** PARTIALLY ACCESSIBLE HMB-BB-6 NB 1
81.22 BMD-M 218 7.1 RPV 1 16 GE.BA-3,BA-4 1
1 1
3 RI-06 RI-06 ** PARTIALLY ACCESSIBLE HME-BB-9 NB 1
B1.22 THD-M 218 3.2 RPV 1 15 GE.BA-3,BA-4 1
1 1
HME-BB-2 NB 1
B1.22 THD-M 218 3.2 RPV 1 15 GE.BA-3,BA-4 1
1 1
28 DECEMBER 1995 PAGE 2 s-
IWB-2500-1 CAT:
B-A CODPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM REY: 4.1 SEcc e INTERVAL PI PE.................. SYSTEM.. CNT. I TEM.No. CF I G... SIZE.. TKNS..... MAT... W81. CAL.. 150................. MT.. UTO.. UT45.... UT60.... PER.... RELRES REMARKS................
HME-BB-3 NB 1
B1.22 TMD-M 218 3.2 RPV 1 15 GE.BA-3,BA-4 1
1 1
HME-BB-4 NB 1
81.22 TMD-M 218 3.2 RPV 1 15 GE.BA-3,BA-4 1
1 1
l HME-BB-5 NB 1
B1.22 TMD-M 218 3.2 RPV 1 15 GE.BA-3,BA-4 1
1 1
HME-BB-6 NB 1
81.22 THD-M 218 3.2 RPV 1 15 GE.BA-3,BA-4 1
1 1
HME-88-7 NB 1
B1.22 TMD-M 218 3.2 RPV 1 15 GE.BA-3,BA-4 1
1 1
3 HME-BB-8 NB 1
B1.22 THD-M 218 3.2 RPV 1 15 GE.BA-3,BA-4 1
1 1
22 ***
i VCB-BC5-1 NB 1
B1.30 VE-F 218 6.2 RPV 1 16 GE.BN-3 1
1 1
1 RI-06 7 TO 127 DAZ...
VCB-BC5-2 NB 1
B1.30 VE-F 218 6.2 RPV 1 16 GE.BN-3 1
1 1
2 RI-06 127 To 248 DAZ...
.VCB-BC5-3 NB 1
81.30 VE-F 218 6.2 RPV 1 16 GE.BN-3 1
1 1
3 RI-06 248 TO 7 DAZ...
3 ***
i VCB-BC6-1 NB 1
B1.40 THD-F 218 3.2 RPV 1 15 GE.BA-3,BA-4 16 1 1
1 1
0 TO 120 DAZ...
VCB-BC6-2 NB 1
81.40 THD-F 218 3.2 -
1 2
120 70 240 DAZ...
VCB-BC6-3 NB 1
81.40 THD-F 218 3.2 RPV 1 15 GE.BA-3,BA-4 16 1 1
1 3
240 TO 360 DAZ...
3 ***
gy 47 r
28 DECEMBER 1995 PAGE 3 m-
r.JB-2500-1 CAT:
B-D COOPER NUCLEAR STATION NUCLEAR BOILER INSERVICE INSPECTION PROGRAM REY: 4.1 SECOND INTERVAL PI PE.................. CNT. I TEM.Wo. CF I G... S I ZE.. TKNS..... MAT... W81. CAL... I S0................. PT.. UTO.. UT45.... UT60.... PER.... RELREQ REMARKS..................
CV!R-BD-NIA 1
B3.100 NIR 28 RPV 1 22,24 CE.232-231 3
1 CA - COMPOUND ANGLE NVIR-BD-N1B 1
B3.100 MIR 28 RPV 1 16 CE.232-231 3
3 CA - COMPOUND ANGLE NVIR-BD-N2A 1
B3.100 NIR 12 RPV 1 16 CE.232-231 3
3 3
CA - COMPOUND ANGLE CVIR-BD-N2B 1
83.100 MIR 12 RPV 1 16 CE.232-231 3
3 3
CA - COMPOUND ANGLE NUIR-BD-N2C 1
B3.100 NIR 12 RPV 1 22,25 CE.232-231 3
1 CA - COMPOUND ANGLE NVIR-BD-N2D 1
83.100 NIR 12 RPV 1 16 CE.232-231 3
3 3
CA - COMPOUND ANGLE CVIR-BD-N2E 1
B3.100 N!R 12 RPV 1 22,25 CE.232-231 3
2 CA - COMPOUND ANGLE RPV 1 22,25 CE.232-231 3
1 CA - COMPOUND ANGLE CVIR-BD-N2F 1
B3.100 NIR 12 NVIR-BD-02G 1
B3.100 MIR 12 RPV 1 22,25 CE.232-231 3
1 CA - COMPOUND ANGLE NVIR-BD-N2H 1
B3.100 NIR 12 RPV 1 22,25 CE.232-231 3
1 CA - COMPOUND ANGLE NVIR-BD-N2J 1
B3.100 NIR 12 RPV 1 22,25 CE.232-231 3
2 CA - COMPOUND ANGLE CVIR-BD-N2K 1
B3.100 NIR 12 RPV 1 22,25 CE.232-231 3
2 CA - COMPOUND ANGLE NVIR-BD-N3A 1
B3.100 NIR 24 RPV 1 22,26 GE.731E611 3
1 CA - COMPOUND ANGLE NVIR-BD-N38 1
B3.100 N!R 24 RPV 1 22,26 GE.731E611 3
2 CA - COMPOLWD ANGLE NVIR-BD-N3C 1
83.100 NIR 24 RPV 1 16 GE.731E611 3
3 CA - COMPOUND ANGLE NVIR-BD-N3D 1
B3.100 NIR 24 RPV 1 22,26 GE.731E611 3
2 CA - COMPOUND ANGLE NVIR-BD-N4A 1
B3.100 NIR 12 RPV 1 16 CE.232-231 14 3,31 3,31 2
NUREG 0619... UT IN LIEU OF PT F91... CA-COMPOUND ANGLE...
NVIQ-BD-N48 1
83.100 NIR 12 RPV 1 16 CE.232-231 14 3,31 3,31 1
NUREG 0619... UT IN LIEU OF PT F91... CA-COMPOUND ANGLE...
NVIR-BD-04C 1
B3.100 NIR 12 RPV 1 16 CE.232-231 14 3,31 3,31 3
NUREG 0619... UT IN LIEU OF PT F91... CA-COMPOUND ANGLE...
RPV 1 16 CE.232-231 14 3,31 3,31 1
NUREG 0619... UT IN LIEU NVIR-BD-N40 1
B3.100 NIR 12 OF PT F91... CA-COMPOUND ANGLE...
CVIR-BD-NSA 1
B3.100 NIR 10 RPV 1 22,28 CE.232-231 3
2 CA - COMPOUND ANGLE NVIR-BD-NSB 1
B3.100 NIR 10 RPV 1 16 CE.232-231 3
3 CA - COMPOUND ANGLE 28 DECEMBER 1995 PAGE 1
1 IWB-2500-1 CAT:
B-D COOPER NUCLEAR STATION NUCLEAR BOILER INSERVI E INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL PI PE.................. CNT. I TEM.NO. CFI G... SIZE.. TKNS..... MAT... WB1. CAL... I S0................. PT.. UTO.. UT45.... UT60.... PER.... RELREQ REMARKS..................
NVIR-BD-N6A 1
B3.100 NIR 6
RPV 1 N/A E.232-244 14 13 3
RI-03 (RI-03 RELIEF REQUEST)
N6A NO2, RPV TP.MD 0 DAZ, ALSO REF: GE DWG BA-3 AND BA-4 NVIR-BD-N6B 1
B3.100 NIR 6
RI-03 (RI-03 RELIEF REOUEST)
N6B N0Z, RPV TP.HD 180 DAZ NVIR-BD-07 1
B3.100 N!R 6
RI-03 (RI-03 RELIEF REQUEST) N7 N02, RPV TP. MD, CENTER OF TP.HD NVIR-BD-NBA 1
83.100 N!R 5
CA - COMPOUND ANGLE (LOC.
DW. 928' 105 DAZ)
CA - COMPOUND ANGLE ( NSB NVIR-BD-N88 1
B3.100 NIR 5
N0Z ) LOC. DW 928' 285 DAZ, ALSO REF: GE DWG BA-2 AND BN-3 NVIR-BD-N9 1
B3.100 NIR 5
( M9 N0Z ) ALSO REF: GE DWG BA-2 AND BN-3, LOC DW 962' 146 DA2, EXAM LIMITED DUE TO PROKIMITY RPV INSULATION SUPPORT RING 28 ***
NVE-BD-N1A 1
B3.90 N-VE 28 7.2 RPV 1 16 CE.232-231 1
1 1
1 RI-21 NVE-BD-N1B 1
B3.90 N-VE 28 7.2 RPV 1 16 CE.232-231 1
1 1
3 RI-21 NVE-BD-Q?A 1
B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1
1 1
3 RI-21 GVE-BD-C2B 1
83.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1
1 1
3 RI-21 CVE-BD-N2C 1
83.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1
1 1
1 RI-21 28 DECEMBER 1995 PAGE 2
IWB-2500-1 CAT:
B-D COOPER NUCLEAR STATION NUCLEAR BOILER INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL P ! PE.................. CNT. I TEM.NO. CF I G... SIZE.. TKNS..... MAT... W81. CAL... I S0................. PT.. UT0.. UT45.... UT60.... PER.... RELREQ REMARKS..................
NVE-BD-N2D 1
B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1
1 1
3 RI-21 CVE-BD-C2E 1
B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1
1 1
2 RI-21 CVE-BD-G2F 1
B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1
1 1
1 RI-21 CVE-BD-N2G 1
B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1
1 1
1 RI-21 NVE-BD-N2H 1
B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1
1 1
1 RI-21 NVE-BD-N2J 1
B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1
1 1
2 RI-21 NVE-BD-N2K 1
B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1
1 1
2 RI-21 OVE-BD-N3A 1
B3.90 N-VE 24 6.2 RPV 1 16 GE.731E611 1
1 1
1 RI-21 NVE-BD-N38 1
B3.90 N-VE 12 6.2 1PV 1 16 GE.731E611 1
1 1
2 RI-21 NVE-BD-N3C 1
B3.90 N-VE 24 6.2 EPV 1 16 GE.731E611 1
1 1
3 RI-21 NVE-BD-N3D 1
B3.90 N-VE 24 6.2 RW 1 16 GE.731E611 1
1 1
2 RI-21 NVE-BD-N4A 1
B3.90 N-VE 12 6.2 RPV 1 16 CE.232-231 30 30 30 2
RI-21 NVE-BD-N48 1
83.90 N-VE 12 6.2 RPV 1 16 CE.232-231 30 30 30 1
RI-21 NVE-BD-N4C 1
83.90 N-VE 12 6.2 RPV 1 16 CE.232-231 30 30 30 3
RI-21 NVE-BD-N40 1
83.90 N-VE 12 6.2 RPV 1 16 CE.232-231 30 30 30 1
RI-21 NVE-BD-N5A 1
83.90 N-VE 10 6.2 RPV 1 16 CE.232-231 1
1 1
2 RI-21 ( NSA NOZ ) LOC. DW. %2' 90 DAZ NVE-BD-C5B 1
B3.90 N-VE 10 6.2 RPV 1 16 CE.232-231 1
1 1
3 RI-21 ( NSB N0Z ) LOC. DU. 962*
270 DAZ NVE-BD-06A 1
83.90 N-VE 6
1 1
3 RI-21 ( N6A N0Z ) RPV TP.HD 0 DAZ, ALSO REF: GE DWG BA-3 AND BA-4 CVE-BD-N6B 1
B3.90 N-VE 6
1 1
2 RI-21 ( N6B N0Z ) RPV TP.HD 180 DAZ NVE-BD-N7 1
B3.90 N-VE 6
1 1
1 RI-21 ( N7 N0Z ) RPV TP.HD, CENTER OF TP.HD NVE-BD-C8A 1
83.90 N-VE 5
1 1
2 RI-21 ( M8A N0Z ) LOC. DW. 928' 105 DAZ CVE-BD-C88 1
83.90 N-VE 5
1 1
3 RI-21 ( N88 N0Z ) LOC. DU. 928' 285 DAZ, ALSO REF: GE DWG 28 DECEMBER 1995 PAGE 3
r IWB-2500-1 CAT:
B-D COOPER NUCLEAR STATION
-NUCLEAR BOILER INSERVICE INSPECTION PROGRAM REY: 4.1 SECOND INTERVAL PI PE.................. CNT. ITEM.No. CF IG... SIZE.. TKNS..... MAT... WB1. CAL... IS0................. PT.. UTO.. UT45.... UT60.... PER.... RELREO REMARKS..................
BA-2 AND BN-3 CVE-BD-N9 1
83.90 N-VE 5
1 1
3 RI-21 ( M9 N0Z ) ALSO REF: GE DWG BA-2 AND BN-3, LOC DW t
9628 146 DAZ, EXAM i
LIMITED DUE TO PROKIMITY t
OF RPV INSULATION SUPPORT RING AND THE M4A N0ZZLE 28 ***
f 56 l
l i
I f
i n
28 DECEMBER 1995 PAGE 4
IWB-2500-1 CAT:
B-F COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL PI PE.................. SYSTEM.. CNT. I TEM.No. CF I G... S IZE.. TKNS..... MAT... W81. CAL.. 150................. PT.. UTO.. UT45.... RELREQ PER.... REMARKS..................
CSA-BF-1*
CS-A 1
B5.10 SE-N 13.44 1.06 P20/RP 51/61/121 CNS-CS-4 7
28,29 3
- FORMER PIPE WHIP EXAM *
( NSA NOZ 90 DAZ ) GL 88-01 (PSI,UTO,F84) ALSO REF: JELCO DWG 2502-1...
CSB-BF-1*
CS-B 1
B5.10 SE-N 13.44 1.06 P20/RP 61/51 CNS-CS-3 7
28,29 1
- FORMER PIPE WHIP EXAM, NSB (ALSO REF JELCO DWG 2502-1) (PSI,F84)
JPA-BF-1 JPI-A 1
B5.10 SE-N 6
0.828 P20/RP 107/109 CE.232-241 7
28 2
( JPI-A ) GL 88-01 (PSI,UTO,F84,EDS # N-433)
ALSO REF CBEI DWG 20.
REFER 70 SIL 455 REV. 1 FOR ADDITIONAL COVERAGE REco mENDATIONS; DUE TO INCONEL 182 FILLER MATERIAL AND BUTTERING JPB-BF-1 JPI-B 1
85.10 SE-N 6
0.828 P20/RP 107/109 CE.232-241 7
28 3
( NSB N0Z ) GL 88-01 (PSI,UT0,F84,EDS # N-433)
ALSO REF CB&I DWG 20.
REFER TO SIL 455 REV. 1 FOR ADDITIONAL COVERAGE RECOMMENDATIONS; DUE To INCONEL 182 FILLER MATERIAL AND BUTTERING ICA-BF-1 NB 1
B5.10 N-C 5.25 160 P18/RP 20 CE.232-242 7
28,29 3
( N9 N02 ) CL 88-01, CAP MAT. IS NI.GR.FE AND INCONEL 182 WITH INCONEL 82 WELD FILLER METAL...
RAS-BF-1 RR-A 1
85.10 N-SE 29 1.973 P20/RP 59/57 CNS-RR-37 7
28,29 1
N1A RRF-BF-1 RR-A 1
B5.10 SE-N 14 1.187 P20/RP 52/60/121 CNS-RR-37 7
28,29 3
( N2F N0Z 210 DAZ )
RRG-BF-1 RR-A 1
B5.10 SE-N 14 1.187 P20/RP 52/60/121 CNS-RR-37 7
28,29 3
( N2G N0Z 240 DAZ )
28 DECEMBER 1995 PAGE 1
- WB-2500-1 CAT
- B-F COOPER NUCLEAR STATION INSERVICE INSPECTICN PROGRAM REV: 4.1 SECOND INTERVAL
'I PE.................. SYSTEM.. CNT. I TEM.NO. CF I G... SIZE.. TKNS..... MAT... W81. CAL.. 1S0................. PT.. UTO.. UT45.... RELREQ PER.... REMARKS..................
l tRH-BF-9 RR-A 1
B5.10 SE-N 14 1.187 P20/RP 60/52 CNS-RR-37 7
28,29 1
N2R tRJ-BF-1 RR-A 1
85.10 SE-N 14 1.187 P20/RP 60/52 CNS-RR-37 7
28,29 2
N2J IRK-BF-1 RR-A 1
B5.10 SE-N 14 1.187 P20/RP 60/52 CNS-RR-37 7
28,29 2
N2K TBS-BF-1 RR-B 1
B5.10 N-SE 29 1.973 P20/RP 57/59 CNS-RR-38 7
28,29 2
N1B i
tRQ-BF-1 RR-B 1
B5.10 SE-N 14 1.187 P20/RP 60/52/121 CNS-RR-38 7
28,29 3
N2A tRB BF-1 RR-B 1
B5.10 SE-1 14 1.187 P20/RP 60/52/121 CNS-RR-38 7
28,29 3
N2B tRC-BF-9 RR-B 1
B5.10 SE-N 14 1.187 P20/RP 60/52 CNS-RR-38 7
28,29 1
N2C tRD-BF-1 RR-B 1
B5.10 SE-N 14 1.187 P20/RP 60/52/121 CNS-RR-38 7
28,29 3
N2D tRE-BF-1 RR-B 1
B5.10 SE-N 14 1.187 P20/RP 60/52 CNS-RR-38 7
28,29 1
N2E 17 ***
CSA-BF-4A CS-A 1
B5.130 P-E 10 0.631 P20/P2 4/49 CNS-CS-4 7
6,26 2
ALSO REF: JELCO DWG 2502-1...
CSB-BF-4A CS-B 1
B5.130 P-E 10 0.631 P20/P2 4/49 CNS-CS-3 7
6,26 1
ALSO REF JELCO DWG 2502-1 RAD-BF-7 RR-A 1
85.130 P-P 24 1.218 P20/P3 55/106 CNS-RR-37 7
6,26 3
FROM RHR "A"... INCLUDE'S INTERSECTION OF ADJ. LS RAD-RJ-40A (C.S. PIPE SIDE)
RAS-BF-12 RR-A 1
B5.130 P-P 20 1.031 P20/P3 53/103 CNS-RR-37 7
6,26 1
(To RHR) INCLUDE'S INTERSECTION OF ADJ. LS RHA-BJ-3A (C.S. PIPE SIDE)...
RBD-BF-7 RR-B 1
B5.130 P-P 24 1.218 P20/P3 55/106 CNS-RR-38 7
6,26 2
FROM RMR "B"... INCLUDE'S INTERSECTION OF ADJ. LS RBD-BJ-40A (C.S. PIPE SIDE) 5 ***
I 28 DECEMBER 1995 PAGE 2 g
W8-2500-1 CAT: B-F COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL I PE.................. SYSTEM.. CNT. I TEM.NO. CFIG... SIZE.. TKNS..... MAT... W81. CAL.. 1 S0................. PT.. UTO.. UT45.... RELREQ PER.... REMARKS..................
VD-8F-14 N8D 1
55.140 P-P 2
.218.
CS-SS N/A X2512-200 7
RI-20 3 REMOVE SUPPORT RRH-20 To ACCESS WELD FOR EXAMINATION 1 ***
23 4
3 i
I 28 DECEMBER 1995 PAGE 3 m
s
k IWB-2500-1 CAT:
B-J COOPER NUCLEAR STATION MAIN STEAM SYSTEM INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL P I PE.................. SYSTEM.. CNT. ITEM.NO. CF IG... SI2E.. TKNS..... MAT... W81. CAL.. 150................. PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
PSA BJ-9 MS 1
99.11 WOL-E 10
.719 F1 77 2506-1 16 6
2 PSA-BJ-11 MS 1
89.11 P-P 10"
. 71 9" P1 78 2506-1 7
16 6 6
PSA-BJ-12 MS 1
89.11 P-E 10"
.719" Pt 78 2506-1 7
16 6 6
PSA-BJ-15 MS 1
89.11 E-VA 10"
.719" F1 77 2506-1 7
16 6 6
PSA-BJ-S6 MS 1
B9.11 VA-P 10"
.719" P1 78 2506-1 7
16 6 6
'PSA-BJ-17*
MS 1
89.11 P-E 10
.719 P1 78 2506-1 7
16 6
3
- FORMER PIPE WHIP EXAM PSA-BJ-S8*
MS 1
B9.11 E-P 10
'.719 P1 78 2506-1 7
16 6
3
- FORMER PIPE WHIP EXAM PSA-BJ-2 MS 1
89.11 E-P 10
.719 P1 78 2506-1 16 6
2 PSA-BJ-20 MS 1
89.11 P-E 10"
.719" P1 78 2506-1 7
16 6 6
PSA-BJ-21 MS 1
89.11 E-P 10"
.719" F1 2506-1 7
16 6 6
PSA-BJ-22 MS 1
89.11 P-FM 10"
.719" F1 77 2506-1 7
16 6 6
INACCESSIBLE, INSIDE CONTAINMENT PENETRATION X-11...
PSQ-BJ-24 MS 1
B9.11 FM-VA 10"
.719" F1 77 2506-1 7
16 6 6
PSA-BJ-3 MS 1
89.11 P-E 10"
.719 P1 78 2506-1 7
16 6 6
PSA-BJ-4 MS 1
B9.11 E-P 10"
.719 P1 78 2506-1 7
16 6 6
PSA-BJ-8 MS 1
89.11 P-E 10"
.719" P1 78 2506-1 7
16 6 6
PSA-BJ-9 MS 1
89.11 E-P 10"
.719" P1 78 2506-1 7
16 6 6
MSA-BJ-S*
MS-A 1
89.11 SE-P 24 1.219 P3 106 GE731E611-4 16 6
2
MSA-BJ-10 MS-A 1
89.11 E-E 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE *S INTERSECTION OF ADJ. LS MSA-BJ-7A, MSA-BJ-10A(IA), AND MSA-BJ-10B(OA)
MSA-BJ-111 MS-A 1
B9.11 N-SE 24 1.593 P3 115 GE731E611-4 16 6
2 MSA-BJ-12 MS-A 1
89.11 E-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION Of ADJ. LS MSA-BJ-10A(IA),
28 DECEMBER 1995 PAGE 1
IWB-2500-1 CAT:
B-J COOPER NUCLEAR STATION MAIN STEAM SYSTEM INSERVICE INSPECTION PROGRAM REV: 4.1 SEco m INTERVAL P I PE.................. SYSTEM.. CNT. I TEM.NO. CF I G... SI 2E.. TKNS..... MAT... W81. CAL.. 150................. PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
7 MSA-BJ-10B(OA), AND MSA-BJ-12A MSA-BJ-15 MS-A 1
89.11 SWL-P 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSA-BJ-16 MS-A 1
89.11 P-F 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSA-BJ-2 MS-A 1
99.11 P-E 24 1.210 P3 106 GE731E611-4 16 6
2 INCLUDE'S INTERSECTION OF ADJ. LS MSA-BJ-1A, i'
MSA-BJ-2A(IA), AND MSA-BJ-28(OA). TOTAL LENGTH OF LS MAS-BJ-1A IS 6.5" II MSA-BJ-20 MS-A 1
89.11 SWL-P 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSA-BJ-22 MS-A 1
89.11 P-F 6"
.719" P1 106 GE731E611-4 7
16 6 6
MSA-BJ-23 MS-A 1
89.11 P-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSA-BJ-12A AND MSA-BJ-23A MSA-BJ-25 MS-A 1
89.11 SWL-P 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSA-BJ-26 MS-A 1
89.11 P-F 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSA-BJ-29 MS-A 1
89.11 P-E 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLtlDE'S INTERSECTION OF ADJ. LS MSA-BJ-23A, MSA-BJ-29ACIA), AND MSA-BJ-29B(OA)
QSA-BJ-3 MS-A 1
B9.11 E-P 24 1.219 P3 106 GE731E611-4 16 6
2 INCLUDE *S INTERSECTION OF ADJ. LS MSA-BJ-2A(IA),
MSA-BJ-28(OA), A 2 MSA-EJ-3A MSA-BJ-30 MS-A 1
89.11 E-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSA-BJ-29ACIA)
AND MSA-BJ-29B(04)
MSA-BJ-35*
MS-A 1
B9.11 P-E 24 1.219 P3 106 GE731E611-4 7
16 6
1
- FORMER PIPE WHIP EXAM... INCLUDE *S 28 DECEMBER 1995 PAGE 2
IWB-2500-1 CAT: B-J COOPER NUCLEAR STATION MAIN STEAM SYSTEM INSERVICE INSPECTION PROGRA*1 REV: 4.1 SECOND INTERVAL PI PE.................. SYSTEM.. CNT. I TEM.NO. CF IG... SIZE.. TKNS..... MAT... W81. CAL.. 150................. PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
l INTERSEC"% OF ADJ. LS MSA-BJ-35A(IA) AND MSA-BJ-35B(OA)...
MSM-167, MA-3...
MSA-BJ-36*
MS-A 1
89.11 E-P 24 1.219 P3 106 GE731E611-4 7
16 6
1
MSA-BJ-35B(OA)...
MSH-167, HA-3...
MSA-BJ-38 MS-A 1
89.11 P-VA 24" 1.219" P3 106 GE731E611-4 7
16 6 6
MSA-BJ-4 MS-A 1
89.11 P-P 24 1.219 P3 106 CE731E611-4 16 6
2 INCLUDE'S INTERSECTION OF ADJ. LS MSA-BJ-3A AND MSA-BJ-4A I
MSA-BJ-42 MS-A 1
89.11 VA-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
MSA-BJ-43 MS-A 1
B9.11 P-FM 24" 1.219" P1 106 GE731E611-4 7
16 6 6
INACCESSIBLE, INSIDE CONTAINMENT PENETRATION X-7A...
l MSA-BJ-46 MS-A 1
89.11 FM-P 24 1.219 P1 106 GE731E611-4 7
16 6 6
e 4
MSA-BJ-48 MS-A 1
B9.11 P-VA 24" 1.219" P1 106 GE731E611-4 7
16 6 6
MSA-BJ-5 MS-A 1
B9.11 P-P 24 1.219 P3 106 GE731E611-4 16 6
2 INCLUDE *S INTERSECTION OF ADJ. LS MSA-BJ-4A AND MSA-BJ-5A MSA-BJ-7 MS-A 1
89.11 P-E 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE *S INTERSECTION OF ADJ. LS MSA-BJ-5A AND MSA-BJ-7A MSB-BJ-1*
MS-B 1
89.11 SE-P 24 1.219 P3 106 GE731E611-4 7
16 6
3
- FORMER PIPE WHIP EXAM... INCLLDE'S INTERSECTION OF ADJ. LS MSB-BJ-1A...
28 DECEMBER 1995 PAGE 3
IWB-2500-1 CAT:
B-J COOPER NUCLEAR STATION MAIN STEAM SYSTEM INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL P I PE.................. SYSTEM.. CNT. I TEM.MO. CFIG... S IZE.. TKNS..... MAT... W81. CAL.. 1S0................. PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
I MSB-BJ-10 MS-B 1
89.11 P-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSB-BJ-8A(IA),
MSB-RJ-8B(04), AND MSB-BJ-10A
[
MSB-BJ-111 MS-B 1
89.11 N-SE 24 1.593 P3 115 GE731E611-4 7
16 6 6
3 i
MSB-BJ-14 MS-B 1
89.11 SWL-P 6"
.719" P1 3
GE731E611-4 7
16 6 6
l MSB-BJ-15 MS-B 1
89.11 P-F 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSB-BJ-19 MS-B 1
89.11 SWL-P 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSB-BJ-2 MS-B 1
89.11 P-E 24 1.219 P3 106 GE731E611-4 7
16 6
3 INCLtDE'S INTERSECTION OF ADJ. LS MSB-BJ-2A (IA),
MS8-BJ-28 (OA), AND MSB-BJ-1A MSB-BJ-20 MS-B 1
89.11 P-F 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSB-BJ-22 MS-B 1
89.11 P-E 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSB-BJ-10A, MSB-BJ-22A(IA), AND MSB-BJ-22B(OA)
MSB-BJ-23 MS-B 1
89.11 E-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSB-BJ-22A(IA)
AND MSB-BJ-22B(OA)
MSB-BJ-2G*
MS-B 1
B9.11 P-E 24 1.219 P3 106 GE731E611-4 7
16 6
1
- FORMER PIPE WHIP EXAM... INCLtDE'S INTERSECTION OF ADJ. LS MSB-BJ-28A(IA) AND MSB-BJ-28B(04) NB-3, MSH-168 MSB-BJ-29*
MS-B 1
B9.11 E-E 24 1.219 P3 106 GE731E611-4 7
16 6
1
- FORMER PIPE WHIP EXAM... INCLLDE'S INTERSECTION OF ADJ. LS MSB-BJ-28ACIA),
28 DECEMBER 1995 PAGE 4
IWB-2500-1 CAT: B-J COOPER NUCLEAR STATION MAIN STEAM SYSTEM INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL PI PE.................. SYSTEM.. CNT. ITEM.No. CF IG... SIZE.. TKNS..... MAT... W61. CAL... I SG................ PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
MS8-BJ-288t0A),
MS8-8J-29ACIA), AND MS8-BJ-29B(CA)
NS-3,MSH-168 MSB-BJ-3 MS-B 1
89.11 E-P 24 1.219 P3 106 GE731E611-4 7
16 6
3 INCLUDE'S INTERSECTION OF ADJ. *; a:SB.gJ.2A (IA),
MSB-8J-28 (OA), AND b48-BJ-3A MSB-BJ-30 MS-B 1
99.11 E-E 24" 1.219" P3 106 GE731E611-4 7
16 6 6
imCLUDE'S INTERSECTION OF j
ADJ. MSB-8J-29A(IA),
MS8-BJ-29B(OA),
MS8-BJ-30A(IA), AND MS8-BJ-30B(OA)
MSB-BJ-31 MS-B 1
89.11 E-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLLDE'S INTERSECTION OF ADJ. LS MSB-sJ-30A(IA),
MS8-8J-30B(OA),
MSB-BJ-31A(IA), AND MS8-BJ-318(OA)
MSB-BJ-34 MS-B 1
89.11 P-VA 24" 1.219" P3 106 GE731E611-4 7
16 6 6
MSB-BJ-38 MS-B 1
89.11 VA-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
MSB-BJ-39 MS-B 1
89.11 P-FM 24" 1.219" P1 106 GE731E611-4 7
16 6 6
INACCESSIBLE, INSIDE CONTAINMENT PENETRATION X-7B...
MSB-BJ-4 MS-B 1
89.11 P-P 24 1.219 P3 106 GE731E611-4 7
16 6
INCLUDE *S INTERSECTION OF ADJ. LS MS8-8J-3A AND MS8-BJ-4A MSB-BJ-42 MS-B 1
89.11 FH-P 24 1.219 Pt 106 GE731E611-4 7
16 6 6
3 2
MSB-BJ-43 MS-B 1
89.11 P-P 24" 1.219" P1 106 GE731E611-4 7
16 6 6
MSB-BJ-44 MS-B 1
89.11 P-VA 24" 1.219" P1 106 GE731E611-4 7
16 6 6
MSB-BJ-6 MS-B 1
89.11 P-P 24 1.219 P3 106 GE731E611-4 7
16 6 6
INCLtDE'S INTERSECTION OF 28 DECEMBER 1995 PAGE 5
- - - - ~
IWB-2500-1 CAT: B-J COOPER NUCLEAR STATION MAIM STEAM SYSTEM INSERVICE INSPECTION PROGRAM REY: 4.1 SECOND INTERVAL PI PE.................. SYSTEM.. CNT. ITEM.NO. CFI G... S IZE.. TKNS..... MAT... W81. CAL... I S0................. PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
ADJ. LS MSB-BJ-6A, MSB-BJ-8A(IA), AND MS8-BJ-8B(04) 5SB-BJ-8 MS-B 1
B9.11 P-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSB-BJ-6A, MSB-BJ-8A(IA), AND MSB-BJ-8B(OA)
MSC-BJ-1*
MS-C 1
89.11 SE-P 24 1.219 P3 106 GE731E611-4 7
16 6
3
- FORMER PIPE WHIP EXAM... INCLUDE'S INTERSECTION OF ADJ. LS MSC-BJ-1A MSC-BJ-11 MS-C 1
89.11 P-E 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSC-BJ-7A, MSC-BJ-11A(IA), AND MSC-BJ-11B(OA)
MSC-BJ-111 MS-C 1
B9.11 N-SE 24 1.593 P3 115 GE731E611-4 16 6 6
3 MSC-BJ-13 MS-C 1
89.11 E-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLLDE'S INTERSECTION OF ADJ. LS MSC-BJ-11ACIA),
MSC-BJ-11B(OA), AND MSC-BJ-13A MSC-BJ-17 MS-C 1
89.11 SWL-P 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSC-BJ-18 MS-C 1
89.11 P-F 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSC-BJ-2 MS-C 1
89.11 P-E 24 1.219 P3 106 GE731E611-4 7
16 6
3 INCLUDE'S INTERSECTION OF ADJ. LS MSC-BJ-1A, MSC-BJ-2A (IA), AND MSC-BJ-2B (04)
MSC-BJ-22 MS-C 1
89.11 SWL-P 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSC-BJ-23 MS-C 1
B9.11 P-F 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSC-BJ-26 MS-C 1
89.11 P-E 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF LS MSC-BJ-13A, 23 DECEMBER 1995 PAGE 6
IWB-2500-1 CAT:
B-J COOPER NUCLEAR STATION MAIN STEAM SYSTEM INSERYiCE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL PI PE.................. SYSTEM.. CNT. ITEM.No. CF I G... SIZE.. TKNS..... MAT... W81. CAL.. 1 S0................. PT., MT.. UT0.. UT45.... PER.... REMARKS..................
MSC-BJ-26A(IA), AND MSC-BJ.MB(OA)
MSC-BJ-27 MS-C 1
89.11 E-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE *S INTERSECTION OF ADJ. LS risC-BJ-26A(IA)
AND MSC-BJ-26B(OA)
MSC-BJ-3*
MS-C 1
B9.11 E-P 24 1.219 P3 106 CE731E611-4 7
16 6
3
- FCRMER PIPE WHIP EXAM... INCLUDE'S INTERSECTION OF ADJ. LS MSC-BJ-2A (IA), MSC-BJ-28 (OA), AND MSC-BJ-3A MSC-BJ-32 MS-C 1
B9.11 P-E 24 1.219 P3 106 CE731E611-4 7
16 6
1 INCLUDE'S INTERSECTION OF ADJ. LS MSC-BJ-32A(IA)
AND MSC-BJ-32B(OA),
HC-3,MSH-169 FTSC-BJ-33 MS-C 1
89.11 E-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSC-BJ-32A(IA),
MSC-BJ-32B(OA), AND MSC-BJ-33 F.SC-BJ-34 MS-C 1
89.11 P-E 24 1.219 P3 106 GE731E611-4 7
16 6 6
INCLUDE *S INTERSECTION OF ADJ. LS MSC-BJ-33A,MSC-BJ-34A(IA)
,AND MSC-BJ-34B(OA)
MSC-BJ-35*
MS-C 1
B9.11 E-P 24 1.219 P3 106 GE731E611-4 7
16 6
1
- FORMER PIPE WHIP EXAM... INCLUDE'S INTERSECTION OF ADJ. Lts MSC-BJ-34A(IA),MSC-BJ-348 (OA),AND MSC-BJ-35A)
MC-3,MSH-169 MSC-BJ-38 MS-C 1
89.11 P-VA 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE 8S INTERSECTION OF ADJ. LS MSC-BJ-3SA...
28 DECEMBER 1995 PAGE 7
i l
IWB-2500-1 CAT: B-J COOPER NUCLEAR STATION MAI:3 STEAM SYSTEM INSERVICE INSPECTION l'RCGRAM REV: 4.1 SECOND INTERVAL P I PE.................. SYSTEM.. CNT. ITEM.NO. CF IG... SI ZE.. TKNS..... MAT... W81. CAL... I S0................. PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
MSC-BJ-42 MS-C B9.11 VA-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
MSC-BJ-43 MS-C 1
89.11 P-FM 24 1.219 P1 106 GE731E611-4 7
16 6 6
IN*.::;25sIBLE, INSIDE CONTAINMENT PENETRATION X-7C...
MSC-BJ-46 MS-C 1
89.11 FN-P 24" 1.219" Pt 106 GE731E611-4 7
16 6 6
MSC-BJ-47 MS-C 1
89.11 P-P 24 1.219 P1 106 GE731E611-4 7
16 6 6
MSC-BJ-48 MS-C 1
89.11 P-VA 24" 1.219" P1 106 GE731E611-4 7
16 6 6
89.11 P-P 24 1.219 F3 106 GE731E611-4 7
16 6 6
INCLUDE *S INTERSECTION OF ADJ. LS MSC-BJ-3A AND e
MSC-BJ-SA MSC-BJ-7 MS-C 1
B9.11 P-P 24 1.219 P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSC-BJ-5A AND i
MSC-BJ-7A MSD-BJ-1*
MS-D 1
B9.11 SE-P 24 1.219 P3 106 GE731E611-4 16 6
2
MSD-BJ-10 PG-D 1
B9.11 P-E 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF LS MSD-BJ-7A, MSD-BJ-10A(IA), AND l
MSD-BJ-10B(OA)
MSD-BJ-111 MS-D 1
B9.11 N-SE 24 1.593 P3 115 GE731E611-4 7
16 6 6
3 MSD-BJ-12 MS-D 1
B9.11 E-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSD-BJ-10A(IA),
f MSD-BJ-10B(OA), AND MSD-BJ-12A MSD-BJ-15 MS-D 1
89.11 SWL-P 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSD-BJ-16 MS-D 1
B9.11 PF 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSD-BJ-2 MS-D 1
89.11 P-E 24 1.219 P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF 28 DECEMBER 1995 PAGE 8
IWB-2500-1 CAT:
8-J COOPER NUCLEAR STATION MAIO STEAM SYSTEM INSERVICE INSPECTION PROGRAM REY: 4.1 SECOND INTERVAL PI PE.................. SYSTEM.. CNT. ITEM.NO. CF IG... SI ZE.. TKNS..... MAT... WB1. CAL.. 150................. PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
ADJ. LS MSD-BJ-1A, MSD-BJ-2A(IA), AND MSD-8J-28(OA)
MSD-8J-2D MS-D 1
89.11 SWL-P 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSD-8J-21 MS-D i
89.11 P-F 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSD-8J-23 MS-D 1
89.11 P-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLLEE'S INTERSECTION OF ADJ. LS MSD-8J-12A AND MSD-8J-23A MSD-8J-23 MS-D 1
89.11 SWL-P 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSD-8J-26 MS-D 1
89.11 P-F 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSD-8J-29 MS-D 1
89.11 SWL-P 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSD-8J-3 MS-D 1
89.11 E-P 24 1.219 P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSD-BJ-2A(IA),
MSD-8J-28(04), AND MSD-8J-3A MSD-8J-30 MS-D 1
89.11 P-F 6"
.719" P1 3
GE731E611-4 7
16 6 6
MSD-8J-33 MS-D 1
89.11 P-E 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSD-8J-23A, MSD-BJ-33A(IA), AND MSD-8J-338(OA)
MSD-8J-34 MS-D 1
89.11 E-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSD-8J-33A(IA)
AND MSD-BJ-338(OA)
MSD-8J-39*
MS-D 1
89.11 P-E 24 1.219 P3 106 GE731E611-4 7
16 6
1
MSD-8J-6 MS-D 1
89.11 P-P 24" 1.219 P3 106 GE731E611-4 7
16 6 6
INCLUDE'S INTERSECTION OF ADJ. LS MSD-8J-3A AND 28 DECEMBER 1995 PAGE 9
IWB-2500-1 CAT:
B-J COOPER NUCLEAR STATION MAIN STEAM SYSTEM INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL P I PE.................. SYSTEM.. CNT. ITEM.NO. CF I G... SIZE.. TKNS..... MAT... W81. CAL.. 150................. PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
MSD-BJ-4A MSD-BJ-40*
MS-D 1
99.11 E-P 24 1.219 P3 106 GE731E611-4 7
16 6
1
- FORMER PIPE WHIP EXAM... INCL *rE'S I
INTERSECTION OF A)J. LS MSD-BJ-39A(IA) M MSD-BJ-39B(OA)... HD-2, MSH-170...
MSD-BJ-41 MS-D 1
89.11 P-VA 24" 1.219" P3 106 GE731E611-4 7
16 6 6
MSD-BJ-46 MS-D 1
B9.11 VA-P 24" 1.219" P3 106 GE731E611-4 7
16 6 6
l MSD-BJ-47 MS-D 1
B9.11 P-FH 24" 1.219" P1 106 GE731E611-4 7
16 6 6
INACCESSIBLE, INSIDE OF CONTAINMENT PEKE 1xAT L X-7D...
MSD-BJ-5 MS-D 1
89.11 P-P 24 1.219 P3 106 GE731E611-4 7
16 6 6
INCLUDE *S INTERSECTION OF ADJ. LS MSD-BJ-4A AND MSD-BJ-5A MSD-BJ-50 MS-D 1
89.11 FH-P 24 1.219 P1 106 GE731E611-4 7
16 6 6
3 t
CSD-BJ-52 MS-D 1
B9.11 P-VA 24" 1.219" P1 106 GE731E611-4 7
16 6 6
MSD-BJ-7 MS-D 1
89.11 P-P 24 1.219 P3 106 GE731E611-4 7
16 6 6
INCLLDE'S INTERSECTION OF ADJ. LS MSD-BJ-5A AND MSD-BJ-7A 116 ***
RSA-BJ-1 MS 1
89.21 WDL-E 3
.438 P1 N/A 2506-2 7
16 3
RSA-BJ-90 MS 1
89.21 E-P 3"
.438" P1 2506-2 7
16 CSA-BJ-11 MS 1
89.21 P-E 3"
.438" P1 2506-2 7
16 RSA-BJ-12 MS 1
89.21 E-VA 3"
.438" F1 2506-2 7
16 RSA-BJ-13 MS 1
B9.21 VA-P 3"
.438" P1 2506-2 7
16 1
RSA-BJ-13A MS 1
89.21 P-FM 3"
.438" P1 2506-2 7
16 INACCESSIBLE, INSIDE CONTAINMENT PENETRATION 28 DECEMBER 1995 PAGE 10
IWB-2500-1 CAT:
B-J COOPER NUCLEAR STATION MAIN SVEAM SYSTEM INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL P I PE.................. SYSTEM.. CNT. I TEM.NO. CF I G... SIZE.. TKNS..... MAT... W81. CAL.. 150................. PT.. MT.. UTO.. UT45.... PER.... REMARKS........
X-10...
RSA-BJ-14 MS 1
89.21 FH-P 3
.438 P1 N/A 2506-2 7
16 3
RSA-BJ-15 MS 1
89.21 P-E 3
.438 P1 N/A 2506-2 7
16 3
RSA-BJ-16 MS 1
B9.21 E-P 3"
.438" P1 2506-2 7
16 1
RSA-BJ-17 MS 1
89.21 P-E 3"
.438" P1 2506-2 7
16 RSA-BJ-18 MS 1
B9.21 E-P 3"
438" P1 2506-2 7
16 RSA-BJ-19 MS 1
B9.21 P-E 3"
.438" P1 2506-2 7
16 RSA-BJ-2 MS 1
89.21 E-P 3"
.438" P1 2506-2 7
16 RSA-BJ-20 MS 1
B9.21 E-P 3"
.438" P1 2506-2 7
16 RSA-BJ-21 MS 1
B9.21 P-VA 3
.438 P1 N/A 2506-2 7
16 3
RSA-BJ-3 MS 1
89.21 P-E 3"
.438" P1 2506-2 7
16 RSA-BJ-4 MS 1
89.21 E-P 3"
.438" Pt 2506-2 7
16 RSA-BJ-5 MS 1
89.21 P-E 3"
.438" P1 2506-2 7
16 RSA-BJ-6 MS 1
89.21 E-P 3"
.438" P1 2506-2 7
16 RSA-BJ-7*
MS 1
B9.21 P-E 3
.438 P1 N/A 2506-2 16 3
- FORMER PIPE WHIP EXAM RSQ-BJ-GP
' MS 1
89.21 E-P 3
.438 P1 N/A 2506-2 16 2
- FORMER PIPE WHIP EXAM RSA-BJ-9 MS 1
89.21 P-E 3"
.438" P1 2506-2 7
16 MSDR-BJ-1 MSDR 1
B9.21 CAP-P 3"
160 P1 2506-3 7
16 MSDR-BJ-2 MSDR 1
89.21 P-V 3
.438 P1 N/A 2506-3 7
16 3
MS-MO-74 MSDR-BJ-3 MSDR 1
89.21 V-P 3"
.438" P1 2506-3 7
16 MS-MO-74 MSDR-BJ-4 MSDR 1
B9.21 FH-P 3
.438 P1 N/A 2506-3 7
16 3
MSDR-BJ-5 MSDR 1
89.21 P-P 3"
.438" P1 2506-3 7
16 MSDR-BJ-71 MSDR 1
89.21 P-FM 3"
438" P1 2506-3 7
16 INACCESSIBLE, INSIDE CONTAINMENT PENETRATION X-8...
MSDR-BJ-72 MSDR 1
89.21 P-VA 3"
.438" P1 N/A 2506-3 7
16 PSI PERFORMED 12/15/1996... NEW WELD DUE TO DC 94-029...
29 ***
28 DECEMBER 1995 PAGE 11
I IWB-2500-1 CAT: B-J COOPER NUCLEAR STATION MAIM STEAM SYSTEM INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL P I PE.................. SYSTEM.. CNT. I TEM.NO. CFIG... SIZE.. TKNS..... MAT... WB1. CAL... IS0................. PT.. MT.. UTC.. UT45.... PER.... REMARCS..................
MSA BJ-14 MS-A 1
89.31 P-SWL 24-6 1.219 P1 106 CE731E611-4 7
16 6 6
MSA-BJ-19 MS-A 1
89.31 P-SWL 24-6 1.219 P1 106 GE731E611-4 7
16 6 6
MSA-BJ-24 MS-A 1
89.31 P-SWL 24-6 1.219 Pt 106 GE731E611-4 7
16 6 6
MSB-BJ-13 MS-B 1
B9.31 P-SWL 24-6 1.219 P1 106 GE731E611-4 7
16 6 6
MSB-BJ-18 MS-B 1
89.31 P-SWL 24-6 1.219 Pt 106 GE731E611-4 7
16 6
3 KSC-BJ-16 MS-C 1
89.31 P-SWL 24-6 1.219 P1 106 GE731E611-4 7
16 6 6
3 MSC-BJ-21 MS-C 1
B9.31 P-SWL 24-6 1.219 P1 106 GE731E611-4 7
16 6 6
MSC-BJ-8*
MS-C 1
89.31 P-SWL 24-10 1.531 P3 106 GE731E611-4 7
16 6
3
- FORMER PIPE WHIP EXAM...
MSD-BJ-14 MS-D 1
89.31 P-SWL 24-6 1.219 P1 106 GE731E611-4 7
16 6 6
MSD-BJ-19 MS-D 1
B9.31 P-SWL 24-6 1.219 P1 106 GE731E611-4 7
16 6 6
MSD-BJ24 MS-D 1
89.31 P-SUL 24-6 1.219 P1 106 GE731E611-4 7
16 6 6
MSD-BJ-28 MS-D 1
89.31 P-SWL 24-6 1.219 P1 106 CE731E611-4 7
16 6 6
12 ***
MSC-BJ-25*
MS-C 1
B9.32 P-WOL 24-3 1.219 P1 106 GE731E611-4 16 2
- FORMER PIPE WHIP EXAM...
t ***
158 28 DECEMBER 1995 PAGE 12 4
IWB-2500-1 CAT:
B-J COOPER NUCLEAR STATION
, NUCLECR BOILER SYSTEM INSERVICE INSPECTION PROGRAM REV: 4.1 i
SECOND INTERVAL P I PE.................. SYSTEM.. CNT. I TEM.NO. CF I G... SIZE.. TKNS..... MAT... W81. CAL... I S0................. PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
NS-BJ-N6B NB 1
89.11 N-F 6"
120 F22 CE.232-244 7
16 6 6
N6B TOP-ND (180 OAZ)
NB-BJ-07 NB 1
89.11 F-N 4
120 F22 CE.232-244 7
16 6 6
N7 TOP-HD
! RHD-BJ-9 NB 1
B9.11 F-N 6"
120 F22 CE.232-244 7
16 6 6
N6A TOP-MD (0 DAZ) 3 ***
RVD-BJ-15 NBD 1
89.21 P-E 2"
.218*
SS N/A x2512-200 7
REMOVE SUPPORT RRN-20 To ACCESS WELD FOR EXAMINATION RVD-BJ-96 NBD 1
B9.21 E-P 2
.218 SS N/A X2512-200 7
3 RVD-BJ-17 NBD 1
B9.21 P-E 2"
.218" SS N/A x2512-200 7
RVD-BJ-10 NBD 1
89.21 E-P 2
.218 SS N/A X2512-200 7
3 RVD-BJ-19 NBD 1
89.21 P-T 2"
.218" SS N/A X2512-200 7
RVD-BJ-20 NBD 1
89.21 T-P 2"
.218" SS N/A X2512-200 7
RVD-BJ-21 NBD 1
89.21 P-E 2"
.218" SS N/A x2512-200 7
RVD-BJ-22 NBD 1
89.21 E-P 2"
.218" SS N/A x2512-200 7
Rt9-BJ-26 NBD 1
89.21 T-P 2
.218 SS N/A X2512-200 7
3 Rt9-OJ-27 NBD 1
B9.21 P-E 2"
.218" SS N/A x2512-200 7
RVD-BJ-28 NBD 1
89.21 E-P 2"
.218" SS N/A x2512-200 7
RVI-BJ-11A1 NBI 1
B9.21 N-SE 2
.218 P12 M/A X2507-219 7
3
( N-11A N0Z ) ALSO REF:
CE DWG 232-242...
RVI-BJ-11A2 NBI 1
B9.21 SE-P 2"
.218" P12 N/A X2507-219 7
( N-11A N0Z ) ALSO REF:
CE DWG 232-242...
CVI-BJ-1181 NBI 1
89.21 N-SE 2"
.218" P12 N/A X2507-218 7
( N-11B NOZ ) ALSO REF:
CE DWG 232-242 RVI-BJ-1182 NBI 1
89.21 SE-P 2"
.218" P12 N/A x2507-218 7
( N-11B NO2 ) ALSO REF:
CE DWG 232-242 RVI-BJ-16A1 NBI 1
89.21 N-SE 2
.218 P12 N/A X2507-219 7
3
( N-16A N0Z ) ALSO REF:
CE DWG 232-242 RVI-BJ-16A2 NBI 1
B9.21 SE-P 2"
.218" P12 N/A x2507-219 7
( N-16A N02 ) ALSO RFE:
28 DECEMBER 1995 PAGE 1
IWB-2500-1 CAT: 8-J COOPER NUCLEAR STATION l O CLEAR BOILER SYSTEM INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL ii l
t PI PE.................. SYSTEM.. CNT. I TEM.No. CFIG... SIZE.. TKNS..... MAT... W81. CAL.. 150................. PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
j 4
I CE DWG 232-242 t
CVI-BJ-1681 M81 1
89.21 N-SE 2"
.218" P12 N/A X2507-218 7
( N-168 NO2 ) ALSO REF:
t CE DWG 232-242 t
l t
RVI-BJ-1682 N8I 1
99.21 SE-P 2"
.218" P12 N/A X2507-218 7
( N-168 N0Z ) ALSO RFE:
CE DWG 232-242 l
19 ***
I I
RVD-8J-SO N8D 1
89.40 P-E 2"
.218" CS N/A X2512-200 16 QVD-BJ-19 N80 1
89.40 E-P 2"
.218" CS N/A X2512-200 16 F
f l RVD-BJ-13 N80 1
B9.40 P-E 2"
.218" CS N/A X2512-200 16 RVD-BJ-13 N80 1
89.40 E-P 2"
.218" CS N/A X2512-200 16
[
RVD-BJ-23 N80 1
89.40 P-V 2
.218 SS N/A X2512-200 7
3 I
RVD-BJ-24 M80 1
89.40 V-P 2"
.218" SS N/A X2512-200 7
I RVD-BJ-25 N8D 1
89.40 P-V 2
.218 SS N/A X2512-200 7
3 QVD-8J-29 N8D 1
89.40 P-T 2"
.218" SS N/A X2512-200 7
RVD-BJ-30 N80 1
89.40 T-R 2"
.218" SS N/A X2512-200 7
RVD-BJ-31 N8D 1
89.40 T-P 2
.218 SS N/A X2512-200 7
3 l
RVD-BJ-32 NBD 1
89.40 P-V 2
.218 SS N/A X2512-200 7
3
[
t RVD-BJ-8 N8D 1
89.40 P-E 2"
.218" CS N/A X2512-200 16 RVD-BJ-9 N80 1
89.40 E-P 2"
.218" CS N/A X2512-200 16
[
RVI-BJ-11A3 NBI 1
89.40 P-R 1.5"
.200" P12 N/A X2507-219 7
( N-11A NOZ )
RVI-BJ-1183 NBI 1
89.40 P-R 2X1
.218 P12 N/A X2507-218 7
3
[
4 i
RVI-BJ-16A3 NBI 1
89.40 P-C00 2"
.218" P12 N/A X2507-219 7
RVI-BJ-16A4 NBI 1
89.40 C00-R 2"X1.5.218" F-304 N/A X2507-219 7
RVI-BJ-16A5 NSI 1
C9.40 1-P 1.5
.200 P12 N/A X2507-219 7
3 RVI-BJ-16AS NBI 1
89.40 P-E 1.5"
.200".
P12 N/A X2507-219 7
RMI-BJ-16A7 NSI 1
89.40 E-P 1.5"
.200" P12 N/A X2507-219 7
RVI-BJ-S6A8 NBI 1
89.40 P-T 1.5"
.200" P12 N/A X2507-219 7
OFF 2A TEMP. EQUAL. COL.,
ALSO REF: YARWAY DWG 28 DECEMBER 1995 PAGE 2 e
e
IWB-2500-1 CAT: B-J COOPER NUCLEAR STATION NUCLEAR BOILER SYSTEM INSERVICE INSPECTION PROGRAM REV: 4.1 SECOW INTERVAL 5
P I PE.................. SYSTEM.. CNT. ITEM.NO. CFI G... SIZE.. TKNS..... MAT... W81. CAL.. 150................. PT.. MT.. UTO.. UT45.... PER.... REMARKS..................
021-043112 RVI-BJ-1683 NBI 1
89.40 P-COU 2"
.218" P12 N/A X2507-218 7
RVI-BJ-1684 NBI 1
89.40 C00-R 2"X1.5.218" P12 N/A X2507-218 7
RVI-BJ-1685 NBI 1
89.40 I-P 1.5
.200 P12 N/A X2507-218 7
3 CUI-BJ-1686 NBI 1
89.40 P-E 1.5"
.200" P12 N/A X2507-218 7
RMI-BJ-1687 NBI 1
B9.40 E-P 1.5"
.200" P12 N/A X2507-218 7
RVI-BJ-1688 NBI 1
B9.40 P-T 1.5"
.200" P12 N/A X2507-218 7
0FF 2B TEMP. EQUAL. COL.,
ALSO REF: YARWAY DWG 021-043112 27 ***
t om 49 i
6 29 DECEMBER 1995 PAGE 3
CODE CASE N-408-2 COOPER NUCLEAR STATION IWC-2500-1 CAT: C-F INSERVICE INSPECTION PROGRAM REV: 4.1 RCic SYSTEM SECOND INTERVAL PI PE.................. SYSTEM.. CNT. I TEM.NO. CF IG... SI ZE.. TKNS..... MAT... W81. CAL... I S0................. PT.. MT.. UT0_. UT45.... PER.... RELREQ REMARKS..................
RWA-CF-10 RCIC 1
C5.51 T-F 6
.432 F-23 135 CB&I-69 7
16 6 6
3 RI-23 0FF TORUS PEN. X-224...
CWA-CF-11 RCIC 1
C5.51 T-F 6
.432 F-23 135 CB&I-69 7
16 6 6
3 RI-23 0FF TORUS PEN. X-224...
CWA-CF-12 RCIC 1
C5.51 P-T 6
.432 P2 135 LBat-69 7
16 6 6
3 RI-23 0FF TOURS PEN. X-224...
CWA-CF-14 RCIC 1
C5.51 N-P 6
.432 P1 153 2621-1 7
16 6 6
3 0FF TORUS PEN. X-224...
4 ***
RWA-CF-15 RCIC 1
P-E 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-16 RCIC 1
E-P 6"
.280" Pt 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION CWA-CF-17 RCIC 1
P-E 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-10 RCIC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-SO RCIC 1
P-E 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL TMICKNESS (N-408-2),
IEJST BE INCLtDED IN TOTAL WELD POPULATION RWA-CF-20 RCIC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL 28 DECEMBER 1995 PAGE 1
CODE CASE N-408-2 COOPER NUCLEAR STATION IWC-2500-1 CAT: C-F INSERVICE INSPECTION PROGRAM REV: 4.1 RCIC SYSTEM SECOND INTERVAL P I PE.................. SYSTEM.. CNT. ITEM.NO. CF I G... SI ZE.. TKNS..... MAT... WB1.taL.. 150................. PT.. MT.. UTO.. UT45.... PER.... RELREQ REMARKS..................
WELD POPULATION RWA-CF-21 RCIC 1
P-E 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNdSS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-22 RCiC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION CWA-CF-23 RCIC 1
P-E 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED 04 WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-24 RCIC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL.
WELD POPULATION CWA -CF-25 RCIC 1
P-E 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST 8E INCLUDED IN TOTAL WELD POPULATION RWA-CF-2G RCIC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLLDED IN TOTAL WELD POPULATION RWA-CF-27 RCIC 1
P-E 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-28 RCIC 1
E-V 6"
.280" F1 2621-1 RCIC-LV-23, EXEMPT FROM 28 DECEMBER 1995 PAGE 2
CODE CASE N-408-2 COOPER NUCLEAR STATION IWC-2500-1 CAT: C-F INSERVICE INSPECTION PROGRAM REV: 4.1 RCIC SYSTEM SECOND INTERV/L P I PE.................. SYSTEM.. CNT. I TEM.NO. CF IG... SI ZE.. TKNS..... MAT... WB1. CAL... IS0................. PT.. MT.. UTO.. UT45.... PER.... RELREQ REMARKS..................
NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION CWA-CF-29 RCIC 1
V-P 6"
.280" P1 2621-1 RCIC-LV-23, EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLLDED IN TOTAL WELD POPULATION RWA-CF-30 RCIC 1
P-E 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD *OPULATION CWA-CF-31 RCIC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-32 RCIC 1
P-E 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLtDED IN TOTAL WELD POPULATION RWA-CF-33 RCIC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWQ-CF-34 RCIC 1
P-V 6"
.280" P1 2621-1 RCIC-MO-41, EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),leJST BE INCLLDED IN TOTAL WELD POPULATION 28 DECEMBER 1995 PAGE 3 m
m m
CODE CASE N-408-2 COOPER NUCLEAR STATION IWC-2500-1 CAT:
C-F INSERVICE INSPECTION PROGRAM REV: 4.1 RCIC SYSTEM SECOND INTERVAL l P ! PE.................. SYSTEM.. CNT. I TEM.NO. CF IG... S IZE.. TKNS..... MAT... W81. CAL.. 150................. PT.. MT.. UTO.. UT45.... PER.... RELREQ REMARKS..................
RWA-CF-35 RCIC 1
V-P 6"
.280" P1 2621-1 RCIC-MO-41, EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST j
BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-37 RCIC 1
P-V 6"
.280" P1 2621-1 RCIC-CV-11. EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-38 RCIC 1
V-T 6"
.280" F1 2621-1 RCIC-CV-11. EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-30 RCIC 1
T-T 6"
.280" F1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION CWA-CF-40 RCIC 1
T-V 6"
.280" F1 2621-1 RCIC-CV-10, EXEMPT FROM
~
NDE 8ASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-41 RCIC 1
V-V 6"
.280" F1 2621-1 RCIC-CV-10.TO.RCIC-M0-18, EXEMPT FROM NDE 8ASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-42 RCIC 1
T-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASE!? ON 28 DECEMBER 1995 PAGE 4
CODE CASE N-408-2 COOPER NUCLEAR STATION IWC-2500-1 CAT:
C-F INSERVICE INSPECTION PROGRAM REV: 4.1 RCIC SYSTEM SECOND INTERVAL P I PE.................. SYSTEM.. CNT. I TEM.NO. CF I G... SI ZE.. TKNS..... MAT... W81. CAL.. 1S0................. PT.. MT.. UTO.. UT45.... PER.... RELREQ REMARKS.................
WALL THICKNESS (N-408-2),
MUST BE INCLLDED IN TOTAL WELD POPULATION CWA-CF-42A RCIC 1
P-V 6"
.280" P1 2621-1 RCIC-LV-10, EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION CWA-CF-43 RCIC 1
P-V 6"
.280" P1 2621-1 RCIC-LV-10, EXEMPT FROM f
NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLtDED IN TOTAL WELD POPULATION RWA-CF-44 RCIC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-45 RCIC 1
P-F F
.230" P1 2621-1 EXEMPT FROM WDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLLDED IN TOTAL WELD POPULATION f
RWA-CF-46 RCIC 1
F-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL i
WELD POPULATION RWA-CF-4F RCIC 1
P-F 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON l
WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-48 RCIC 1
F-P 6"
.280" P1 2621-1 EXEMPT FROM WDE 8ASED ON 28 DECEMBER 1995 PAGE 5 m
CODE CASE N-408-2 COOPER NUCLEAR STATION IWC-2500-1 CAT:
C-F INSERVICE INSPECTION PROGRAM REV: 4.1 RCIC SYSTEM SECOND INTERVAL P I PE.................. SYSTEM. CNT. I TEM.NO. CF I G... SIZE.. TKNS..... MAT... WB1. CAL.. 150................. PT.. MT.. UTO.. UT45.... PER.... RELREQ REMARKS..................
WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-49 RCIC 1
P-PU 6"
.280" P1 2621-1 RCIC PUMP, EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-50 RCIC 1
T-E 6"
.280" F1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-51 RCIC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-52 RCIC 1
P-E 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-53 RCIC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON
)
WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-54 RCIC 1
P-E 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL TMICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-53 RCIC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
28 DECEMBER 1995 PAGE 6
CODE CASE N-408-2 COOPER NUCLEAR STATION IWC-2500-1 CAT: C-F INSERVICE INSPECTION PROGRAM REV: 4.1 RCIC SYSTEM SECOND INTERVAL PI PE.................. SYSTEM.. CNT. ITEM.NO. CF I G... SIZE.. TKNS..... MAT... W81. CAL... IS0................. PT.. MT.. UTO.. UT45.... PER.... RELREQ REMARKS..................
MUST BE INCLUDfD IN TOTAL WELD POPULATION CWA CF-56 RCIC 1
P-E 6"
.280" P
r*
2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION CWA-CF-57 RCIC 1
E-E 6"
.280" F1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION CWA-CF-5G RCIC 1
E-P 6"
.280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULAft0N RWA-CF-59 RCIC 1
P-E 6"
.280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-60 RCIC 1
E-P 6"
.280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-G1 RCIC 1
P-E 6"
.280" P1 2621-2 EXEMPT FROM NDE 8ASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION CWA-CF-62 RCIC 1
E-P 6"
.280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION 28 DECEMBER 1995 PAGE 7
CODE CASE N-408-2 COOPER NUCLEAR STATION IWC-2500-1 CAT:
C-F INSERVICE INSPECTION PROGRAM REY: 4.1 RCIC SYSTEM SECOND INTERVAL P I PE.................. SYSTEM.. CNT. ITEM.NO. CF IG... SIZE.. TKNS..... MAT... W81. CAL.. 150................. PT.. MT.. UTO.. UT45.... PER.... RELREQ REMARKS..................
RWA-CF-63 RCIC 1
P-E 6"
.280" P1 2621-2 EXEMPT FROM NDE BASED ON
[
WALL THICKNESS (N-408-2),
L MUST BE INCLUDED IN TOTAL f
WELD POPULATION RWA CF-64 RCIC 1
E-P 6"
.280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-65 RCIC 1
P-E 6"
.280" P1 2621-2 EXEMPT FROM NDE BASED ON i
WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-66 RCIC 1
E-P 6"
.280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWQ-CF-67 RCIC 1
P-T 6"
.280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL
- WELD POPULATION RWA-CF-68 RCIC 1
T-R 6"
.280" F1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION 54 ***
om 58 28 DECEMBER 1995 PAGE 8
k IWC-2500-1 CAT:
C-G COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM REV: 4.1 SECOND INTERVAL P I PE.................. SYSTEM.. CNT. I TEM.NO. CFIG... SIZE.. TKNS..... MAT... I S0................. PT.. MT.. PER.... REMARKS..................
PIC-CG-10A PNC 1
C6.20 VLV.BD 24 RCC-755-1 7
16 VALVE PC-A0V-238AV...
PNC-CG-10B PNC 1
C6.20 VLV.BD 24 RCC-755-1 7
16 VALVE PC-A0V-238AV...
PNC-CG-27A PNC 1
C6.20 VLv.BD 24 RCC-755-2 7
16 VALVE PC-MOV-233MV...
PNC-CG-27B PNC 1
C6.20 VLV.BD 24 RCC-755-2 7
16 VALVE PC-MOV-233MV...
PNC-CG-28A PNC 1
C6.20 VLV.BD 24 RCC-755-2 7
16 VALVE PC-A0V-237AV...
PNC-CG-28B PNC 1
C6.20 VLV.BD 24 RCC-755 7 16 VALVE PC-A0V-237AV...
PNC-CG-35A PNC 1
C6.20 VLV.BD 24 RCC-755-3 7
16 3 VALVE PC-Mov-231MV...
PNC-CG-35B PNC 1
C6.20 VLV.BD 24 RCC-755-3 7
16 3 VALVE PC-Mov-231MV...
PNC-CG-36A PNC 1
C6.20 VLV.BD 24 RCC-755-3 7
16 VALVE PC-A0V-246AV...
PNC-CG-368 PNC 1
C6.20 VLV.BD 24 RCC-755-3 7
16 VALVE PC-A0V-246AV...
'PNC-CG-5A PNC 1
C6.20 VLv.BD 24 RCO-755-1 7
16 VALVE PC-MOV-230MV...
PNC-CG-5B PNC 1
C6.20 VLV.BD 24 RCO-755-1 7
16 VALVE PC-MOV-230MV...
PNC-CG-6A PNC 1
C6.20 VLV.BD 24 RCC-755-1 7
16 VALVE PC-A0V-245AV...
PNC-CG-68 PNC 1
C6.20 VLV.BD 24 RCC-755-1 7
16 VALVE PC-ADV-245AV...
PNC-CG-9A PNC 1
C6.20 VLV.BD 24 RCC-755-1 7
16 VALVE PC-MOV-232MV...
PNC-CG-98 PNC 1
C6.20 VLV.BD 24 RCC-755-1 7
16 VALVE PC-MOV-232MV...
16 ***
16 28 DECEMBER 1995 PAGE 1
I l
l l
l l
l CODE CASE N-509 COOPER NUCLEAR STATION IWD-2500-1 CAT: D-A INSERVICE INSPECTION PROGRAM kW: 4.1 REACTOR EQUIPMENT COOLING STSTEM SECOND INTERVAL i
l PI PE.................. SYSTEM.. CNT. I TEM.NO. CFIG... SIZE.. TKNS..... MAT.. 150................ VT....... PER.... REMARKS..................
REC-TK-ST-A1 REC 1
D1.10 SP-TK 2848-7 8
3 SURGE TANK SUPPORT ATTACHMENT... REFERENCE EATON METAL PRODUCTS CORP. VENDOR CODE E0600 FOR DRAWING #80066-3...
REC-TK-ST-A2 REC 1
D1.10 SP-TK 2848-7 8
3 SURGE TANK SUPPORT ATTACHMENT... REFERENCE EATON METAL PRODUCTS CORP. VENDOR CODE E0600 FOR DRAWING #80066-3...
REC-TK-SV-A3 REC 1
D1.10 SP-TK 2848-7 8
3 SURGE TANK SUPPORT ATTACHMENT... REFERENCE EATON METAL PRODUCTS CORP. VENDOR CODE E0600 FOR DRAWING #80066-3...
REC-TK-ST-A4 REC 1
D1.10 SP-TK 2848-7 8
3 SURGE TANK SUPPORT ATTACHMENT... REFERENCE EATON METAL PRODUCTS CORP. VENDOR CODE E0600 FOR DRAWING #80066-3...
REC-HXB-Al REC-A 1
D1.10 SP-HX 2852-8 8
REC HEAT-EXCHANGER
" REC-HX-A" SUPPORT OPPSITE END FROM NAMEPLATE... REFERENCE "SWECO" VENDOR CODE S2900 FOR DRAWINGS... VENDOR MANUAL #0153 REC-HXB-A2 REC-A 1
D1.10 SP-HX 2852-8 8
REC NEAT-EXCHANGER
" REC-HX-A" SUPPORT ADJACENT TO NADE PLATE...
28 DECEMBER 1995 PAGE 1
CODE CASE N-509 COOPER NUCLEAR STATION IWD-2500-1 CAT: D-A INSERVICE INSPECTION PROGRAM REV: 4.1 REACTOR EQUIPMENT COOLING SYSTEM SECOND INTERVAL PI PE.................. SYSTEM.. CNT. I TEM.NO. CF I G... SIZE.. TKNS..... MAT... I SO................. VT........ PER.... REMARKS..................
REFERENCE "SWECO" VEIN)0R CODE S2900 FOR DRAWINGS... VENDOR MANUAL
- 0153 REC-HXA-A1 REC-B 1
D1.10 SP-HX 2852-9 8
3 TOP SUPPORT OPPSITE END FROM NAME PLATE ON BOTTOM HEAT-EXCHANGER... SYSTEM EQUAL REC-HX-B ON P&lD...
REFERENCE:
REC-HX-A ON "SWEC0" DRAWING NO.
M-82057, VENDOR CODE S2900 FOR DRAWINGS...
VENDOR MANUAL #0153...
REC-HXA-A2 REC-B 1
D1.10 SP-HX 2852-9 8
3 TOP SUPPORT ADJACENT TO NAME PLATE ON BOTTOM HEAT-EXCHANGER... SYSTEM EQUAL REC-HX-B ON P&ID...
REFERENCE:
REC-HX-A ON "SWECO" DRAWING NO.
M-82057, VENDOR CODE S2900 FOR DRAWINGS...
VENDOR MANUAL #0153...
REC-HXA-A3 REC-B 1
D1.10 SP-HX 2852-9 8
3 BOTTOM SUPPORT OPPSITE END FROM NAMEPLATE ON BOTTOM HEAT-EXCHANGER...
SYSTEM EQUAL REC-HX-B ON P&lD...
REFERENCE:
REC-HX-A ON "SWEC0" DRAWING NO. M-82057, VENDOR CODE S2900 FOR 28 DECEMBER 1995 PAGE 2 w
CODE CASE N-509 COOPER NUCLEAR STATION IWD-2500-1 CAT:
D-A INSERVIE INSPECTION PROGRAM REV: 4.1 REACTOR EQUIPMENT COOLING SYSTEM SECOND INTERVAL P I PE.................. SYSTEM.. CNT. ITEM.NO. CF IG... SIZE.. TKNS..... MAT.. 1S0................. VT........ PER.... REMARKS..................
DRAWINGS... VENDOR MANUAL
- 0153...
REC-HXA-A4 REC-B 1
D1.10 SP-HX 2852-9 8
3 BOTTON SUPPORT ADJACENT TO NAMEPLATE ON BOTTOM HEAT-EXCHANGER... SYSTEM EQUAL REC-HX-B ON P&!D...
REFERENCE:
REC-HX-A ON "SWEC0" DRAWING NO.
M-82057, VENDOR N E
$2900 FOR DRAWINGS...
VENDOR MANUAL #0153...
10 ***
RCC-DB-135 REC 1
D1.20 STN 2848-14 8
REFERENCE CNS MSK N0670/RCC-X135...
RCC-DB-160 REC 1
D1.20 STN 2848-8 8
REFERENC CNS HSK N0670/RCC-H140...
RCC-DB-149 REC 1
D1.20 STN 2848-14 8
REFERENCE CNS HSC N0670/RCC-H149...
RCC-DB-181 REC 1
D1.20 STN 2848-7 8
REFERENCE CNS HSK N0670/RCC-M181...
RCC-DB-S9 REC 1
D1.20 STN 2848-2 8
REFERENCE CNS HSK N0670*RCC-M19...
D1.20 STN 2848-2 8
REFERENCE CNS MSK N0670*RCC-H20 RCC-DB-21 REC 1
D1.20 LUG 2848-2 8
REFERENCE CNS MSK N0670/RCC-H21...
RCC-DB-23A REC 1
D1.20 STN 2848-2 8
REFERECNCE CNS HSC N0670/RCC-H23A...
23 DECEMBER 1995 PAGE 3 a
CODE CASE N-509 COOPER NUCLEAR STATION 12-2500-1 CAT: D-A INSERVICE INSPECTION PROGRAM REY: 4.1 REACTOR EQUIPMENT COOLING SYSTEM SECOND INTERVAL P IPE.................. SYSTEM.. CNT. ITEM.No. CFI G... SIZE.. TKNS..... MAT.. 150................. VT........ PER.... REMARKS..................
CCC-DB-24A REC 1
D1.20 STN 2848-2 8
REFERENCE CNS MSK N0670*RCC-H24A...
CCC-DB-30A REC 1
D1.20 STN 2848-2 8
REFERENCE CNS MSK N0670*RCC-H30A...
RCC-DB-32A REC 1
D1.20 STN 2848-2 8
REFERENCE CNS MSK N0670*RCC-H32A...
RCC-DB-33A REC 1
D1.20 STN 2848-2 8
REFERENCE CNS MSK N0670*RCC-H33A...
RCC-DB-34 REC 1
D1.20 LUG 2848-2 8
REFERENCE CNS MSC N0670*RCC-H34...
RCC-DB-34A REC 1
D1.20 STN 2848-2 8
REFERENCE CNS MSK N0670/RCC-H34A...
RCC-DB-35 REC 1
D1.20 STN 2848-2 8
REFERENCE CNS HSK N0670*RCC-H35...
RCC-DB-50 REC 1
D1.20 STN 2848-14 8
REFERENCE CNS MSK N0670/RCC-S50...
RCC-DB-90 REC 1
D1.20 STN 2848-8 8
REFERENCE CNS HSK N0670/RCC-S90...
RCC-DB-51 REC-A 1
D1.20 STN 2848-14 8
3 REFERENCE CNS MSK N0670*RCC-SSI...
RCC-DB-97 REC-ENC 1
D1.20 LUG 2848-51 8
3 REFERENCE CNS MSK i
N0670*RCC-S97...
19 ***
29
[
28 DECEMBER 1995 PAGE 4
CODE CASE N-509 COOPER NUCLEAR STATION IWD-2500-1 CAT: D-A INSERVICE INSPECTION PROGRAM F4V: 4.1 SERVICE WATER SYSTEM SECOND INTERVAL PI PE.................. SYSTEM.. CNT. I TEM.MO. CF I G... SIZE., TKNS..... MAT.. 150................. VT........ PER.... REMARKS..................
SW-STRB-Al SW 1
D1.10 STRN 2852-3 8
SW STRAINER "SW-STR-B" SUPPORT... REFERENCE ZURN INDUSTRIES INC VENDER CODE ZO100 FOR DRAWING NO. I-691125-A... VENDOR MANUAL #0520...
SW-SVRA-A1 SW-A 1
D1.10 STRN 2852-3 8
3 SW STRAINER "SW-STR-A" i
SUPPORT... REFERENCE ZURN INDUSTRIES INC VENDER CODE Z0100 FOR DRAWINGS NO. 1-691125-A AND 47736... WNDOR MANUAL
- 0320...
2 ***
SW-DB-104 SW 1
D1.20 STN 2851-7 8
REFERENCE CNS HSK N0670/SW-S104...
SW-DB-105 SW 1
D1.20 STN 2851-2 8
REFERENCE CNS HSK SW-S105...
SW-DB-124 SW 1
D1.20 STN 2851-1 8
REFERENCE CNS HSK N0670/SW-S124 SW-DB-126 SW 1
D1.20 LUG 2852-54 8
REFERENCE CNS MSK N0670/SW-5126 SW-DB-128 SW 1
D1.20 STN 2852-54 8
REFERENCE CNS HSC N0670/SW-5128...
SW-DB-13F SW 1
01.20 LUG 2852-9 8
REFERENCE CNS HSK N0670/SW-H137...
SW-DB-138 SW 1
D1.20 LUG 2852-9 8
REFERENCE CNS MSK N0670/SW-H138...
28 DECEMBER 1995 PAGE 1
CODE CASE N-509 COOPER NUCLEAR STATION IWD-2500-1 CAT:
D-A INSERVICE INSPECTION PROGRAM REY: 4.1 SERVICE WATER SYSTEM SECOND INTERVAL f I PE.................. SYSTEM.. CNT. I TEM.NO. CFI G... SIZE.. TKNS..... MAT.. 150................. VT........ PER.... REMARKS..................
SW-DB-14 SW 1
D1.20 STN 2851-6 8
REFERENG CNS HSK N0670*SW-S14...
SW-DB-141 SW 1
D1.20 STN 2852-9 8
REFEREN N Q S HSK N0670/SW-H141 SW-D3-144 SW 1
D1.20 STN 2852-9 8
REFERENG CNS HSK N0670/SW-H141...
SW-DB-144A SW 1
D1.20 STN 2852-55 8
REFERENCE CNS HSK N0670/SW-S144...
SW-DB-147 SW 1
D1.20 LUG 2852-9 8
REFERENG CNS HSK N0670/SW-H147...
D1.20 SAD 2852-3 8
REFERENCE CNS HSC N0670/SW-14...
SW-DB-15 SW 1
D1.20 LUG 2851-6 8
REFERENCE CNS MSK N0670/SW-515...
SW-DB-15A SW 1
D1.20 SAD 2852-3 8
REFERENCE CNS MSK N0670/SW-15...
SW-DB-164 SW 1
D1.20 LUG 2852-8 8
REFERENCE CNS HKS N0670/SW-H164 SW-DB-17 SW 1
D1.20 SAD 2852-3 8
REFERENG CNS MSC N0670/SW-17...
SW-DB-18 SW 1
D1.20 SAD 2852-3 8
REFERENCE CNS MSK N0670/SW-18...
SW-DB-184 SW 1
D1.20 LUG 2851-1 8
REFERENCE CNS HSK N0670/SW-H184 SW-DR-1*7 SW 1
D1.20 LUG 2852-8 8
REFERENG CNS NSK N0670/SW-H187...
D1.20 STM 2852-8 8
REFERENC CNS MSK N0670/SW-H189...
SW-DB-19 SW 1
D1.20 SAD 2852-3 8
REFERENG CNS MSK N0670/SW-19...
28 DECEMBER 1995 PAGE 2
CODE CASE N-509 COOPER NUCLEAR STATION IWD-2500-1 CAT:
D-A INSERVICE INSPECTION PROGRAM REV: 4.1 SERVICE WATER SYSTEM SECOND INTERVAL PI PE.................. SYSTEM.. CNT. I TEM.NO. CF IG... SI ZE.. TKNS..... MAT... IS0................. VT........ PER.... REMARKS..................
SW-DB-190 SW 1
D1.20 E-LUG 2852-8 8
REFEREN E CNS HSC N0670/SW-190...
f SW-DB-194 SW 1
D1.20 LUG 2851-4 8
REFERENCE CNS HSK N0670/SW-H194...
SW-DB-20 SW 1
D1.20 SAD 2852-3 8
REFERENCE CNS MSK NM70/SW-20...
SW-DB-21 SW 1
D1.20 SAD 2852-3 8
REFERENCE CNS MSK N0670/SW-21 SW-DB-22 SW 1
D1.20 SAD 2852-3 8
REFERENCE CNS HSK N0670/SW-22...
SW-DB-220 SW 1
D1.20 E-LUG 2400-4 8
REFERENCE CNS HSC N0670*SWH220...
SW-DB-221 SW 1
D1.20 E-LUG 2400-4 8
REFERENCE CNS MSC N0670/SW-H221...
SW-DB-223 SW 1
D1.20 E-LUG 2400-4 8
REFERENCE CNS HSK N0670/SW-H223 SW-DB 23 SW 1
D1.20 SAD 2852-3 8
REFERENCE CNS MSC N0670/SW-23...
SW-DB-230 SW 1
D1.20 LUG 2852-54 8
REFERtNCE CNS MSK Nuo70/SW-H230...
SW-DB-23A SW 1
D1.20 ~ LUG 2852-10 8
REFERENCE CNS HSK N%70/SW-S23...
SW-DB-23E SW 1
D1.20 SAD 2852-3 8
REFERENCE CNS HSK NM70/SW-H23E...
SW-DB-23F SW 1
D1.20 SAD 2852-3 8
REFERENCE CNS HSK N0670/SW-H23F...
SW-DB-23G SW 1
D1.20 SAD 2852-3 8
REFERENCE CNS MSK N0670/SW-H23G...
SW-DB-23H SW 1
D1.20 SAD 2852-3 8
REFERENCE CNS MSK N0670/SW-H23H...
28 DECEMBER 1995 PAGE 3
CODE CASE N-509 COOPER NUCLEAR STATION IWD-2500-1 CAT: D-A INSERVICE INSPECTION PROGRAM REV: 4.1 SERVICE WATER SYSTEM SECOND INTERVAL P I PE.................. SYSTEM.. CNT. ITEM.NO. CF IG... SIZE.. TKNS..... MAT.. 1S0................. VT........ PER.... REMARKS..................
SW-DB-25 SW 1
D1.20 LUG 2852-10 8
REFERENCE CNS MSK N0670/SW-S24...
SW-DB-256 SW 1
01.20 STN 2852-55 8
3 REFERENCE CMS HSK N0670*SW-H256...
SW-DB-258 SW 1
D1.20 STN 2852-55 8
REFERENCE CNS MSK N0670/SW-H258...
SW-DB-26 SW 1
D1.20 LUG 2852-10 8
REFERENCE CNS HSK N0670/SW-S26...
SW-DB-20 SW 1
D1.20 SAD 2852-7 8
REFERENCE CNS HSK N0670/SW-S28 SW-DB-44 SW 1
D1.20 E-LUG 2851-6 8
REFERENCE CNS N0670/SW-H44...
SW-DB-446 SW 1
D1.20 LUG 2852-26 8
REFERENCE CNS HSK N0670/SW-H446...
SW-DB-447 SW 1
D1.20 LUG 2852-26 8
REFERENCE CNS HSK N0670/SW-H447...
SW-DQ-44A SW 1
D1.20 LUG 2852-18 8
REFERENCE CNS MSK N0670/SW-$44...
SW-DB-49 SW 1
01.20 STN 2852-9 8
REFERENCE CNS HSK N0670/SW-S49...
SW-DB-500 SW 1
D1.20 LUG 2852-23 8
REFERENCE CNS HSK N0670/SW-S500B&R...
SW-DB-501 SW 1
D1.20 LUG 2852-23 8
REFERENCE CNS MSK N0670/SW-S5018&R...
SW-DB-51 SW 1
D1.20 STN 2852-9 8
REFERENCE CNS MSK N0670/SW-S51 SW-DB-52 SW 1
D1.20 STN 2852-9 8
REFERENCE CNS MSK N0670/SW-S52...
SW-DB-59 SW 1
D1.20 E-LUG 2851-3 8
REFERENCE CNS HSK N0670/SW-H59...
28 DECEMBER 1995 PAGE 4
CODE CASE N-509 COOPER NUCLEAR STATION IWD-2500-1 CAT: D-A INSERVICE INSPECTION PROGRAM REY: 4.1 SERVICE WATER SYSTEM SECOND INTERVAL P I P E.................. SY ST EM. CNT. I T EM.NO. CF I G... S I ZE.. T KNS..... MAT... I S0................. VT........ PE R.... REMARKS..................
SW-DB-61A SW 1
D1.20 LUG 2851-2 8
REFERENCE CNS HSK N0670/SW-H61A...
SW-DB-62A SW 1
D1.20 SAD 2851-2 8
REFERENCE CNS HSK N0670/SW-H62A...
SW-DB-65 SW 1
D1.20 SAD 2851-2 8
REFERENCE CNS MSK N0670/SW-H65...
SW-DB-60 SW 1
D1.20 STN 2852-19 8
REFERENCE CNS HSK N0670/SW-S68...
SW-DB-70 SW 1
D1.20 STN 2852-19 8
REFERENCE CNS MSK N0670/SW-570...
SW-DB-72 SW 1
D1.20 STN 2852-19 8
REFERENCE CNS HSK N0670/SW-S72...
SW-DB-74 SW 1
D1.20 STN 2852-19 8
RErERENCE CNS HSK N0670/SW-S74...
SW-DB-94 SW 1
D1.20 STN 2852-8 8
REFERENCE CNS MSK N0670/SW-S94...
SW-DB-96 SW 1
01.20 STN 2852-19 8
REFERENCE CNS HSK N0670/SW-H%
SW-DB-97 SW 1
D1.20 STN 2852-8 8
REFEREMCE CNS HSK N0670/SW-S97...
SW-DB-97A SW 1
D1.20 STN 2852-19 8
REFEREN E CNS HSK N0670/SW-H97...
SW-DB-98 SW 1
D1.20 STN 2852-19 8
REFERENE CNS MSK N0670/SW-H98...
SW-DB-99 SW 1
D1.20 STN 2852-19 8
REFERENCE CNS HSK N0670/SW-H99...
SW-og-178 SW-A 1
D1.20 LUG 2851-1 8
3 REFERENCE CNS HSK N0670*SW-H178...
SW-DB-45 SW-A 1
01.20 E-LUG 2851-6 8
3 REFERENCE CNS HSK N0670*SW-H45...
28 DECEMBER 1995 PAGE 5
CODE CASE N-509 C000Eit NUCLEAR STATION IWD-2500-1 CAT: D-A INSERVICE INSPECTION PROGRAM REV: 4.1 SERVICE WATER SYSTEM SECOND INTERVAL PI PE.................. SYSTEM.. CN T. ITEM.NO. CF I G... SIZE.. TKNS..... MAT.. 150................. VT........ PER.... REMARKS..................
SW-DB-46 SW-A 1
D1.20 STN 2851-6 8
3 REFERENCE CNS HSK N067D*SW-M46 SW-DB-245 SW-B 1
D1.20 STN 2852-9 8
3 REFERENCE CNS MSK N0670*SW-H145...
SW-DB-16 SW-B 1
D1.20 SAD 2852-3 8
3 REFERENCE CNS HSK N0670*SW-16...
SW-DB-50 SW-B 1
D1.20 STN 2852-9 8
3 REFERENCE CNS HSK N0670*SW-$50...
SW-DB-57 SW-8 1
D1.20 E-LUG 2851-3 8
3 REFERENCE CNS HSK N0670*SW-H57...
72 see SW-PR-A1 SW 1
01.30 SP-PU 2852-3 8
SW PUMP "SW-P-B" SUPPORT... REFERENCE
" BYRON JACKSON" VENDOR CODE B5800 FOR DRAWINGS 2C-4747 AND 1F-6921...
VENDOR MANUAL #0180...
SW-PC-A1 SW 1
D1.30 SP-PU 2852-3 8
SW PUMP "SW-P-C" SUPPORT... REFERENCE
" BYRON JACKSON" VENDOR l
CODE B5800 FOR DRAWINGS... VENDOR MANUAL
- 0180 SW-PD-Al SW 1
D1.30 SP-PU 2852-3 8
SW PUMP "SW-P-D" l
SUPPORT... REFERENCE l
" BYRON JACKSON" VEIO0k CODE B5800 FOR DRAWINGS... VEICOR MANUAL 20 DECEMBER 1995 PAGE 6
~
~_
CODE CASE N-509 COOPER NUCLEAR STATION IWD-2500-1 CAT: 0-A INSERVICE INSPECTION PROGRAM REV: 4.1 SERVICE WATER SYSTEM SECO 2 INTERVAL P I PE.................. SYST EM.. CNT. I TEM.NO. CFIG... SIZE.. TKNS..... MAT.. 150................. VT........ PER.... REMARKS..................
80180 SW-pA-A1 SW-A 1
D1.30 SP-PU 2852-3 8
3 SW PUMP "SW-P-A" SUPPORT... REFERENCE
" BYRON JACKSON" VE20R CODE B5800 FOR DRAWINGS 2C-4747 AND 1F-6921...
VENDOR MANUAL 80180...
4 ***
78 L
23 DECEMBER 1995 PAGE 7
~
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL AUGNENTED INSERVICE INSPECTION PROGRAN REC WELD EXANINATION SCHEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
TEK.
1993 1995 t
2848-1-FW-PT-2-B-X24E PIPE TO PENETRATION X-24 8
0.322 I
2848-2-FW-W101 ELBOW TO FLANGE (REC-V-14) 10 0.365 I
i 2848-2-FW-W17 PIPE TO TEE 12 0.375 I
i 2848-2-FW-W4 FLANGE (PUMP 1B) TO RED. ELBOW 6
0.28 II 2848-2-FW-W41 PIPE TO FLANGE (REC-V-18) 12 0.375 I
2848-2-FW-W5 RED. ELBOW TO PIPE 8
0.322 II 2848-2-FW-W66 PIPE TO ELBOW 4
0.237 I
2848-2-FW-W67 PIPE TO ELBOW 4
0.237 I
2848-2-FW-W68 PIPE TO 6X4 CONC. REDUCER 4
0.237 I
2848-2-FW-WD ELBOW TO VALVE (REC-CV-11CV) 8 0.322 I
4 2848-2-SW-W8 RED. ELBOW TO PIPE 8
0.322 II 2848-2-SW-WA ELBOW TO VALVE (REC-CV-10CV) 8 0.322 II 2848-2-SW-WL VALVE (REC-V-17) TO PIPE 8
0.322 II 2848-2-SW-WQ PIPE TO VALVE (REC-MOV-MO694) 4 0.237 II 2848-2-SW-WS VALVE (REC-MOV-MO698) TO ELBOW 6
0.28 I
2848-2-SW-WW PIPE TO BRANCH 12 0.375 I
2848-2-W1 FLANGE (PUMP 1A) TO RED. ELBOW 6
0.28 II 2848-2-W10 FLANGE (PUMP ID) TO RED. ELBOW 6
0.280 S
Page 2 Of 15 t
L
COOPER NUCLEAR STATION i
SECOND TEN YEAR INTERVAL AUGMENTED INSERVICE INSPECTION PROGRAM REC WELD EXAMINATION SCHEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
THK.
1993 1995 2848-2-W102 FLANGE (PI-449C) TO ELBOW 10 0.375 S
2848-2-W11 RED. ELBOW TO PIPE 6
0.280 S
2848-2-W112 FLANGE TO PI-449D 6
0.280 S
2848-2-W12 PIPE TO ELBOW 8
0.322 C
2848-2-W13 PIPE TO CAP 8
0.322 C
2848-2-W2 RED. ELBOW TO PIPE 3
0.322 S
2848-2-W3 PIPE TO ELBOW 8
0.322 C
2848-2-W43 12X16 CONC. REDUCER TO TEE 12 0.375 S
2848-2-W44 12X16 CONC. REDUCER TO FLANGE 16 0.375 S
2848-2-W45 TEE TO BRANCH 12 0.375 C
2848-2-W46 ELBOW TO PIPE 12 0.375 S
2848-2-W52 TEE TO ELBOW 12 0.375 S
2848-2-W56 FLBOW TO PIPE 6
0.280 S
2848-2-W57 PIPE TO ELBOW 6
0.280 S
2848-2-W60 PIPE TO ELBOW 6
0.280 S
2848-2-W69 BRANCH TO 6X4 CONC. REDUCER 6
0.280 C
2848-2-W70 TEE TO 6X4 CONC. REDUCER 6
0.280 C
2848-2-W71 ELBOW TO TEE 6
0.280 S
Page 3 Of 15
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL AUGMENTED INSERVICE INSPECTION PROGRAM REC WELD EXAMINATION SCHEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
TEK.
1993 1995 y
2848-2-W75 ELBOW TO PIPE
-4 0.237 S
2848-2-W80 PIPE TO 12X10 CONC. REDUCER 12 0.375 II 2848-2-W86 PIPE TO 12X10 CONC. REDUCER 10 0.365 II 2848-2-W90 PIPE TO 12X10 CONC. REDUCER 12 0.375 II 2848-2-W95 PIPE TO 6X4 CONC. REDUCER 6
0.280 C
2848-2-W96 FLANGE (REC-V-12) TO 12X10 CONC. REDUCER 10 0.375 S
J 2848-2-WC VALVE (REC-V-11) TO PIPE 8
0.322 C
I,t48-2-WF VALVE (REC-V-13) TO PIPE 8
0.322 S
2848-2-WK VALVE (REC-CV-13CV) TO VALVE (REC-V-17}
8 0.322 S
t 2848-4-34-SW-W1 PIPE TO ELBOW 6
0.28 II 2848-4-34-SW-W2 ELBOW TO PIPE 6
0.2P II i
...?
7 2848-4-35-FW-WC PIPE TO ELBOW 6
0.28 I
1 2848-4-35-SW-W1 ELBOW TO PIPE 6
0.28 I
[
l 2848-4-35-SW-W2 PIPE TO ELBOW 6
0.28 I
j 2848-4-35-SW-W3 ELBOW TO PIPE 6
0.28 I
2848-4-35-SW-W4 PIPE TO ELBOW 6
0.28 I
2848-4-38-FW-WG ELBOW TO PIPE 6
0.28 I
2848-4-38-SW-W1 ELBOW TO PIPE 6
0.28 I
Page 4 Of 15 i
I
i
. i COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL AUGMENTED INSERVICE INSPECTION PROGRAM REC WELD EXAMINATION SCHEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
TEK.
1993 1995 t
2848-4-38-SW-W2 PIPE TO ELBOW 6
0.28 I
i 2848-4-38-SW-W3 ELBOW TO PIPE 6
0.28 I
2 84 8-4-38 -SW-W4 PIPE TO ELBOW 6
0.28 1
2848-7-A PIFL 7ALVE (REC-V-173) 6 0.280 S.
2848-7-FA PIPE TO PIPE 6
0.280 C
2848-7-FW-W1 PIPE TO ELBOW 6
0.28 I
2848-7-FW-W3 ELBOW TO PIPE 3
0.216 I
2848-7-SW-WD FLANGE TO RED. ELBOW 4
0.237 I
2848-7-W2 ELBOW TO PIPE 6
0.280 S
2848-7-WB VALVE (REC-V-173) TO FLANGE 6
0.280 C
2848-7-WC PIPE TO PIPE 6
0.280 C
2848-8-FW-PT-2-B-X23E PIPE TO PENETRATION X-23 8
0.322 I
2848-8-WI PIPE TO ELBOW 8
0.322 S
2848-8-WJ PIPE TO PIPE.
8 0.322 II 2848-8-WK PIPE TO ELBOW 8
0.322 II 2848-8-WL PIPE TO ELBOW 8
0.322 S
2848-9-FW-36 ELBOW TO PIPE 3
0.216 I
2848-9-FW-W11 PIPE TO ELBOW 4
0.237 I
Page 5 of 15 m
m
t I
l COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL AUGNENTED INSERVICE INSPECTION PROGRAN l
l REC WELD EXANINATION SCNEDULE, REVISION 1 i
WELD ID DESCRIPTION DIA.
TEK.
1993 1995 i
i 2848-9-FW-W2 PIPE TO TEE 4
0.237 II
(
2848-9-FW-W25 ELBOW TO PIPE 4
0.237 II 2848-9-FW-W52 ELBOW TO PIPE 4
0.237 II l
i 2848-9-FW-W69 PIPE TO PIPE 3
0.216 I
t i
i 2848-9-FW-W'/4 ELBOW TO PIPE 3
0.216 I
2848-9-FW-W79 PIPE TO ELBOW 3
0.216 II I
2848-9-FW-W80 ELBOW TO PIPE 3
0.216 II i
2848-9-FW-WF TEE TO BRANCH 4
0.237 II 2848-9-FW-WG 413 CONC. REDUCER TO PIPE 3
0.216 II 2848-9-FW-WS TEE TO BRANCH 4
0.237 II 2848-9-SW-W27 TEE TO 4X3 CONC. REDUCER 4
0.237 II 2848-9-SW-W81 PIPE TO 3X1-1/2 CONC. REDUCER 3
0.216 II 2848-9-SW-WI PIPE TO ELBOW 3
0.216 I
T 2848-9-SW-WK ELBOW TO VALVE (REC-V-96) 3 0.216 I
2848-9-SW-WP PIPE TO ELBOW 3
0.216 II 2848-9-SW-WQ PIPE TO PIPE 3
0.216 II 2848-9-SW-WR PIPE TO 4X3 CONC. RECUCER 3
0.216 II 2848-9-SW-WY ELBOW TO PIPE 3
0.216 II k
Page 6 of 15 L
L E
r F
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL
[
AUGMENTED INSERVICE INSPECTION PROGRAN l
REC WELD EXANIMATION SCEEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
TEK.
1993 1995 t
2848-9-W12 PIPE TO ELBOW 4
0.237 s
I 2848-?-W17 ELBOW TO PIPE 4
0.237 S
2848-9-W19 PIPE TO ELBOW 4
0.237 s
2848-9-W31 PIPE TO PIPE 4
0.237 S
2848-9-W34 ELBOW TO PIPE 4
0.237 S
2848-9-W44 PIPE TO ELBOW 4
0.237 s
I 2848-9-W55 PIPE TO ELBOW 4
0.237 S
2848-9-W1 TEE TO PIPE 4
0.237 S
2848-9-WFE ELBOW TO PIPE 4
0.237 II
(
2848-9-WN PIPE TO VALVE (REC-V-95) 3 0.216 S
5 2848-14-FW-W15 PIPE TO ELBOW 6
0.28 II l
2848-14-FW-W17 PIPE TO 6X4 CONC. REDUCER 6
0.28 II 2848-14-FW-W18 PIPE TO PIPE 6
0.28 I
2848-14-FW-W21 PIPE TO FLANGE (REC-MOV-MO731) 6 0.28 I
2848-14-FW-W26 ELBOW TO PIPE 4
0.237 I
2848-14-FW-W34 PIPE TO ELBOW 4
0.237 I
i 2848-14-FW-W44 BRANCH TO REDUCING TEE 8
0.322 I
2848-14-FW-W6 PIPE TO ELBOW 6
0.28 II Page 7 Of 15 i
t e
i
i COOPER NUCLEAR STATION l
SECOND TEN YEAR INTERVAL AUGNENTED INSERVICE INSPECTION PROGRAN REC RM.D EXANINATION SCHEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
TEK.
1993 1995 2848-14-FW-W62 ELBOW TO VALVE (REC-V-501) 8 0.322 II i
2848-14-FW-WA VALVE TO 12X10 CONC. REDUCER 10 0.365 I
2848-14-FW-WI PIPE TO VALVE (REC-MOV-MO714) 6 0.28 I
2848-14-SW-W19 PIPE TO ELBOW 6
0.28 I
2848-14-SW-W2O ELBOW TO FIPE 12 0.375 I
l 2848-14-SW-W23 TEE TO 10X12 CONC. REDUCER 12 0.375 I
f 2848-14-SW-W24 16X12 CONC. REDUCER TO ELBOW 16 0.375 I
2848-14-SW-W3 16X12 CONC. REDUCER TO TEE 12 0.575 II 2848-14-SW-W43 12X10 CONC. REDUCER TO TEE 12 0.375 I
2848-14-SW-W46 TEE TO 45 ELBOW 12 0.375 I
2848-14-SW-W47 45 EL30W TO PIPE 12 0.375 II 2848-14-SW-W49 45 ELBOW TO PIPE 12 0.375 II 2848-14-SW-W53 PIPE TO TZE 12 0.375 II 2848-14-SW-WD VALVE (REC-MOV-MV695) TO 6X4 CONC.
6 0.28 I
REDUCER 2848-14-SW-WG VALVE (REC-V-74) TO 6X4 CONC. REDUCER 4
0.237 II 2848-14-W14 TEE TO PIPE 4
0.237 S
2848-14-W15 PIPE TO ELBOW 4
0.237 S
2848-14-W28 ELBOW TO PIPE 4
0.237 S
Page 8 Of 15 i
i
J COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL AUGMENTED INSERVICE INSPECTION PROGRAM REC WELD EZAMINATION SCHEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
THK.
1993 1995 2848-14-W29 PIPE TO ELBOW 4
0.237 S
2848-14-W30 ELBOW TO PIPE 4
0.237 S
2848-14-W31 PIPE TO ELBOW 4
0.237 S
2848-14-W56 ELBOW TO PIPE 12 0.375 S
2848-14-W57 FLANGE (REC-MOV-MV712) TO PIPE 12 0.375 S
2848-14-W63 VALVE (REC-V-501) TO PIPE 8
0.322 S
2848-14-WC VALVE (REC-MOV-MV714) TO TEE 6
0.280 S
2848-14-WF PIPE TO VALVE (REC-V-74) 4 0.237 S
2848-15-FW-W15 3X1-1/2 CONC.
TO PIPE 3
0.216 II 2848-15-FW-W16 3X1-1/2 CONC. REDUCER TO PIPE 3
0.216 II 2848-15-FW-W24 ELBOW TO PIPE 3
0.216 II 2848-15-FW-W25 PIPE TO ELBOW 4
0.237 II 2848-15-FW-W3 ELBOW TO PIPE 4
0.237 II 2848-15-SW-W35 4X3 CONC. REDUCER TO PIPE 3
0.237 II 2848-15-SW-WF PIPE TO ELBOW 4
0.237 I
2848-15-W11 PIPE TO 4X3 CONC. REDUCER 4
0.237 S
2848-15-W12 4X3 CONC. REDUCER TO PIPE 3
0.216 C
2848-15-W20 PIPF TO ELBOW 3
0.216 S
Page 9 of 15
.. ~. -....
- ~. -. -.~--.
- -..~. -...~- --. -
4 COOPER NUCLEAR STATION SECOND TEN YEAK INTERVAL AUGNENTED INSERVICE INSPECTION PROGRAN REC WELD EXANIMATION SCHEDULE, REVISION 1 I
i e
i WELD ID DESCRIPTION DIA.
TEK.
1993 1995 l
2848-15-W21 ELBOW TO PIPE 3
0.216 S
i f
2848-15-W22 PIPE TO ELBOW 3
0.216 C
2848-15-W32 45 ELBOW TO PIPE 4
0.237 S
P 2848-15-W33 ELBOW TO PIPE 4
0.237 c
2848-15-W4 ELBOW TO PIPE 4
0.237 c
2848-15-W5 PIPE TO ELBOW 4
0.237 C
1 2848-15-WA ELBOW TO PIPE 4
0.237 S
i 2848-15-WC ELBOW TO VALVE (REC-V-101) 3 0.216 C
2848-16-FW-W11 PIPE TO ELBOW 3
0.216 II I
2848-16-FW-W12 ELPGW TO PIPE 3
0.216 II f
2848-16-FW-W25 TEE TO ELBOW 4
0.237 I
2848-16-FW-W26 ELBCW TO PIPE 4
0.237 I
I 2848-16-FW-W27 PIP': TO ELBOW 4
0.237 II 2848-16-FW-W28 ELBON TO PIPE 4
0.237 II i
2848-16-FW-W30 TME TO PIPE 4
0.237 I
2848-16-FW-W3A PIPE TO ELBOW 3
0.216 I
2848-16-FW-W53 PIPE TO ELBOW 3
0.216 I
i 2848-16-FW-W54 ELBOW TO PIPE 3
0.216 I
Page 10 of 15
i
\\
F
[
f, COOPER NUCLEAR STATION l
i SECOND TEN YEAR INTERVAL l
AUGNENTED INSERVICE INSPECTION PROGRAN i
REC WELD EXANIMATION SCHEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
TEK.
1993 1995 2848-16-FW-W55 PIPE TO ELBOW 3
0.216 I
2848-16-FW-W56 ELBOW TO PIPE 3
0.216 I
2848-16-FW-W57 ELBOW TO PIPE 3
0.216 I
2848-16-FW-W65 TEE TO ELBOW 4
0.237 II 3
2848-16-FW-W66 ELBOW TO PIPE 4
0.237 I
l 2848-16-FW-W67 PIPE TO ELBOW 4
0.237 I
i 2848-16-FW-W79 TEE TO 412-1/2 CONC. REDUCER 4
0.237 I
j 2848-16-FW-WD ELBOW TO PIPE 3
0.216 I
l 2848-16-FW-WF PIPE TO ELBOW 3
0.216 I
i 2848-16-FW-WI PIPE TO 4K3 CONC. REDUCER 3
0.216 I
2848-16-FW-WJ 4X2-1/2 CONC. REDUCER TO PIPE 2.5 0.203 I
2848-16-FW-WK PIPE TO ELBOW 2.5 0.203 I
2848-16-FW-WL PIPE TO ELBOW 2.5 0.203 I
2848-16-FW-WQ ELBOW TO PIPE 4
0.237 I
2848-16-W1 PIPE TO ELBOW 3
0.216 C
j 2848-16-W2 ELBOW TO ELBOW 3
0.216 s
2848-16-W3 ELBOW TO PIPE 3
0.216 S
2848-16-W32 PIPE TO PIPE 3
0.216 C
Page 11 Of 15 i
e
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL AUGMENTED INSERVICE INSPECTION PROGRAM REC WELD EXAMINATION SCHEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
THK.
1993 1995 2848-16-W4 PIPE TO ELBOW 3
0.216 C
2848-16-W68 PIPE TO ELBOW 4
0.237 C
2848-16-W69 ELBOW TO PIPE 4
0.237 S
2848-16-W70 PIPE TO ELBOW 4
0.237 S
2848-16-W71 ELBOW TO PIPE 4
0.237 S
2848-16-W72 PIPE TO ELBOW 4
0.237 C
2848-16-W73 ELBOW TO PIPE 4
0.237 C
2848-16-W74 PIPE TO ELBOW 4
0.237 s
t 2848-16-WB TEE TO PIPE 3
0.216 S
2848-16-WC ELBOW TO PIPE 3
0.216 C
2848-21-AJ VALVE (REC-V-97) TO 2-1/2x1 CONC.
2.5 0.203 II REDUCER 284 8-21-FW -W1 2-1/2X -1/2 CONC. REDUCER TO PIPE 2.5 0.203 I
2848-21-Fil-W3 PIPE TO ELBOW 2.5 0.203 I
2848-21-FW-WS ELBOW TO PIPE 2.5 0.203 II 2848-21-FW-W6 PIPE TO ELBOW 2.5 0.203 I
2848-21-FW-W7 ELBOW TO PIPE 2.5 0.203 I
2848-21-FW-WI PIPE TO VALVE (REC-V-97) 2.5 0.203 I
2848-21-FW-WJ PIPE TO VALVE (REC-V-98) 2.5 0.203 II Page 12 of 15
f-l COOPER NUCLEAR STATION
{'
SECOND TEN YEAR INTERVAL AUGNENTED INSERVICE INSPECTION PROGRAN REC WELD EXANIMATION SCHEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
TEK.
1993 1995
[
2848-21-W4 ELBOW TO PIPE 2.5 0.203 C
l 2848-21-WAA PIPE TO PIPE 2.5 0.203 S
2848-21-WAB PIPE TO PIPE 2.5 0.203 S
i 2848-22-FW-W2 PIPE TO ELBOW 3
0.216 I
2848-22-FW-W4 PIPE TO 3X1-1/2 CONC. REDUCER 3
0.216 II 2848-22-FW-W8 ELBOW TO PIPE 3
0.216 I
i 2848-22-W13 3X1-1/4 CONC. REDUCER TO TEE 3
0.237 S
i 2848-22-W14 TEE TO BRANCH 3
0.216 C
2848-22-W15 PIPE TO ELBCW 3
0.216 S
i 2848-22-W16 ELBOW TO PIPE 3
0.216 C
2848-22-W17 PIPE TO TEE 3
0.216 S
j 2848-22-W18 ELBOW TO PIPE 3
0.216 C
l 2848-22-W19 PIPE TO ELBOW 3
0.216 S
2848-22-W20A VALVE (REC-V-104) TO PIPE 3
0.216 C
i 2848-22-W20 PIPE TO VALVE (REC-V-104) 3 0.216 C
2848-22-W21 ELBOW TO PIPE 3
0.216 C
2848-22-WB PIPE TO ELBOW 3
0.216 C
2848-22SFW-W5 PIPE TO 3X1-1/2 CONC. REDUCER 3
0.216 I
Page 13 of 15 l
r f
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL i
AUGNENTED INSERVICE INSPECTION PROGRAN REC NELD EXANINATION SCHEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
TEK.
1993 1995 2848-50-FW-WH PIPE TO ELBOW 4
0.237 I
2848-50-FW-WI ELBOW TO VALVE (SW-MOV-MV889) 4 0.237 I
2848-50-WF TEE TO PIPE 4
0.237 C
2848-50-WG PIPE TO ELBOW 4
0.237 C
2848-50-WJ ELBOW TO PIPE 4
0.237 c
2848-50-WK PIPE TO ELBOW 4
0.237 s
2848-50-WL ELBOW TO PIPE 4
0.237 C
2848-50-WM PIPE TO VALVE (SW-MOV-MV888) 4 0.237 S
2848-51-WJA PIPE TO PIPE 8
0.322 S
2848-51-WU PIPE TO VALVE (REC-MOV-MV1329) 8 0.322 S
2848-51-WVV PIPE TO ELBOW 8
0.322 S
2848-51-WY ELBOW TO PIPE 8
0.322 S
2848-54-W1 2-1/2X1 CONC. REDUCER TO FLANGE 2.5 0.203 C
2848-54-W2 PIPE TO ELBOW 2.5 0.203 c
2848-54-W20 PIPE TO FLANGE (FC-R-1F) 2.5 0.203 c
2848-54-W21 PIPE TO PIPE 2.5 0.203 C
2848-54-W3 ELBOW TO PIPE 2.5 0.203 c
2848-55-W1 PIPE TO VALVE (REC-V-96) 3 0.216 C
Page 14 of 15
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL AUGNERITED INSERVICE INSPECTION PROGRAN REC WELD EXANINATION SCHEDULE, REVISION 1 WELD ID DESCRIPTION DIA.
THK.
1993 1995 2848-55-W14 3X1 CONC. REDUCER TO ELBOW 3
0.216 C
294o-55-W16 ELBOW TO PIPE 3
0.216 C
2848-55-W2 PIPE TO ELBOW 3
0.216 C
1 2848-55-W25 PIPE TO FLANGE (FC-R-IE) 3 0.216 C
2848-55-W3 ELBOW TO PIPE 3
0.216 C
2848-56-W13 3X1-1/4 CONC. REDUCER TO PIPE 3
0.216 C
2848-56-W14 PIPE TO ELBOW 3
0.216 C
2848-56-W15 ELBOW TO PIPE 3
0.216 C
2848-56-W16 PIPE TO FLANGE 3
0.216 C
NOTES:
"I" DENOTES PHASE 1 EXAMINATION "II" DENOTES PHASE 2 EXAMINATION (SAMPLE EXPANSION)
"S" DENOTES SCHEDULED EXAMINATION "C"
DENOTES CONTINGENT EXAMINATION (SAMPLE EXPANSION) i f
I Page 15 of 15 l
t 1
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM REVISION 4.1 AUGMENTED INSERVICE INSPECTIONS INSTRUMENT NOEELE SAFE ENDS Augmented supplemental volumetric examinations of the entire instrument nousle safe end for nossles N10, N11A/B, N12A/B, and N16A/B will be performed when flaws are detected during the scheduled surface examination in accordance with the ISI program.
The surface examination will be extended to cover the entire instument nousle safe end.
These examinations will begin in 1995 as recommended in GE SIL No. 571.
J Page 1 of 1
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM REVISION 4.1 RELIEF REQUESTS The following is a list of Relief Requests:
Relief Request Descriotion Mump _g.E RI-01 Deleted, See Note 1 RI-02 Deleted, See Note 2 RI-03 Volumetric Examination of Nozzle Inner Radii (Reformatted, see Note 3)
RI-04 Deleted, See Note 1 RI-05 Inaccessible RHR Heat Exchang'er Welds (Revised, see Note 4)
RI-06 Inaccessible Reactor Pressure Vessel Welds (Revised, see Note 5 and 9)
RI-07 Inspection of Reactor Vessel Support Skirt to Reactor vessel Bottom Head Wald (See Note 6)
RI-08 10-Year Hvdrostatic Pressure Test Requirements for Class 1, 2 and 3 Systems (See Note 8)
RI-09 Pressure Testing of Non-safety System Process Piping In Containment Penetrations (See Note 8)
RI-10 Visual Examination (VT-2) In Redundant Systems for Buried Components (See Note 8)
RI-11 Visual Examination (VT-2) of Relief Valve Piping Which Discharge into the Suppression Pool (See Note 8)
RI-12 Examination of Class 1 and 2 Longitudinal Seams (See Note 8)
RI-13 ISI of Snubbers included in CNS Technical Specifications (See Note 10)
RI-14 Alternative Rules for Selection and Examination of Class 1, 2 and 3 Integrally Welded Attachments (See Note 8)
RI-15 Inaccessible CRD Housing Welds (See Note 8)
RI-16 Examination of Pump Casing and Valve Body Internal Surfaces (See Note 8)
RI-17 Deleted, See Note 7 Page 1 of 3
_. ~
- ~..
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM REVISION 4.1 RELIEF REQUESTS Relief Request Descrintion Number RI-18 Integrally Welded Attachments (See Note 8)
RI-19 Exemption From Pressure Testing Reactor Vessel Head Flange Seal Leak Detection System (See Note 8)
RI-20 Dissimilar Metal Butt Welds in Piping (See Note 9)
RI-21 Full Penetration Welds of Nozzles in Vessels (See Note 9)
RI-22 Branch Pipe Connection Welds (See Note 9)
RI-23 Submerged RCIC Piping Welds (See Note 9)
NOTE 1:
Relief Requests RI-01 and RI-04 have been deleted.
Alternate welds have been selected in accordance with 10CFR50. 55a (b) (2 ) (ii) and Code Case N-408-2.
NOTE 2:
Relief Request RI-02, "ASME Category C-F, RHR Drywell Spray Internal to Drywell", was not granted by the NRC and thus, removed per the May, 1987, addenda.
NOTE 3:
Relief Request RI-03, " Volumetric Examination of Nossle Inner Radii", was reformatted.
The basis for the relief and the alternate examination proposed are unchanged.
NOTE 4:
Relief Request RI-05, " Inaccessible RER Heat Exchanger Welds", has been revised to correct an error in the weld number.
The basis for the relief and the alternate examination proposed are unchanged.
NOTE 5 Relief Request RI-06, " Inaccessible Reactor Pressure
~
Vessel Welds", has been revised to incorporate NRC Safety Evaluation dated January 27, 1986.
Note that this relief request is still applicable per 10CFR50.55 a (g) 6 ( A) (3) (iv) because the augmented examinations of the RPV have been scheduled for the first period of the third inspection interval.
NOTE 6:
Relief Request RI-07, " Inspection of Reactor Vessel Support Skirt to Reactor Vessel Bottom Head Weld", was approved by the NRC on August 31, 1995.
Page 2 of 3
COOPER NUCLEAR STATION SECOND TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAN REVISION 4.1 RELIEF REQUESTS NOTE 7:
Relief Request RI-17 was withdrawn by CNS on October 27, 1995.
NOTE 8:
Relief Requests RI-08 thru RI-12, RI-14 thru RI-16, RI-18, and RI-19, were approved by the NRC on December 13, 1995.
NOTE 9:
The necessity for Relief Requests RI-20, 21, 22 and 23 was identified during the last refueling outage of the Escond Ten-Year Interval.
Similarily, the need to revise RI-06 to add the access restrictions for the vessel bottom head circumferential weld and and shell to flange circumferential weld was identified during RFO-16.
NOTE 10:
RI-13 was submitted to the NRC on June 21, 1995.
4 Page 3 of 3
COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-06 REVISION 2 Code Class:
1
Subject:
Inaccessible Reactor Pressure Vessel Welds.
Components:
Category B-A circumferential welds in vessels.
Code Requirements:
Reference; ASME Section XI, 1980 Edition with the Winter 1981 Addenda Table IWB-2500-1 requires a volumetric examination of the following circumferential welds:
HMB-BB-1 HMB-BB-2 HMB-BB-3 HMB-BB-4 HMB-BB-5 HMB-BB-6 HMC-BB-1 VLA-BA-1 VLA-BA-2 VLA-BA-3 VLB-BA-1 VLB-BA-2 VLB-BA-3 VCB-BA-2 VCB-BC-5-1 VCB-BC-5-2 VCB-BC-5-3 Basis For Relief:
The Cooper Nuclear Station construction permit was issued before the effective date of implementation for ASME Section XI and thus the plant was not designed to meet the requirements of inservice inspection; therefore, 100%
compliance is not feasible or practical.
Access to the reactor vessel beltline region is not possible.
The reactor vessel is insulated with permanent reflective insulation and surrounded by a concrete biological shield.
The annular space between the inside diameter of the insulation and the outside diameter of the reactor vessel is a nominal 2 inches.
There is no working space to remove the insulation panels from the vessel, which precludes both direct and remote examination of the outside
{
- surface, i
The interior surface is clad and the arrangement of the vessel internals, shroud and jet pumps make an internal volumetric examination of these welds impracticable for a
meaningful examination using the technology available at the beginning of the interval.
Parts of longitudinal seams VLA-BA-1, 2,
and 3, however, appear.to be accessible from openings around the recirculation-riser nozzles N2A, N2E, and N2H respectively.
Again these seams are not 100% accessible.
The scanning surface would require a minimum of 17 inches from the weld.
This surface area is only available for a few inches - closest to a nozzle.
Page 1 of 2
. _ ~
COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-06 REVISION 2 Access to the bottom head circumferential weld HMC-BB-1 is limited due to the proximity of the vessel skirt.
The configuration limits scanning with the 60* probe.
The total composite coverage is approximately 86%.
I Access to the shell to flange circumferential weld VCB-BC-5-1,
-2,
-3, is limited due to the flange configuration and the proximity of the vessel thermocouples.
The configuration limits scanning with the 0*, 45*, and 60* probes.
The thermocouples limit scanning with both the 45* and 60* probes. The total composite coverage is approximately 74%.
Proposed Alternative In lieu of performing the Code required examinations, CNS proposes:
(a)
When the recirculation riser nozzle to vessel welds (Category B-D) are examined, a best effort examination of longitudinal shell welds in the beltline region, VLA-BA-1, 2,
and 3, shall be performed; (b)
The accessible portions of the bottom head meridional welds,
.HMB-BB-1 through 6, will be examined on a best effort basis when the vessel support skirt weld is examined; (c)
The beltline region weld areas shall be visually examined from the vessel interior during the Category B-N-1 and B-N-2 examinations; (d)
The areas of the lower head and the shield annulus below the vessel shall be visually inspected during a system hydrostatic test; (e)
The accessible portions of the bottom head circumferential weld, VCB-BB-1, and 150 inches of longitudinal seam shell weld above the shield wall shall be examined; (f)
The accessible portions of the bottom head circumferential weld, HMC-BB-1, shall be examined; and (g)
The accessible portions of the shell to flange weld shall be examined.
Page 2 of 2
COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-07 REVISION 2 Code Class 1
Subject Inspection of Reactor Vessel Support Skirt to Reactor Vessel Bottom Head Weld.
Component:
Category B-H Integral Attachment Weld Code Recuirements Reference; ASME Section XI, 1980 Edition with the Winter 1981 Addenda Table IWB-2500-1 requires a surface examination to be performed on areas A-B and C-D of Figure IWB-2500-13.
Basis for Relief The reactor vessel bottom head was constructed with a weld build-up around the circumference of the head that was designed as the attachment point for the reactor vessel support skirt (Figure RI-07-1).
This weld build-up was machined and heat treated along with the reactor vessel.
The support skirt is attached to the weld build-up by means of a full penetration butt weld.
As can be seen in Figure RI-07-2, the design of this weld is such that the surface examination requirements of Figure IWB-2500-13 (Area C-D) can not be met due to lack of accescibility.
The interior surface area is not accessible due to the configuration of the vessel skirt, lower vessel head insulation, close proximity of CRD housings, and the lack of adequate skirt access manways and manueuverability space.
There is a severe angle between the vessel bottom head and the vessel skirt which physically prohibits access to the root area of the weld.
However, a partial coverage volumetric examination of this volume
~
can be performed from one side (A-B) of the weld.
Based upon a review of the fabrication. drawings, it is estimated that an ultrasonic examination can be performed on volume A-B-C-D, as shown on Figure RI-07-2, using a O degree longitudinal wave search unit, 45 degree shear wave search unit, and a 60 degree shear wave search unit.
Due to the configuration, the scanning will be performed in one direction only.
Performance of this partial coverage volumetric examination, coupled with a surface examination on the B-C side of the weld, will provide adequate assurance of the structural integrity of the weld.
Page 1 of 4
COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-07 REVISION 2 Basis for Relief (continued):
A fracture mechanics evaluation has been performed for the support skirt to lower RPV head weld.
The results of the evaluation indicate that, for a surface flaw, growth rate is extremely small, and such growth would provide negligible adverse impact upon the integrity of the weld for the remainder of plant life.
Proposed Alternative:
As an alternate examination, CNS will perform a surface examination on the accessible side of the subject weld (area A-B),
and an ultrasonic examination of area A-B-C-D, as shown on Figure RI-07-2, each inspection interval.
I l
l 1
Page 2 of 4
COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-07 REVISION 2 FIGURE RI-07-1 REACTOR VESSEL BOTTOM HEAD WELD BUILD-UP
- SHELL RING NO. 1 ELEY 110.3/16' m
VCB-88-1 i
x I
s 8
I UPPER
~
- SIDE SE6HENT s
HMC C[
l N
LOVER l
SIDE SEGHENT CbSS S
T KNilCKLE i
/
i l
SKIRT KNUCLE TO HHD-80-1 SIDE PLATE-GKIRT RING WELD gT
-SKIRT RING H C-Cl-1 l
///
HNC-C1-2 HNC-C1-3 f////////?
00HE Page 3 of 4
I l
l COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-07 i
REVISION 2 I
FIGURE RI-07-2 REACTOR VESSEL SUPPORT SKIRT ATTACHMENT WELD 1
HNC-80-1 g
UPPER 15' v
$.B SIDE SEGHENT L0ilER
- r A-533 BR 8
/
'O fb!h3GRB is 88 1 5/15' CLAD g *4 g
i CLASS 1 SEE DETAIL 'B' 0,
7
.j0 4
d SKIRT KNUCKLE A-588 A
CLASS 2 2.5' R l
^
c o
u2.
HNC-Cl-1 HNC-Cl-2 HNC-Cl-3 C
f 2.5' A O
SKIRT RIHs DETAIL "B" V
SEE FA-2-1 t
l
\\
l
. N Page 4 of 4
COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-20 REVISION 0 code class:
1 subjects Dissimilar Metal Butt Welds in Piping Components:
Category B-F, Weld RVD-BF-14.
Code Requirements:
Reference:
ASME Section XI, 1980 Edition with the Winter 1981 Addenda Table IWB-2500-1 requires a surface examination to be performed on dissimilar metal butt welds in piping s 4 inches defined by the areas in Figure IWB-2500-8.
]Utsis for Relief:
A rigid support is located adjacent to this 2 inch NPS stainless steel to carbon steel butt weld in the reactor drain line.
The design of the support does not permit disassembly without cutting the support members.
The support limits access to one side of the weld crown such that only
% inch of the adjacent base metal can be examined.
The total surface examined is approximately 83%.
ProDosed AlternatiVG:
)
In lieu of performing the Code required examinations, CNS proposes to examine the accessible portions of weld RVD-BF-14.
Page 1 of 1
1 COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-21 REVISION O l
Code Class:
1
Subject:
Full Penetration Welds of Nozzles in Vessels Components:
Category B-D, Reactor Vessel Nozzle-to-Vessel Welds Code Recuirements:
Reference:
ASME Section XI, 1980 Edition with the Winter 1981 Addenda Table IWB-2500-1 requires a volumetric examination of the following reactor vessel nozzle-to-vessel welds:
N1A, N1B, N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, N2K, N3A, N3B, N3C, N3D, N4A, N4B, N4C, N4D, NSA, N5B, N6A, N6B, N7, N8A, N8B, and N9.
Basis For Relief:
The Cooper Nuclear Station construction permit was issued before the effective date of implementation for ASME Section XI and thus the plant was not designed to meet the requirements of inservice l
inspection; therefore, 100%
compliance is not feasible or practicable.
The configuration of the nozzles, the design of the vessel insulation support rings and the nozzle access hatches, and interferences from thermocouple pads, instrument
- lines, etc.
prevents 100% examination of the required weld volumes.
Alternate angles were used to the extent practicable to increase the volume g
examined.
The extent of the nozzle restrictions and the total j
volume examined is summarized on table RI-21-1.
Proposed Alternative l
l In lieu of performing the Code required examinations, CNS proposes to examine the accessible portions of reactor vessel nozzle-to-
~
vessel welds.
i Page 1 of 2
COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-21
[
REVISION O i
Table RI-21-1 t
?
Nozzle Nozzle Access Restrictions l
Number Description Examined N1A,B Recirculation Nozzle configuration, and insulation support frame 32%
Inlet i
t N2A-H, Recirculation Nozzle configuration, and insulation support frame 40%
i J&K Outlet i
N3A-D Main Steam Nozzle configuration 35%
I s
N4A&C Feedwater Nozzle configuration, insulation support frame-27%
thermocouple pads, and Instrument Nozzles N11A&B i
N4B&D Feedwater Nozzle configuration, insulation support frame, 31%
and thermocouple pads NSA,B Core Spray Nozzle configuration, insulation support frame, 31%
j and thermocouple pads N6A,B Top Head Spray Nozzle configuration 58%
i N7 Top Head Vent Nozzle configuration 30%
j N8A,B Jet Pump Nozzle configuration, and insulation support frame 76%
[
Instrumentation l
N9 CRD Return Nozzle configuration, and insulation support frame 70%
i I
Nozzle and Inner Radius l
Page 2 of 2 i
h
- - _ ~. _. _
COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-22 REVISION 0 Code Class:
1 Subjects Branch Pipe Connection Welds Components:
Category B-J, Welds FWA-BJ-81, RAS-BJ-10, and RBS-BJ-6A Code Recuirements:
Reference:
ASME Section XI, 1980 Edition with the Winter 1981 Addenda s
Table IWB-2500-1 requires a surface and volumetric examination to be performed on branch pipe connection welds 2: 4 inches defined by the areas in Figure IWB-2500-10.
Basis for Relief The configuration of the 8 inch branch weldolet to 18 inch pipe weld FWA-BJ-81, prevents complete ultrasonic examination of the code required volume.
The configuration of the weldolet prevents examination from the branch side of the weld and limits the examination to one direction from the other side.
No supplemental examinations to increase the coverage were possible.
The total volume examined is approximately 82%.
The configuration of the 6 inch branch to 20 inch elbow weld RAS-BJ-10, prevents complete ultrasonic examination of the code required volume.
The branch connection is welded to the extrado of the elbow.
The angle between the branch connection and the elbow changes as the probe is scanned circumferentially around the branch.
Where the angle is most acute, the sound can not reach the root of the weld and the configuration of the branch prohibits the use of larger angles.
Supplemental examinations were performed to increase the coverage.
The total volume examined is approximately 82%.
The configuration of the 4 inch branch weldolet to 28 inch pipe weld RBS-BJ-6A, prevents complete ultrasonic e:mmination of the code required volume.
The configuration of the weldolet prevents examination from the branch side of the weld and limits the examination to one direction from the other side.
No supplemental examinations to increase the coverage were possible.
The total volume examined is approximately 67%.
Page 1 of 2
COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-22 REVISION O Proposed Alternative In lieu of performing the Code required examinations, CNS proposes to examine the accessible portions of branch connection welds FWA-BJ-81, RAS-BJ-10, and RBS-BJ-6A.
e Page 2 of 2 1
\\.
i COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NUMBER RI-23 REVISION O Code Class:
2
Subject:
Submerged RCIC Pipe Welds Components:
Category C-F, Welds RWA-CF-10, RWA-CF-11, and RWA-CF-12 Code Reauirements:
Reference:
ASME Section XI, 1980 Edition with the Winter 1981 Addenda and Code Case N-408-2.
Table 2 of Code Case N-408-2 requires a surface and volumetric examination to be performed on circumferential pipe welds 2 4 I
inches defined by the areas in Figure IWC-2500-7.
Basis for Relief:
The RCIC suction strainer is 6 inch NPS Schedule 80.
The strainer is located in the Torus and is submerged in the suppression pool.
The welds on the strainer are inaccessible during a normal refueling outage because the Torus is not normally drained.
RCIC is normally supplied from the emergency condensate storage tanks.
The suppression pool is an alternate source of water.
The maximum pressure the suction piping would experience in a design basis event is 58 psig.
Suppression pool temperature would not exceed 200*F.
Since the suction piping in the Torus is an alternate supply for RCIC, operates at less than 275 psig and less than or equal to 200*F, and is not accessible during a normal refueling outage, the submerged welds on the suction piping should be exempt from NDE.
Pronosed Alternative In lieu of performing the Code required examinations, CNS proposes to examine the accessible welds on the RCIC suction piping.
Page 1 of 1 L-.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _