IR 05000456/1985035
| ML20133C851 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/31/1985 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20133C820 | List: |
| References | |
| 50-456-85-35, 50-457-85-34, IEB-82-02, IEB-82-2, NUDOCS 8508070161 | |
| Download: ML20133C851 (11) | |
Text
.
.
.
.
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report Nos. 50-456/85035(DRS);50-457/85034(DRS)
i Docket Nos. 50-456; 50-457 Licenses No. CPPR-132; CPPR-133
'
Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Braidwood Station, Units 1 and 2 Inspection At: Braidwood Site, Braidwood, Illinois Inspection Conducted: July 15-18, 1985 N
QJ Inspector:
.
. Ward f^ <
-f fat! 64
,
Date
[*
1 3d6~
Approved By:
. H. Danielson, Chief Materials and Processes Section Date Inspection Summary Inspection on July 15-18, 1985 (Report Nos. 50-456/85035(DRS); 50-457/80534(DRS))
Areas Inspected: Routine, unannounced safety inspection to review actions on a previous inspection finding and an IE Bulletin; observe installation of reactor coolant pressure boundary piping; visually examine (VT) and review radiographs and reports on piping shop and field welds. The inspection involved a total of 32 inspector-hours by one NRC inspector.
Results: No violations or deviations were identified.
.
i i
8508070161 850731 F
gDR ADOCK 05000456 PDR
.
L
.
.
.
.
DETAILS 1.
Persons Contacted Commonwealth Edison Company (CECO)
- L. Kline, Project Licensing and Compliance (PLC) Supervisor
- M. Gorski, Engineer
.
- P. Barnes, Licensing Engineer
- D. Cecchett, Proje Licensing and Compliance Engineer
- K. Miller, QA Iny.cor R. Gardner, PSI Coordinator, Level III T. D' Antonio, Quality Assurance Level III Phillip Getschow Company (PGCo)
5. Batty, Supervisor The inspector also contacted and interviewed other licensee and contractor personnel.
- Denotes those present at exit interview.
2.
Licensee Action on Previous Inspection Finding (Closed) Ncnccmpliance (456/84-05-01; 457/84-05-01). The procedural and issuance controls for hanger drawings were deficient; i.e., ECN and FCN were not posted against site QA drawings. The NRC inspector reviewed the licensee's final response, dated August 10, 1984, a QA site quality instruction, data on a training session on this subject, and other related documentation.
Subsequent to the NRC's finding, Commonwealth Edison Site Quality Assurance placed an immediate " Hold Point" on the issuance of print copies from Quality Assurance's aperture cards.
The control of aperture cards in the Site Quality Assur.ince Office was outlined in Site Quality Instruction (SQI) #7. Because the handling of the prints for the NRC may not have been in strict accordance with SQI
- 7, thIS aperture card control instruction SQI was revised to assure greater control of prints.
The NRC inspector agreed with the licensee's corrective action and considers this item closed.
.-
o
.
'
.
.
.
.
3.
Licensee Action on IE Bulletin (IEB)
(Closed) IE Bulletin 82-02 (456/82-02-BB; 457/82-02-BB): Degradation of threaded fasteners in the reactor coolant pressure boundary of BWR plants, issued to PWR's for information only. The NRC inspector reviewed related documents and verified that the licensee management investigated the IEB concerns and determined that the system in place onsite adequately addresses the bulletin. The NRC inspector agreed with the licensee actions and considered this item closed.
.
4.
Reactor Coolant Loop Piping - Special Welding Applications The NRC inspector selected the following welds and determined that the weld repairs were conducted in accordance with the applicable requirements and specified procedures:
Weld No.
Weld No.
RC-3-FW13A RC-9-FW2 RC-4-FW2B RC-4-FW5 RC-4-FW1A RC-3-FW2 The inspector observed welding, reviewed repair welding procedures, and welder performance qualifications and determined that they were in accordance with the applicable Code requirements. The NRC inspector also reviewed field fabrication process and data sheets, NDE inspection reports, weld rod withdrawn slips and other related documents.
No violations or deviatioris were identified.
5.
Reactor Coolant Pressure Bcundary Piping - Work Activities All reactor coolant pressure boundary piping installation is complete.
The hRC inspector determined that the piping runs were installed as required by the applicable specification and Drawing Nos. 1C-SI-8-1 and IC-SI-8-3P.
The NRC inspector also reviewed inspection records of the following lines and determined that the required scope of the inspection was performed and recorded and that the records confirm that specifications and installation procedures were met:
Line Number Line Number ISIO9AB-10 ISIO5DB-6 IS109BB-10 ISIO6A-4
.
t'
-.
-
- _ _ _ -
'.
.
.
.
The inspection records reviewed included drawings, field fabrication process data sheets, weld rod withdrawn slips, NDE records and other related documentation including audits.
No violations or deviations were identified.
6.
Visual Examination of Reactor Coolant Loop Piping and Other Safety Related Piping Welds The NRC inspector selected the following 44 completed welds and determined by visual examination that the welds conformed to applicable Codes, standards, construction specifications and welding procedure requirements, including size, length and appearance:
Reactor Coolant Loop Piping PG-15AP, Loop - 2 FW-5, Loop - 2 PG-14AP, Loop - 2 FW-6, Loop - 2 SW-3, Loop - 2 FW-5A, Loop - 3 SW-4, Loop - 2 PG-7A, Loop - 3 FW-15, Loop - 2 FW-7, Loop - 3
-
SW-2, Loop - 2 FW-8, Loop - 3 FW-14, Loop - 2 SW-7, Loop - 3 PG-13B, Loop - 2 SW-4, Loop - 3 FW-13, Loop - 2 SW-6, Loop - 3 PG-13A, Loop - 2 SW-2, Loop - 3 FW-12, Loop - 2 PG-5C, Loop - 3 FW-11, Loop - 2 SW-3, Loop - 3 Safety-Related Piping Welds SW-3, IA-AF-13 SW-5, IA-AF-13 SW-4, 1A-AF-13 SW-6, IA-AF-13 PG-1A, 1A-AF-13 FW-1, 1A-AF-13
,
SW-2, 1A-AF-13 SW-3, IA-AF-13
'
FW-6, IA-AF-13 FW-7, 1A-AF-13 FW-1, IA-AF-13 SW-7, IA-AF-13 FW-3, 1A-AF-13 FW-8, 1A-AF-13 FW-4, 1A-AF-13 FW-5-1, 1A-AF-13 FW-9-1, 1A-AF-13 FW-10, 1A-AF-13 FW-15, 1A-AF-13 FW-16, 1A-AF-13
!
l The NRC inspector also reviewed quality records for the following welds
'
and determined that the records reflected adequate weld quality and that the weld history records were adequate:
l Reactor Coolant Loop Piping Reactor Coolant Loop Piping RC-1-FW1B RC-1-FWC RC-1-FW1A RC-1-FW2 RC-1-FW1 RC-1-FW3
,
m
.-
--_u-.,.
.
.
-
-
,
- - -. - _ -, -
_. - -
--
--_
'
.
.
.
.
Safety-Related Piping Welds Safety-Related Piping Welds AF-13-FW-10 AF-13-FW-13 AF-13-FW-11 AF-13-FW-14-1 AF-13-FW-12 AF-13-FW-15-1 7.
Visual Examination of Pipe Welds The NRC inspector visually examined the following selected piping welds and other pipe welds in the area in accordance with ASME Section III 1974, Sunser 1975 Addenda and found them to be acceptable:
1A-CC-2, FW-11 1A-CC-2, FW-22 1A-CC-2, FW-12 1A-CC-2, FW-21 1A-CC-2, PG-9A 1A-CC-2, FW-9 1A-CC-2, PG-9B 1A-CC-2, FW-10 1A-CC-2, PG-23C 1A-CC-2, FW-23 1A-CC-2, FW-20 1A-CC-2, PG-23D
.1A-CC-2, PG-23B 1A-CC-2, PG-200 1A-CC-2, FW-8 1A-CC-2, PG-20E 1A-CC-2, PG-20B1 1A-CC-2, FW-14 1A-CC-2, FW-17 1A-CC-2, PG-25A 1A-CC-2, FW-1 1A-CC-2, FW-24 1A-CC-2, FW-13 1A-CC-2, FW-16 1A-CC-2, PG-18A 1A-CC-2, PG-13A 1A-CC-2, FW-19 1A-CC-2, PG-19A 1A-CC-2, PG-13B 1A-CC-2, FW-7 1A-CC-2, FW-27 1A-CC-2, PG-24A 1A-CC-2, PG-25B 1A-CC-2, FW-25 1A-CC-2, PG-25C 1A-CC-2, PG-25D 1A-CC-2, PG-25G 1A-CC-2, FW-25E 1A-CC-2, PG-18B 1A-CC-2, FW-181 1A-CC-2. FW-6 1A-CC-2, PG-5A 1A-CC-2, PG-6A 1A-CC-2, FW-5 1A-CC-2, FW-4 1A-CC-2, FW-3 1A-CC-2, FW-1 1A-CC-2, FW-2 1A-CC-2, FW-15 1A-CC-2, FW-26 1A-CC-1, SW-2 1A-CC-1, SW-3 1A-CC-1, PG-1 1A-CC-1, PG-24A 1A-CC-1, PG-25A 1A-CC-1, PG-25B1 1A-CC-1, FW-25-2 1A-CC-1, PG-24AA 1A-CC-1, FW-2 1A-CC-1, SW-1 1A-CC-1, SW-9 1A-CC-1, SW-5 1A-CC-1, SW-6 1A-CC-1, PG-1A 1A-CC-2, FW-1 1A-CC-2, FW-2 1A-CC-2, FW-15 1A-CC-2, FW-26 IA-CC-1, SW-2 1A-CC-1, SW-3
,
'
1A-CC-1, PG-25A 1A-CC-1, PG-25B1 1A-CC-1, FW-25-2 1A-CC-1, PG-24AA 1A-CC-1, FW-2 1A-CC-1, SW-1
.
$
..
.
.
.
.
IA-CC-1, SW-9 1A-CC-1, SW-5 1A-CC-1, SW-6 1A-CC-1, PG-1A 1A-CC-1, PG-1B 1A-CC-1, SW-1 1A-CC-1, SW-4 1A-CC-1, FW-24 1A-CC-1, PG-22B 1A-CC-1, FW-3 1A-CC-1, SW-7 1A-CC-1, FW-1 1A-CC-1, SW-8 1A-CC-1, PG-3A 1A-CC-1, FW-23 1A-CC-1, FW-18 1A-CC-1, PG-22A 1A-CC-1, FW-19 1A-CC-1, FW-22 1A-CC-1, FW-20 1A-CC-1, FW-21 1A-CC-1, PG-13B 1A-CC-1, PG-13A 1A-CC-1, FW-4 1A-CC-1, FW-17 1A-CC-1, FW-16 1A-CC-1, PG-13E 1A-CC-1, PG-12D 1A-CC-1, PG-13D 1A-CC-1, FW-13 1A-CC-1, PG-13C 1A-CC-1, FW-12 1A-CC-1, PG-12A 1A-CC-1, PG-12C 1A-CC-1, PG-78-1 1A-CC-1, PG-6A 1A-CC-1, PG-7C-1 1A-CC-1, FW-7 1A-CC-1, SW-10 1A-CC-1, FW-8 1A-CC-1, FW-5 1A-CC-1, PG-8B 1A-CC-1, PG-8A 1A-CC-1, FW-9 1A-CC-1, SW-4 1A-CC-1, FW-24 1A-CC-1, PG-22B 1A-CC-1, FW-3 1A-CC-1, SW-7 1A-CC-1, FW-1 1A-CC-1, SW-8 1A-CC-1, PG-3A 1A-CC-1, FW-23 1A-CC-1, FW-18 1A-CC-1, PG-22A 1A-CC-1, FW-19 1A-CC-1, FW-22 1A-CC-1, FW-20 1A-CC-1, FW-21 1A-CC-1, PG-13B 1A-CC-1, PG-13A 1A-CC-1, FW-4 1A-CC-1, FW-17 1A-CC-1, FW-16 1A-CC-1, PG-13E 1A-CC-1, PG-120 1A-CC-1, PG-13D 1A-CC-1, FW-13 1A-CC-1, PG-13C 1A-CC-1, FW-12 1A-CC-1, PG-12A 1A-CC-1, PG-12C 1A-CC-1, PG-7B-1 1A-CC-1, PG-6A 1A-CC-1, PG-7C-1 1A-CC-1, FW-7 1A-CC-1, SW-10 1A-CC-1, FW-8 1A-CC-1, FW-5 1A-CC-1, PG-8B 1A-CC-1, PG-8A 1A-CC-1, FW-9 1A-CC-1, FW-10 1A-CC-1, FW-11 1A-CC-1, FW-17 1A-CC-1, FW-15 1A-CC-1, FW-14 1A-CC-1, FW-16 1A-CC-3, FW-6 1A-CC-3, FW-26-1
,
1A-CC-3, SW-1 1A-CC-3, SW-2 1A-CC-3, SW-8 1A-CC-3, SW-3 1A-CC-3, SW-9 1A-CC-3, PG-21A
.
.
.
.
.
.
1A-CC-3, FW-21 1A-CC-3, PG-17D 1A-CC-3, SW-1 1A-CC-3, PG-17A 1A-CC-3, PG-17C 1A-CC-3, PG-17B 1A-CC-3, FW-4 1A-CC-3, SW-4 1A-CC-3, SW-5 1A-CC-3, PG-21B 1A-CC-3, SW-7 1A-CC-3, SW-6 1A-CC-3, FW-3 1A-CC-3, FW-5 1A-CC-3, PG-3B 1A-CC-3, PG-3A 1A-CC-3, FW-14 1A-CC-3, FW-15 1A-CC-3, FW-28 1A-CC-3, PG-15A 1A-CC-3, FW-16 1A-CC-3, FW-18 1A-CC-3, FW-17 1A-CC-3, FW-20 1A-CC-3, PG-10C 1A-CC-3, FW-11 1A-CC-3, PG-10D 1A-CC-3, FW-13 1A-CC-3, FW-12 1A-CC-3, FW-22-1 1A-CC-3, FW-19 1A-CC-3, PG-228 1A-CC-3, FW-9 1A-CC-3, PG-10A 1A-CC-3, FW-10 1A-CC-3, PG-10AA 1A-CC-3, PG-7B 1A-CC-3, PG-10B 1A-CC-3, FW-11 1A-CC-3, PG-10AB 1A-CC-3, PG-10C 1A-CC-3, PG-10D 1A-CC-3, PG-5A 1A-CC-3, PG-22F 1A-CC-3, PG-22B 1A-CC-3, PG-22G 1A-CC-3, PG-22C 1A-CC-3, PG-22D 1A-CC-3, FW-2 1A-CC-3, FW-23-1 1A-CC-3, FW-1 1A-CC-3, PG-7C 1A-CC-3, FW-27 1A-CC-3, FW-8 1A-CC-3, PG-7B 1A-CC-3, FW-25-1 1A-CC-3, FW-24-1 1A-CC-3, PG-25A 1A-CC-3, FW-8 1A-CC-3, PG-24A M2537A, FW-9 M2537A, FW-4 M2537A, FW-1A M2537A, FW-6A M2537A, FW-1B M2537A, FW-6 M2537A, FW-1 M2537A, FW-6B M2537A, FW-2 M2537A, FW-3 M2537A, FW-8 M2537A, FW-7 No violations or deviations were identified.
8.
Review of Radiographs and Reports a.
Field Welds
-
The NRC inspector reviewed radiographs and reports of the following field pipe welds that were radiographed by Pittsburgh Testing Laboratory (PTL) in accordance with ASME Section III 1974 Edition, Summer 1975 Addenda and found them to be acceptable:
'
m '
.
.
.
.
-System Weld No.
Diameter Thickness Date RT AF-28 FW-12A 4"
0.337" 12/29/81 AF-28 FW-1 4"
0.438" 09/25/81
AF-27 FW-14A 4"
0.337" 12/09/81 CC-52 FW-10 3"
0.216" 10/28/82 CC-42 FW-13-1 3"
0.216" 12/03/81 CC-42 FW-16 3"
0.216" 09/12/79 CC-42 FW-6 3"
0.216" 05/12/80 CS-6 FW-11 10" 0.365" 01/12/79 CS-8 FW-5 10" 0.365" 11/12/80 CS-9 FW-28 14" 0.375" 12/02/80 CV-3 FW-10AA 4"
0.237" 10/07/82 CV-3 FW-1B 8"
0.322" 10/01/81 CV-2 FW-8 3"
0.438" 01/22/81 FW-39 FW-4-1 6"
0.562" 12/09/83 FW-28 FW-10 16" 0.843" 02/09/84 FW-27 FW-5 16" 0.843" 12/08/84 FW-20 FW-55A 24" 1.812" 09/28/84 FW-18 FW-22 16" 1.218" 10/22/82 MS-8 FW-52 28" 1.188" 11/27/81 MS-10 FW-62 28" 1.188" 05/29/81 MS-10-5 FW-66 28" 1.188" 07/07/80 MS-15 FW-2 30" 1.25" 01/25/83 WO-40 FW-7 6"
0.280" 04/24/81 WO-40 FW-2 6"
0.280" 04/13/81 VQ-7 FW-2A 6"
0.280" 08/31/81 VQ-13 FW-1E 8"
0.322" 05/10/84 WO-40 FW-11 8"
0.322" 04/21/81 VQ-101 FW-2 48" 0.240" 05/16/84 WO-7 FW-7 8"
0.322" 09/22/81 WO-7 FW-19 10" 0.365" 10/06/82 SX-72 FW-1A 10" 0.365" 03/30/81 SX-72 FW-1 10" 0.365" 03/30/81 SX-66 FW-1AB 10" 0.365" 11/05/81 SI-26 FW-1 10" 0.365" 06/20/84 SI-14 FW-16 12" 0.375" 11/24/80 SI-11 FW-3A 4"
0.337" 12/05/80 SI-7 FW-8AB 8"
0.332" 10/29/81 SI-5 FW-3 10" 1.000" 10/28/81 SI-6 FW-8A 8"
0.906" 01/29/81 SI-5 FW-2 10" 1.000" 01/08/81 SI-3 FW-1 8"
0.322" 07/20/82
SI-1 FW-13A 10" 0.365" 01/05/81 RY-15 FW-7 3"
0.438" 11/02/81 RY-1 FW-3 6"
0.718" 02/23/81 RY-5 FW-1A 6"
0.718" 05/29/81
,RY-5 FW-13 4"
0.531" 09/17/81 RY-5 FW-3 3"
0.438" 09/10/83 RY-13 FW-7 4"
0.531" 06/20/83 RH-12 FW-5 8"
0.322" 07/11/83 MS-16 FW-5-1 30" 1.250" 01/19/82 MS-16 FW-17 28" 1.187" 04/19/82 MS-17 FW-7 32" 1.344" 09/22/82 MS-18 FW-5 32" 1.344" 01/22/82
.
r-
.
.
.
.
System Weld No.
Diameter Thickness Date RT MS-35 FW-42 30" 1.344" 10/20/81 MS-40 FW-111 41" 1.688" 04/05/85 RH-2 FW-8A 3"
0.216" 08/09/82 RH-2 FW-7 14" 0.438" 05/08/79 RH-2 FW-2-1 12" 0.375" 04/13/82 The PTL radiographs of the field pipe welds onsite were interpreted by the following individuals:
PTL Level II PGCo Level II ANI CECO Level I or II (10% document review only)
NRC (Random sample)
When an unacceptable radiograph is detected because of weld or film quality or a dispute in interpretation, the radiographs are interpreted by the following individuals to resolve the problem:
PLT Level II PGCo Level II PLT Level III PGCo Level III S&L/ CECO Level III (Consultation)
ANI CECO Level I or II (10% document review only)
NRC (Random sample)
b.
Shop Welds The NRC inspector reviewed radiographs and reports of the following shop pipe welds that were radiographed by Southwest Fabricating and Welding Company, Inc., (S.W. FAB.) in accordance with ASME Section III 1974 Edition, Summer 1975 Addenda and found them to be acceptable:
System Weld No.
Diameter Thickness Date RT WO-3-1 W-2 10" 0.490" 04/20/78 WO-3-1 W-3 10" 0.490" 04/20/78 WO-3-1 W-4 10" 0.490" 04/20/78 WO-3-1 W-5 10" 0.490" 04/20/78 WO-3-7 W-2 8"
0.478" 03/14/78 WO-3-7 W-3 8"
0.478" 03/14/78 VQ-7-2 W-2 6"
0.280" 08/21/81 VQ-7-2 W-3 6"
0.280" 08/21/81 VQ-7-2 W-4 6"
0.280" 08/21/81 VQ-7-2 W-5 6"
0.280" 08/21/81 FC-26-1 W-2 4"
0.237" 09/21/79 FC-26-1 W-3 4"
0.237" 09/21/79 FC-26-1 W-4 4"
0.237" 09/21/79
-
.
%
.
,-
.
.
..
,
System Weld No.
Diameter Thickness Date RT FC-26-1 W-5 4"
0.237" 09/21/79 CS-7-3 W-1 10" 0.365" 06/13/77 CS-7-3 W-2 10" 0.365" 06/13/77 CS-7-3 W-3 10" 0.365" 06/13/77 CS-7-3 W-8 10" 0.365" 06/13/77 CV-5-6 W-2 3"
0.274" 11/07/77 CV-5-6 W-3 3"
0.274" 11/07/77 CV-5-6 W-4 3"
0.274" 11/07/77 CV-5-6 W-5 3"
0.274" 11/07/77 CV-5-6 W-6 3"
0.274" 11/07/77
'
CV-5-6 W-7 3"
0.274" 11/07/77 MS-16 FW-5-1 30" 1.250" 01/19/82 MS-16 FW-17 28" 1.187" 04/19/82 MS-17 FW-7 32" 1.344" 09/22/82 MS-18 FW-5 32" 1.344" 01/22/82 MS-35 FW-42 30" 1.344" 10/20/81 MS-40 FW-111 41" 1.688" 04/05/85 RE-3-7 W-2 3"
0.216" 02/02/78 RE-3-7 W-3 3"
0.216" 02/02/78 RE-3-7 W-4 3"
0.216" 02/02/78 RY-1-3 W-2 6"
0.719" 03/14/79 RY-1-3 W-3 6"
0.719" 03/14/79
,
RY-1-3 W-4 6"
0.719" 03/14/79 i
RY-1-3-W-5 6"
0.719" 03/14/79 RY-1-3 W-6 6"
0.719" 03/14/79 SI-2-5 W-2 8"
0.906" 06/22/78 SI-2-5 W-3 8"
0.906" 06/22/78-SI-2-5 W-4 8"
0.906" 06/22/78 SI-2-5 W-5 8"
0.906" 06/22/78 SI-2-5 W-6 8"
0.906" 06/22/78 SX-35-7 W-12 10" 0.600" -
06/12/79 1.300" FW-16-B W-2 16" 0.844" 08/07/79 FW-16-B W-4 16" 0.844" 08/07/79 MS-15-6 W-3 28" 1.188" 06/14/79
-
MS-15-6 W-4 28" 1.'188" 06/14/79 RH-2-6 W-2 16" 0.500" 12/07/70 RH-2-6 W-3 16" 0.500" 12/07/78 RH-2-6 W-4 16" 0.500" 12/07/78 RH-2-7 W-2 16" 0.500" 04/18/78 TH-2-7 W-3 16" 0.500" 04/18/78 CC-43-1A W-2 3"
0.216" 01/15/81 CC-43-1A W-3 3"
0.216" 01/15/81 CC-43-1A W-4 3"
0.216" 01/15/81 CC-43-1A W-5 3"
0.216" 01/15/81 CC-43-1A W-6 3"
0.216" 01/15/81 AF-13-5 W-2 4"
0.337" 04/04/78 AF-13-5 W-3 4"
0.337" 04/04/78
,
e
%
.
.
'
.
.
.
- -
..
System Weld No.
Diameter Thickness Date RT AF-13-5 W-4 4"
0.337" 04/04/78 AF-13-5 W-5 4"
0.337" 04/04/78 AF-13-5 W-6 4"
0.337" 04/04/78 OG-33-7 W-2 3"
0.216" 10/12/79 OG-33-7 W-3 3"
0.216" 10/12/79 OG-33-7 W-4 3"
0.216" 10/12/79 OG-33-7 W-5 3"
0.216" 10/12/79 OG-33-7 W-6 3"
0.216" 10/12/79 RC-1-8 W-2 8"
0.906" 10/13/78 RC-1-8 W-3 8"
0.906" 10/13/78 RC-1-8 W-4 8"
0.906" 10/13/78 RC-1-8 W-5 8"
0.906" 10/13/78 RC-1-8 W-6 8"
0.906" 10/13/78 The S.W. FAB. radiographs of the onsite shop pipe welds were interpreted by the following individuals:
S.W. FAB. Level II ANI (Amount reviewed is unknown)
S&L Level II or III CECO Level I or II (10% document review only)
NRC (Random sample)
When an unacceptable radiograph is detected because of weld or film quality or a dispute in interpretation, the radiographs are interpreted by the following individuals to resolve the problem:
S.W. FAB. Level II ANI S&L Level II or III S.W. FAB. Level III S&L Level III
Ceco Level I or II (10% document review only)
NRC (Random sample)
No violations or deviations were identified.
8.
Exit Interview The inspector met with site representatives (denoted in Persons Contacted paragraph) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection noted in this report. The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify any such document / processes as proprietary.
.