IR 05000455/1985015
| ML20126J542 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/04/1985 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20126J540 | List: |
| References | |
| 50-455-85-15, NUDOCS 8506100631 | |
| Download: ML20126J542 (8) | |
Text
.
.
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-455/85015(DRS)
Docket No. 50-455 License No. CPPR-131 Licensee:
Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name:
Byron Station, Unit 2 Inspection At:
Byron Site, Byron, Illinois Inspection Conducted: May 15, 17, 20-22, 1985 kYJ Inspector:
. Ward (* '
N Date Approved By:
. H. Danielson,p s Chief b / 81,.
Materials & Processes Section Date Inspection Summary Inspection on May 15, 17, 20-22, 1985 (Report No. 50-455/85015)(DRS)
Areas Inspected:
Unannounced, routine safety inspection of containment penetrations, Reactor Coolant pressure boundary piping, safety-related piping, and preservice inspection activities.
The inspection involved a total of 34 inspector-hours by one'NRC inspector.
Results:
No violations or deviations were identified.
Nk
[
G m
-
)
.
.
DETAILS
.1.
Persons Contacted Commonwealth Edison Company (Ceco)
- E. Martin, QA Superintendent
- M. Lohmann, Assistant Construction Superintendent
- R. Klinger, QC Supervisor
- R. Morajec, Mechanical Supervisor
- G. Briette, QA Engineer
- W. Wolbor, QA Inspector G. Sorensen, Construction Superintendent J. Woldridge, QA Supervisor J. Porter, Construction Supervisor Powers-Azco-Pope R. Larkin, QA Manager Hunter Corp.
K. Kranz, Welding Engineer Ebasco Services Inc.
P. Deeds, Level III UT Nuclear Regulatory Commission (NRC)
J. Hinds, Jr., Senior Resident Inspector Th'e inspector also contacted and interviewed other licensee and contractor employees.
- Denotes those attending the exit interview May 22, 1985.
2.
Containment Penetrations - Review of Quality Records The NRC inspector reviewed the pertinent work and quality records for five containment penetrations (two electrical #2SIO6E and #2AP85EA and three piping #2PC-4, #2PC-9 and #2PC-10) and determined that the records exist to confirm that quality requirements have been met and that the records reflect work accomplishment consistent with NRC requirements and SAR commitments.
The NRC inspector reviewed material requirements imposed by the purchase specifications, certifications of material, receipt inspection reports and QC records relative to installation activities.
No violations or deviations were identified.
'.
.
.
3.
Containment Penetration -' Observation of Work Activities The NRC inspector selected five electrical penetrations #2E52 FW14,
- 2E53 FW15, #2E54 FW16, #2E55 FW17, and #2E56 FW18.
The completed
. work was reviewed and the NRC inspector visually examined the welds of the penetrations.
The NRC inspector reviewed documents related to the subject and determined that the requirements of applicable
-
specifications,. standards, work procedures, testing procedures and inspection procedures were met.
The method of assembly of components were consiste'nt with design drawings and travelers.
Installation activities and other activities were conducted with reference to specified procedures.
Nondestructive examinations (NDE) were performed in accordance with work specifications.
NDE personnel were certified in accordance with SNT-TC-1A.
QA/QC inspector activities-were performed as required by established procedures and by properly qualified personnel.
No violations or deviations were identified.
4.
Safety-Related Piping and Reactor Coolant Loop Piping Welder Qualifications-The NRC inspector reviewed twelve welder status records, records of-performance qualification tests and determined that these documents conform to the applicable-Code requirements.
The licensee and contractor has established procedures for qualification of welders and welding operators in accordance with the ASME Code,-as applicable, has an adequate system for maintaining a continuous record of the qualification status of all welders and welding operations and this system is effectively utilized and accurate.
The NRC inspector reviewed qualification status records of six welders involved in weld repairs and determined that they meet applicable
. qualification requirements.
The NRC inspector also visually examined bend test specimens from qualification weldments.
No violations or deviations were identified.
5.
Safety-Related Piping - Observation of Work Activities One hundred percent.of the large bore piping is completed and approximately 98% of the small bore piping is completed for Unit 2.
The NRC inspector
.
observed the end preparation on main steam pipe weld #1893-6 and reviewed
documents on twelve welds:
RH-10 #303, #329, #328, #106, #346, #105, S-CV-100-242 #5642, #5638, #5643, #5639,_#5644, and #5640.
The NRC inspector determined that the activities were conducted in accordance with the process sheets which coordinate the operations, referenced
<
procedures, established hold points and provided for inspection approval.
The NRC inspector also reviewed welding procedures, detailed drawings, weld data sheets, material traceability records, weld records, NDE reports, process sheets and visually examined the welds.
..
-
-
-
.
.
---
e
.
No violations or deviations were identified.
6.
Safety-Related Pipina (Weldina) - Review of Quality Records The NRC inspector selected five field welds (RH-10 #374, #373, #102, #101 and #99) where welding,.NDE and inspection activities were completed.
The NRC inspector reviewed records for each weld and determined that the records meet established procedures and that the records reflected work accomplishment consistent with NRC requirements and SAR commitments.
The inspector reviewed weld records, process sheets, NDE records, material traceability, welder and welder inspector qualifications.
No violations or deviations were identified.
7.
Reactor Coolant Loop Pipina - Visual Examination of Welds The NRC inspector selected twelve completed field welds and determined by visual examination that the welds (2H-CBE-3 #FW210, #FW209,.#FW211,
-#FW208, #FW207, #FW204,' #FW205, #FW206, #FW202, #FW201, #FW203 and #FW212)
conformed to applicable Codes, standards, construction specifications and welding procedure requirements.
The NRC inspector visually examined the welds for _ length, size, shape, surface, weld reinforcement-height and appearance, arc strikes, weld spatter and surface defects and found these welds to be acceptable.
The NRC inspector reviewed quality records of the welds and determined that the records reflected adequate weld quality, weld history records were adequate and that the specified inspections required were completed.
No violations or deviations were identified.
8.
Safety-Related Pipina - Weld Heat Treatment The~NRC inspector determined that approved procedures were available for weld joint preheating when required by'a welding procedure specification and that these procedures properly specified acceptable preheating methods, provided requirements for monitoring and recording
-
preheat temperature before, during and after welding.
The NRC inspector also determined that approved and adequate procedures-were available for the conduct of postweld heat treatment and that the licensee and contractor had a system capable of meeting the heating and
. cooling rates, metal temperatures, temperature uniformity and control limits specified in the ASME B&PV Code, as applicable.
The NRC inspector reviewed post weld heat treatment records for three welds (2FWO3DA-16 #FW750, 2FWO308-16 #FW727 and 2FWO300-16 #FW28) and determined that the weld areas were instrumented to provide time temperature records for the duration of the entire heat treatment cycle, temperature monitoring instruments were properly calibrated, sufficient thermocouples were used and that the PWHT temperature and holding time was specified.
The NRC inspector reviewed final reports, process sheets, weld records, drawings, work requests, NDE records, weld material stores requisitions, field orders and material traceability records.
.
.
No violations or deviations were identified.
9.
Safety-Related Piping - Special Welding Applications The NRC inspector reviewed several records of weld repairs and determined that they were conducted in accordance with applicable requirements and specified procedures.
The following welds were reviewed:
2MS01AA-30
- 328, 2MS01AC-32 #321, and 2MS-5713 #422, #423, #425 and #424.
Grinding was performed prior to the repair welding to remove the weld defects.
Also weld S-51-100-56 #3199 was blended by grinding and no welding was required.
The NRC inspector reviewed the welding procedures used for the weld repairs, qualification of the procedures, NDE records and certification of welders.
No violations or deviations were identified.
10.
Reactor Coolant Pressure Boundary Piping - Review of Quality Records The NRC inspector reviewed documentation for the 908 elbow #RIR167, tee #RIR252, and coupling #RIR349.
Included in this review were material test reports on chemical composition and physical characteristics; receiving inspection reports for physical condition, damage, cleanliness, etc.; storage inspection records; and installation records for installation checklists and alignment.
No violations or deviations were identified.
11.
Reactor Coolant Pressure Boundary Piping (Welding) - Observation of Work
'
Activities Onsite, 100% of the large bore piping is completed and 98% of the small bore piping is completed. The NRC inspector observed welding on weld T299-32PT-467A #FW4 and determined that the applicable specifications and procedures requirements were complied with for weld identification; use of applicable weld procedures; welder qualification, use of specified weld material; starts, stops and undercuts ground.
The inspector also observed there was no unused or uncontrolled weld filler material in the welding area.
The NRC inspector visually examined the welds T991-2FT-424 #FW10 and i
- FW11, and T977-2FT-415 #FW23 and #FW24 and found them to be acceptable.
In touring the welding material issuing station the inspector determined that there were applicable procedures on-hand and these procedural requirements were being complied with for storage of materials, including identification, segregation, cleanliness and storage temperature, issue records, amount withdrawn, identity of withdrawer and dates.
No violations or deviations were identified.
I
~
,
'
12.
Reactor Coolant Pressure Boundary Piping - Observation of Work Activities
'The NRC inspector reviewed pipe spools.2H-CBE-2 and T959-2FT-445, visually. examined the spools and determined that applicable procedures including specified materials and qualified inspection personnel were i
being utilized.
The NRC inspector located selected components in system #2A-CBE-1 and
- 2H-CBE-2 and determined that the piping runs are installed as required by applicable specifications.
Also that the NDE activities were performed by qualified NDE personnel.
The NRC inspector compared piping drawings with actual Reactor Coolant loop installations and found them to be acceptable.
The NRC inspector also reviewed installation records of several pipe spools and determined that the required scope of the inspection was performed and recorded data and that records confirm that specification and installation procedures, including cleanliness requirements, were met.
The NRC inspector reviewed audits performed by Powers-Azco-Pope, Hunter Corp. and CECO and determined that the audits were performed of the scope ana frequency specified and that the deficiencies identified during the audits were corrected in a timely manner.
No violations or deviations were identified.
13.
Preservice Inspection (PSI)
a.
General ESASCo is performing PSI in accordance with ASME Section XI and are scheduled to be completed by the end of 1985.
b.
Procedure Review The NRC inspector reviewed the following procedures:
Rockwell International (RI), Preservice/ Inservice Inspection-
Ultrasonic Examination of Reactor Vessel Circumferential Shell Welds, #445151000005, Revision A.
RI, Preservice/ Inservice Inspection-Ultrasonic Examination
for Near Surface Resolution of Vessel Welds from the Inside Surface, #4451S1000009, Revision A.
RI, Preservice/ Inservice Inspection-Ultrasonic Examination
of Reactor Nozzle Inside Radius Section, #4451$1000008, Revision A.
RI, Preservice/ Inservice Inspection-Ultrasonic Examination
of Nuclear Reactor Nozzle to Vessel Welds #445151000006, Revision A.
-
<
...
.
EBASCo,~Multifrequency Eddy Current Examination of Westinghouse
Steam Generator-Tubing, #151-ET-578-1.~
EBASCo, Visual Examination of Bolting Components, #1S1-VT-S78-1,
Revision 1.
EBASCo, Liquid Penetrant Examination, #151-PT-S78-1, Revision 2.
'
EBASCo, Magnetic Particle Examination of Welds and Bolting,
- 1SI-MT-S78-1, Revision 1.
EBASCo, Ultrasonic Examination of Nozzle Inside Radius,
- 151-UT-S78-12, Revision 1.
""
EBASCo, Ultrasonic Examination of RPV & S.G. Safe End Welds,
- 1S1-UT-S78-11, Revision 0.
EBASCo, Ultrasonic Straight Beam Examination of RPV Shell to
Flange Weld #151-UT-S78-10, Revision 0.
EBASCo, Straight Beam Ultrasonic Examination of Piping Welds,
- 1S1-UT-S78-9, Revision 1.
E8ASCo, Ultrasonic Straight Beam Examination, #151-UT-S78-8,
Revision 0.
EBASCo, Ultrasonic Inspection of 3.0" Diameter 20" Long
Austenitic Stainless Steel RC Isolation Valve Studs,
- 151-UT-S78-6, Revision 0.
EBASCo, Ultrasonic Inspection of 4.5" Diameter 3S" Long
Carbon Steel Reactor Coolant Pump Stud, #151-UT-S78-5, Revision 1.
EBASCo, Ultrasonic Examination of Flange Ligament Areas of
Reactor Vessel, #1S1-0T-S78-4, Revision 1.
EBASCo, Ultrasonic Examination of Class 1 and 2 Bolts and
Studs, #151-UT-S78-3, Revision 1.
EBASCo, Ultrasonic Manual Examination of Class 1 and 2 Vessel
Welds Including Reactor Pressure Vessel Welds, #1$1-UT-S28-2, Revision 1.
c.
Material and Equipment Certifications The inspector reviewed the certification documents relative to the following items Ultrasonic instruments, calibration blocks, transducers and
couplant.
<
>
T I
l.
.
Liquid penetrant, pentrant, cleaner and developer.
- Magnetic particle, materials and equipment.
- d.
Review of NDE Personnel Certifications, Observation of Work, and Review of Data Reports and Audits The NRC inspector reviewed selected NDE personnel certifications in accordance with SNT-TC-1A.
The certifications of Level IIs and IIIs that were certified by EPRI for IGSCC were also reviewed.
The NRC inspector also observed the work and had discussions with personnel during review of the following activities.
These observations included calibrations, performance of the examinations and the associated documentation.
Ultrasonic examinations of welds 2MS07AB-28 Loop 2
- C20L and #C21.
Liquid pentrant examinations of welds 2S105DD-6 #J10 and #J11.
- The NRC inspector reviewed selected data reports and audits.
No violations or deviations were identified.
14.
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 documents / processes as proprietary.
2