IR 05000445/1982004
| ML20054E206 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/31/1982 |
| From: | Gilbert L, Hunnicutt D, Westerman T, Whittlesey K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20054E204 | List: |
| References | |
| 50-445-82-04, 50-445-82-4, 50-446-82-03, 50-446-82-3, NUDOCS 8204260257 | |
| Download: ML20054E206 (6) | |
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APPENDIX A U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report:
50-445/82-04; 50-446/82-03 Dockets: 50-445; 50-446 Category A2 Licensee:
Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Facility Name:
Comanche Peak, Units 1 and 2
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Inspection at:
Comanche Peak Steam Electric Station Inspection conducted: March 15-19, 1982 b4:2 2]J2 Inspectors:l#L.D. Gilbert,ReactorInspector,EngineeringSection 3kt/g1 Date j(
(Paragraphs 1, 2, 3, 4, & 7)
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3/3//8L D. M. Hunnicutt, Chief, Engineering Section Datd (Paragraphs 5 & 6)
N ) uwLP 3/3//S2-K. A. Whittlesey, Reactor Inspector-Trainee, Engineering Date/
Section (Paragraphs 5 & 6)
Reviewed:
7/!fk T. F. Westerman, Chief, Reactor Project Section A D6te'
Approved:
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- Ea27-8/3//82-D. M. Hunnicutt, Chief, Engineering Section Date~
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Inspection Sumary Inspection During March 15-19, 1982 (Report 50-445/82-04; 50-446/82-03)
Areas Inspected:
Routine, unannounced inspection of construction activities including site tour; observation of work and review of records for welding of reactor coolant pressure boundary pipe and other safety-related pipe in Unit 2; and review of records for installation of electrical and piping penetrations in Unit 1.
The inspection involved 90 inspector-hours by three NRC inspectors.
Results:
No violations or deviations were identified.
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DETAILS 1.
Persons Contacted Principal Licensee Personnel R. G. Tolson, Site QA Supervisor, Texas Utilities Generating Company (TUGC0)
- B. C. Scott, QA Supervisor, TUGC0
- R. D. Calder, Manager Technical Support, Texas Utilities Services, Inc. (TUSI)
- M. R. McBay, Manager Engineering, TUSI Of.her Personnel
- G. R. Purdy, Site QA Manager, Brown & Root (B&R)
W. E. Baker, Senior Project Welding Engineer, B&R E. Opelski, Site NDE Level III, B&R G. Richardson, Pipefitter Foreman, B&R J. Hite, Welding Material Engineer B&R J. Butler, QC Inspector, B&R R. Darby, QC Inspector, B&R R. Barber, Welding Engineer, Gibbs & Hill (G&H)
The NRC inspectors also interviewed other licensee and contractor employees during the course of the inspection.
- Denotes those attending the exit interview.
2.
Site Tour The NRC inspectors toured the Reactor Building, Auxiliary Building, and Fuel Handling Building for Units 1 and 2 to observe construction in progress and to inspect housekeeping.
No violations or deviations were identified.
3.
Reactor Coolant Pressure Boundary Pipe Welding - Unit 2 The NRC inspector observed the welding and quality control activities associated with fabricating the following welds in the Reactor Coolant (RC) and Safety Injection (SI) Piping Systems:
Drawing Line Number Weld RC-2-RB-019 6" RC-2-008-2501R-1 llA RC-2-RB-019 6" RC-2-070-2501R-1 FW6 RC-2-RB-019 6" RC-2-070-2501R-1 FW7 SI-2-RB-061 6" SI-2-148-2501R-1 FW10
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In the areas reviewed, the entries on the weld data cards were consistent with the status of the welds, the inspections of QC personnel appeared to be adequate ar.e consistent with Procedure QAP-11.1-26, the qualifications of the welders were consistent with ASME Section IX requirements, and the filler materials were consistent with weld procedure requirements and were traceable to certified material test reports.
The storage and handling of welding filler materials by personnel in the Rod Issue Rooms were inspected and found to be consistent with Procedure CPM 6.98 for control of welding filler materials.
No violations or deviations were identified.
4.
Safety-Related Pipe Welding - Unit 2 The NRC inspector observed the welding and quality control activities associated with fabricating the following welds in the Chemical and Volume Control (C&VC) System and the Safety Injection (SI) Piping System:
Drawing Line Number Weld CS-2-RB-024 3" CS-2-009-601R-2 FW15A CS-2-SB-039 3" CS-2-358-301R-3 FW6 31-2-RB-070 10" SI-2-106-250R-2 FW2 In the areas reviewed, the entries on the weld data cards were consistent with the status of the welds, the inspections of QC personnel appeared to be adequate and consistent with Procedure QAP-11.1-26, the qualifications of the welders were consistent with ASME Section IX requirements, and filler materials were consistent with weld procedure requirements and were traceable to certified material test reports.
No violations or deviations were identified.
5.
Containment Electrical Penetrations - Unit 1 The NRC inspectors selected two electrical penetrations, IE-9 and IE-46, for review. These penetrations had been installed previously and no installation activities of penetrations were in progress at Unit 1 during this inspection period.
The NRC inspectors reviewed the following documentation related to the electrical penetrations:
a.
G&H Specification 2323-ES-100 b.
G&H Specification 2323-ES-12 c.
Amphenol Sams Specification 123-2101
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Amphenol Sams Specification 123-2098 e.
Construction Drawing El-500-01 and related revisions f.~
Construction Drawing El-501-01 and related revisions.
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Construction Drawing El-501-05 and related revisions h.
Construction Drawing El-502 and reined revisions i.
Traveler No. EE 79-221-0200 j.
Traveler No. RI 80-392-0200 k.
G&H QA Release 2633 (QAR No. 2633)
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Electrical Penetration G&H Specification No. ES-12 (P.O. 460), Rev.1 m.
Material (physical and chemical) certifications n.
Pneumatic certification (conducted at 63 psi) (design specification 50 psi at 280 degrees F)
Drawing FSE 00182 - Installation of weld neck flanges for electrical o.
penetrations q.
Review of the individual data packages to verify that records and supporting documentation were assembled for each of these electrical penetrations The NRC inspectors visually examined several electrical penetrations during an inspection and tour of the Unit 1 Containment-Building and related site structures on March 15, 1982.
Each of the penetrations visually inspected appeared to be properly installed in accordLace with applicable documentation.
No violations or deviations were identified.
6.
Containment Piping Penetrations - Unit 1 The NRC inspector selected one piping penetration, Field Weld 15 M III-15, in the containment spray system for review.
This mechanical penetration had been installed previously and no installation activities of piping (mechanical) penetrations were in progress at Unit I during this inspection period.
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The NRC inspectors reviewed the following documentation related to this penetration:
a.
B&R Drawing BRP-PN-1-503-3-1 b.
B&R WPS No. 11010 c.
Field Weld Serial No. 05969.
d.
Material (physical and chemical) certifications ASME Form N-2 (Manufacturers Data Report for NPT and appurtenances)
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Gulf & Western Energy Products Group _(G&W - EPG) Procedure 4.4.2 (LP)
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G&W - EPW Procedure Q.S.P.4.1.1 (RT of butt welds)
h.
G&W - EPG Procedure Q.S.P.4.2.2 (MT)
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G&W - EPG Procedure Q.S.P.4.5.1 (hydrostatic testing)
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Certification of Ultrasonic Testing (UT) of calibration standard k.
G&W - EPG Drawing 802252-5 and SER No. 802252-13A-1 1.
Certification that radiographic testing (RT) had been performed at Field Weld 15.
Certification listed five films (R1, R2, R3, R4, and RS).
RT was certified to have been performed using Ir-192 with source strengths ranging from 48 to 106 curies.
m.
Review of the individual data package to verify that records and supporting documentation were assembled for this piping penetration.
The NRC inspectors visually examined several mechanical (piping) penetra-tions during an inspection and tour of the Unit 1 Containment Building and
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related site structures on March 15, 1982.
Each of the penetrations visually inspected appeared to be properly installed in accordance with applicable documentation.
No violations or deviations were identified.
7.
Exit Interview The NRC inspectors met with licensee representatives (denoted in para-graph 1) and R. G. Taylor (NRC Resident Reactor Inspector) on March 19, 1982, and summarized the scope and findings of the inspection.
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