IR 05000483/1981019
| ML20010G292 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/28/1981 |
| From: | Danielson D, Key W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20010G284 | List: |
| References | |
| 50-483-81-19, NUDOCS 8109150533 | |
| Download: ML20010G292 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT l'
-REGION III Report No. 50-483/81-19 Docket No. 50-483 License No. CPPR-139 Licensee: The Union Electric Company P;st Office Box 149 i
St. Louis, MO 63166
Facility Name:
Callaway Plant, Unit 1 Inspection At:
Callaway Site, Callaway County, M0
Inspection Conducted: August 12-14, 1981 b
Inspector:
W. J. Key ad NW
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Approved By:
D. H. Danielson, Chief
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Materials and Processes Section
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Inspection Summary E
Inspection on August 12
,, 1981 (Report No. 50-483/81-19)
Areas Inspected: Review of reactor vessel internals installation procedures;
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observation of NSSS component installation, storage, and protection; review of reactor coolant pressure boundary piping installation, welding and NPE
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procedures; visual axamination of welds. This inspection involved a total of
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20 onsite inspector-hours by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
8109150533 810831 PDR ADOCK 05000483 Q
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DETAILS Persons Contacted Union Electric Company (UE)
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- J. V. Laux, Supervisor Engineering QA
- R. L. Powers, Site QA Superintendent
- W. H. Weber, Manager Nuclear Construction
- J. W. Millwood, QA Engineer
- R. Veatch, QA Assistant Engineer
- M.
I. Doyne, Gcneral Superintendent
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Daniel International Corporation (Daniel)
- G. M. Warblow, Service Manager
- A. D. Arnold, Project Quality Manager i
- M. K. Smith, Audit Response Coordinator J. Erickst,n, Mechanical Engineer
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C. Keihn, NSSS Supervisor R. Papini, Mechanical Engineer
- J. A. Holland, Engineering Manager
- Denotes those attending the exit meeting.
Functional or Program Areas Examined 1.
Installation, Welding and NDE Procedure Review The following nrocedures were reviewed for conformance to NRC and
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l ASME Code requirements.
Work Procedures (WP)
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l WP-114, Revision 8 Rigging WP-127, Revision 1 Control of Special Life Materials WP-200, Revision 15 Field Fabrication and Installation of Piping and Component Supports WP-205, Revision 12 Preparation and Processing of Travelers WP-211. Revision 0 Cleanliness Control of Mechanical Equipment l
Westinghouse Specification No. 2463A68-G01
Four Loop Standard Reactor Iaternals Assembly Specification.
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WP-502, Revisio 12 Qualification of Welders WP-503, Revision 15 Control of Welding Consumables WP-504, Revision 5 l
Weld Repair
WP-506, Revision 2 l
Control of Tools used on Stainless Steel Pipe, Plate, and Lh. pes I
l WP-400, Revision 3
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Zoning and Controlled Entry
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Welding Procedures (WPS)
WPS-N-1-3, Revision 6 Welding of Carbon Steel to Alloy Steel, PQT-149, 324 WPS-N-1-6, Revision 8 Welding of Carbon Steel to Stainless Stcel, PQT-44, 163, 164, 42, 371 WPS-N-8-8, Revision 27 Welding of Stainless Steel, PQT-53, 94, 40, 335, 111, 180 WPS-N-8-45, Revision 3 Welding of Stainless Steel, P-8 to Nichel Base Alloy P-45, PQT-158 Nonedestructive Examination Procedures (NDE)
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NDE-7.1-1, Revision 0 Certification of Visual Examination Personnel NDE-7.1Q Certification of NDE Personnel NDE-7.3C, Revision 4 Liquid Penetrant Examination of Weldments NDE 7.4A, Revision 3
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Magnetic Particle Examination of Weldments ASME Code NDE-7.5C3, Revision 3 Radiographic Examination of Weldments No items of noncompliance or deviations were identified 2.
Observation of Activities The following items of NSSS equipment were examined in storage
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for cleanliness, protection and controlled access.
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Reactor Vessel Internals and Cavity
The reactor internals are stored in the vessel covered and clean.
Access to the cavity for personnel, tools, and equipment is con-trolled in accordance with procedures.
Steam Generators All steam generators have been installed, access through the manways are covered and locked. The interior is protected from dirt and moisture.
Reactor Coolant Pumps The reactor coolant pumps and-internals are installed, motors have
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not been connected, heaters are being maintained for moisture pro-taction.
Reactor Vessel Head The reactor vessel head is stored on the refueling floor with access controlled in accordance with procedures.
No items of noncompliance or deviations were identified.
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Visual Examination of Welds
I The inspector examined completed welds in the following systems for conformance to ASME Code requirements for inservice inspection.
High Pressure Coolant Injection EM03, FW-1, FW-3 Accumulator Safety Injection EP01, Weld-A,' Weld-B Peactor Coolant BB-Weld-2, Weld-4
No items of noncompliance or deviations were identified.
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Documentation Review The following Weld control records and radiographs of reactor coolant piping were examined for conformance to NRC and ASME Code requirements Radiographic Review DWG. 2-BG-03-S020/122, Weld "C"
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DWG. 2-EN-02-S-015/111, Weld "A"
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DWG. 2-EF-03-S-18/134, Weld "B" DWG. 2-OP Loop 2, SG side, Weld-3 DWG. 2-0P Loop 2, RCP Side, Weld-W4 DWG. 2-BB01, Weld-F108
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DWG. 2-BB01, Weld-F103 DWG. 2-BB01, Weld-F402 DWG. 2-BB01, Weld-F304 DWG. 2-BB01, Weld-F?.07 SCP1-Surge 1, Weld-6 SCP-Surge 3, Weld-2 SCP-Surge 3, Weld-3 SCP-Surge 3, Weld-8 Weld Control Records DWG. FS-M-D-M-03BB01(Q)
Weld No. 2-BB-01-F001 Spool No. S-402 to S-001 RT Report - 03855 PT Report - 01416, 01434 DWG. FS-M-D-M-03BB01(Q)
Weld No. 2-BB-01-F002 Spool S-001 to S-002 RT Report - 03753 PT Report - 01397 DWG. FS-M-D-M-03BB01(Q)
Weld No. 2-BB-01-F004 Spool S-003 to Pressurizer T BB03 RT Report - 3365 PT Report 1238, 1222 DWG. FS-M-D-M-03BB1(Q)
Weld No. 2-BB-01-F105 S G E BB01A to ' pool S-103 DWG. M-03BB01(Q)
Weld No. 2-BB-01-F108 Spool S-104 to S-105 RT Report - 05416, 05256 PT Report - 02424, 2443, 2259, 2257-5-
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DUG. M-03BB-01(Q)
Weld No. 2-B3-01-F306 Spool S-303 to S-304 RT Report - 05227 PT Report - 02283, 02282 No items of noncompliance or deviations were identified.
5.
Unresolved Matter Identified During Independent Inspection On July 26, 1981 the licensee generated NCR 2SN-4340 when it was discovered that the right wheel on snubber assembly "A" on the Polar Crane in the reactor building had worn through the 4\\"
diameter axle. The axle did not break, however, only a section 2 5/16" long by 1 ?'64" thick remained of the axle. The wheel bore was grooved tc a depth of 1/32",
All wheels and axles of the three (3) remaining snubber assemblies were examined. No indications of wear was noted.
The licensees Architect Engineers (AE) Bechtel Power Corporation, and the Crane manufacture P&H Harnischferger Corporation (P&H) a-investigating the cause of the problem. It is suspected that the cause of the problem is localized out-of-tolerance of the Polar Crane rail and girders.
The inspector examined the snubber assembly wheel flanges and axle bore. There appeared to be no damage to these items.
On August 7, 1981 the licensee and Bechtel requested permission of P&H to conditionally release the crane for cperatior.. This was granted on August 11, 1981, however, a thorough visual examination is to be performed prior to making lifts gre ter than 30 tons.
This is considered an unresolved item pending review of the final resolution to this matter.
(483/81-19-01)
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of non-compliance, or deviations. One unresolved item disclosed during this inspection is discussed in Paragraph 5.
Exit Interview The inspector met with licensee representatives (denoted under Persons Contacted) et the conclusion of the inspeciton. The inspector summarized the purpose and findings of the inspection.
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