IR 05000483/1979014
| ML19290D570 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 01/11/1980 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19290D564 | List: |
| References | |
| 50-483-79-14, NUDOCS 8002220192 | |
| Download: ML19290D570 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-483/79-14 Docket No. 50-483 License No. CPPR-139 Licensee: Union Electric Company P.O. Box 149 St. Louis, MO 63166 Facility Name: Callaway Nuclear Plant, Unit 1 Inspection At: Callaway Site, Callaway County, Missouri Inspection Conducted: December 10-13, 1979 Inspector:
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muLJw Approved by:
D. H. Danielson, Chief i4 86
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Engineering Support Section 2 Inspection Summary Inspection on December 10-13, 1979 (Report No. 50-483/79-14)
Areas Inspected: Observation of cleaning operations on internals and reactor cavity; observation welds in surge line; QA records for the pump and steam generator support columns; setting of reactor pressure vessel; previous inspection findings.
This inspection involved a total of 23 inspector hours on site by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
8002220 19 re DETAILS Persons Contacted (UECo)
- W. H. Weber, Manager, Nuclear Construction M. I. Doyne, General Superintendent
- R. L. Powers, Supervising Engineer, QA
- R. Veatch, Assistant Engineer, QA J. Gearhart, Engineer, QA Other Personnel H. J. Starr, Project Manager, Daniel International
- E. D. McFarland, Construction Engineering Manager, Daniel International
- J. A. Holland, Project QA Manager Daniel International
- W. L. Sykora, Assistant Project Manager, Daniel International J. Martinez, Site Manager, Westinghouse J. Long, Project Welding Engineer, Daniel International H. Kisner, Lead Mechanical QC Inspector, Daniel International
- Denotes those present at the exit meeting.
Licensee Actions on Previous Inspection Findings (Closed) Unresolved item (483/79-03-01): An incorrect number appeared on a microfiche N-1 form supplied by Applied Engineering Company through Westinghouse. This applied to a Reheat Letdown Ex-changer System and a corrected hard copy of the N-1 is now in the files. This unresolved matter is considered closed, but the micro fiche must also be corrected in an expeditious mancer.
Functional or Program Areas Inspected 1.
Cleaning and Leveling of the Reactor Vessel a.
Dry cleaning in the area of the transfer canal was being done.
Fitting of the internals to the reactor vessel was being per-formed under clean room conditions in an acceptable manner.
b.
Installation check list, RPV/RBB01 for the reactor pressure vessel indicated steps where quality control verification had not been performed. One step in particular where 75% bearing under the vessel nozzle supports is required indicated only a check and signature by the field engineer. While Procedure SCP-210 states that engineering shall call out the hold points for QC, it appears that QC should insist on their signature and verification under the above conditions. The' licensee agreed to review the need for QC inspection sign off on in-stallation checklists. This is an unresolved item (483/79-14-01).
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.o 2.
Installation and Welding of CRD Mechanism Lower Canopy Seal Westinghouse (W) process specification PWR82127, Revision B, will be the basic requirement for installing the 78 CRD end welds. An automasde Astro-Arc welder will be qualified and a three channel strip recorder will record amperage, voltage, and speed. This weld will utilize a y-shaped insert and the base materials are stainless steel. Daniel Inc. is qualifying velders and their own procedure for this work. Applicable ASHE codes for this work should be referenced in the Daniel procedures.
No items of noncompliance or deviations were identified.
3.
Inspection of Surge Line Welds Field Weld No. BB-01-E-001 in the 14" stainless steel surge line was examined. This ia a class I weld and the weld has been ground to an acceptable contour for radiographic testing. Welds No. I and No. 2 were made to Procedure N-8-8-BA-2.
The fit up on weld No. 4, which had not been made, was acceptable.
No items of noncompliance or deviations were identified.
4.
QC Records Main Coolant Pump Supports and Steam Generator Supports These supports were supplied by W and manufactured by Lamco. The QC records and certifications for the following parts vere examined and found ta be acceptable to the requirements of ASME Section III, 1974 Edition, Summer 1976 Addenda.
No.
System W Quality Release 101064 Reactor Coolant Pump 33590 1126 Steam Generator Support 33599-1 1127 Steam Generator Support 33599-1 The above items were inspected at the source before shipment.
No items of noncompliance or deviations were identified.
Unresolved items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. An unresolved item disclosed during the inspection is dic-cussed in Paragraph Ib.
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Exit Interview The inspector met with licensee and f.ontractor representatives (denoted in Persons Contacted Paragraph) at the conclusion of the inspection on December 13, 1979. The inspector summarized the purpose, scope and findings identified during the inspection.
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