IR 05000483/1981001
| ML19345G318 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 02/05/1981 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19345G312 | List: |
| References | |
| 50-483-81-01, 50-483-81-1, NUDOCS 8103180163 | |
| Download: ML19345G318 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCMEhT
REGION III
Report No. 50-483/81-01
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Docket No. 50-483 License No. CPPR-139 Licensee: Union Electric Company P. O. Box 149 St. Louis, MO 63166 Facility Name: Callaway Plant, Unit 1 Inspection At: Callaway Site, Callaway County, M0 Inspection Conducted: January 13-16, 1981 Inspector:
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.D9 Approved by:
D. H. Danielson, Chief M
Engineering Support Section 2 Inspection Summary Inspection on January 13-16, 1981 (Report No. 50-483/81-01)
Areas Inspected: Quality records on structural installation; records on reactor vessel head to CRDMS; observation pump and valve installations; preparation for installation of post tensioning system. The inspection involved a total of 20 onsite inspector-hours by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS Persons Contacted Union Electric Company (UEC)
- W. H. Weber, Manager Nuclear Construction
- J.
V. Laux, Supervising Engineer - QA Construction
- R. Veatch, Quality Assurance Assistant Engineer
- C. J. Plows, Consultant, Quality Assurance
. Daniel International Corporation (DIC)
- A. D. Arnold, Project Quality Manager
- J. A. Holland, Engineering Manager
- M. K. Smith, Audit Resp. Coordinator
- H. J. Starr, Project Manager
- W.
L. Petrie, Project Quality Assurance Management E. E. Ster.~inger, Welding Quality Control Engineer B. Harte, General Foreman, Boiler Makers R. Gagne, Lead Weld Quality Control Inspector G. Weiler, Quality Control Inspector Other Personnel
- W. Hanson, Resident Inspector, NRC:RIII
- Denotes those attending the exit meeting.
Functional or Program Areas Inspected 1.
Building Structures Inside Containment - Procedure Review The following procedures relating to erection of safety related structural steel were examined.
WP-ll3, Revision 6, Erection Structural Steel WP-127, Revision 1, Control Special Lift Materials Construction N-1-1, Welding Carbon Steel
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WP-115, Revision 6, Repair Structural and Miscellaneous Steel Construction QCP-507, Inspection Structural and Miscellaneous Steel
'The reference specification for heating and straightening is 1972 AISC Code of Standard Practice for Steel Buildings and Bridges. Structural g
welding conforms to AWS Dl.1-75.
The high strength bolts either ASTM A-325 or A-490 are installed using load indicating' washers with a gap tolerance maximum of.015".
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D.I.C. Weld Procedure WP-N-1-1, Revision 27, was examined. Welding was performed using E7018 electrode and the Shielded Metal Arc Process.
These welds if greater than 1 1/2" thick required a minimum preheat of 200 and if over 3/4" thick and carbon of 0.30% the same preheat.
The welds are given a visual inspection prior to acceptance.
No items of noncompliance or deviations were identified.
2.
-Quality Records on CRDM's to Reactor Vessel Head This work has been completed and several of the welds were inspected.
All were smooth, clean, and with acceptable contour. These welds are ASME Section III Class 1 and are made to procedure NM-8-8-B-1-W.
The weld is.070.080 thick using an ER308L insert. A needle purge of 7 CFH for five minutes is employed prior to start of welding. CRDM No. I was welded to WP204, Revision 7, and was hydro tested for ten minutes at 3,125 psi. This hydrotest procedure was used on all the CRDMs.
The cleanliness requirement is outlined in Specification 292722 and the water quality in Specification 597760. A repair weld procedure was qualified in the event it was needed.
An NCR 2SN-1629-M had been issued on head adapter S/N M232A06 due to imperfect threads. The inspector noted that the licensee must assure that all NCRs requiring W design action be signed off by W engineering.
'No items of noncompliance or deviations were identified.
3.
Component Record Review This pump PEM01A is a Class 2 pump and was manufactured by Pacific Pump and supplied by W.
The pump was released on W QR29744 and is a 3" pump meeting the requirements of ASME Section III, 1974 Edition, Summer 1974 Addenda. However, the QR indicated a contingency that the motor seismic analysis had not been received.
Investigation revealed that the matter
'had been closed but not noted on the quality documentation.
The new system now in operation requires that an NCR be issued against any contingencies which could solve the above problem.
Documentation'for a 3" Gate Valve No. 3G74 was examined. This valve was manufactured by W and released under QR 24158. It is a Class 1 valve and certified by Lumberman's Insurance Company to meet ASME Section III, 1974 Edition, Winter 1975, Addenda plus Code Cases 1769 and 16/49. Certifications on materials, mechanical properties and NDT were included in the package.
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No items of noncompliance or deviations were identified.
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Post Tensioning Activities A r. umber of the 170 wire tendons have been delivered. Bechtel Specifi-cation 10466-C155, Revision 5, governs the furnishing, fabricating, and delivery of reactor building post tensioning sustem for SNUPPS.
InRyco are furnishing the tendons, but their procedures have not been approved so no work has begun onsite. Bechtel specifications 10466-C156, Revision 5, governs stressing and greasing tendons while Specification 10466-C-157 Q governs furnishing and delivering of tendon sheathing and filler material.
No items of noncompliance or deviations were identified.
Exit Interview The inspector. net with licensee representatives (denoted under Persons Con-tacted) at the conclusion of the inspection on January 16, 1981. The inspactor summarized the scope and findings of the inspection which were
- ackrowledged by the licensee.
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