IR 05000341/1981011
| ML20010C140 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/04/1981 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20010C134 | List: |
| References | |
| 50-341-81-11, NUDOCS 8108190172 | |
| Download: ML20010C140 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT I
REGION III
Report No.'50-341/81-11 Docket No.-50-341 License No. CPPR-87 Licensee: Detroit Edison Company 2000 Second Avenue Detroit, MI 48226 Facility Name: Enrico Fermi Atomic Power Plant, Unit 2 Inspection At: Fermi Site, Monroe, MI Inspection Conducted: July 6-9, 1981 3MP/
Inspector:
. M. Erb
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Approved by:
D. H. Danielson, Chief-Materials and Processes Section Inspection Summary Inspection on July 6-9, 1981 (Report No. 50-341/81-11)
Areas Inspected: Previously reported 50.55(e) item; observation and status of Internals work; observation of process pipe penetration work activities; observation of welding of CRD insert and withdraw lines. The inspection involved a total of 23 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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'8108190172 010806 PDRADOCK05000g
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DETAILS Persons Contacted Detroit Edison Company (DECO)
- T. A. Alessi, Director, Project QA
- D. A. Wells, Manager, QA
- H. A. Walker, Supervisor, Construction QA
- C. R. Bacon, Assistant Supervisor, Field Engineering
- S. H. Noetzel, Assistant Project Manager, Control
- W. A. Boelder, Assistant Project Manager, Construction W. Adair, Resident Field Engineer
- R. F. McCrancy, QA Supervisor, Wismer and Becker Company L. Santilli, Document Technician, Wismer and Becker Company J. Reed, Site Manager, Reactor Controls Inc.
J. W. Flaherty, Welding Engineer, Wismer and Becker Company D. H. levering, Manager, Dry Well Construction J. R. Moskwa, Supervisor, QA, Reactor Controls Inc.
USNRC:RIII
- P. M. Byron, Resident Inspector
- Denotes those present at the exit interv..w.
Licensee Action on Previously Identified Items (0 pen) 50.55(e) item - lack of clearance on CRD insert and withdraw lines at drywell penetrations.
Licensee engineering people stated that three different approaches to the problem have been suggested and are under study. Cost and schedule will be evaluated before any recommendation is made in this area.
Functional or Program Areas Inspected 1.
Internals Installation A clean room has been set up for personnel entering the reactor pressure vessel. The inspector examined the inside bottom of the vessel and found cleanliness to be acceptable. Two core spray nozzles loose on the header will require rework and are covered in a deviation report.
Tests are in progress in the steam pre-dryer to ascertain whether it is acceptably clean. This component was involved in a fire when a shipping cover was ignited and burned.
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The steam dryer will be reworked by removal of several of the top plates and replacement by heavier plates. This work will be done in the equipment pool and has alre.dy been performed on a number of steam dryers in other plants.
No items of noncompliance or deviations were identified.
2.
Control Rod Drive System Installation Welding Activities Auto;aatic welding of the insert and withdraw lines to the control rod drive housing flange was observed. Of the 370 welds to be made, about 150 had been completed with two requiring repair. The welds are made to procedures WP300 and WS381. The pipe and socket are cleaned, the pipe is rolled into the socket, a measurement is made of socket depth, and the assembly is recleaned prior to welding.
After the weld is made, without addition of any filler, a visual inspection and liquid penetrant inspection to PE-1, Revision 6, is made. Then the documentation is audited. Weld Nos. 5439-I6B, 5431-I6B, and 5435-W4B were observed. DRR's 6654 and 6655 were issued to cover the welds requiring repairs. Any manual repair requires qualification of the welder making the repair. These welds are performed to the requirements of ASME Section III and V, 1971 Edition, Winter 1972 Addenda.
No items of noncompliance or deviations were identified.
3.
Penetration Installation and Reactor Vessel Holddown Bolts The following process line penetrations were observed.
Pen. No.
Ident.
Size System X-16B E:1-3144-14WO 12" process line Core Spray X-15 T'8-04-2098 4"
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Gas to Recombiner X-17 E11-3035 6"
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Residual Heat Removal X-43 G33-3096 6"
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These penetrations are required to meet the requirements of ASME Section III, 1971 Edition, Winter 1971 Addenda.
Penetration No. X-43 has a 6" process line and the guard pipe is 30" diameter x.500" thick. This penetration is about 6" from a concrete wall which is perpendicular to the containment. Upon close examination, the inspector found 3 ground out areas in the weld which could not be seen without getting down and looking up between the penetration and wall. There was no tag indicating that the weld was under repair. However, the paper work which existed in the office area showed that the weld was under repair. There would appear to be the chance for missing such an incomplete weld, particularly if the practice extends to dozens of welds in various areas of the plant.
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The base of the Reactor Vessel was observed to contain 60 bolts
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2-1/2" diameter x 10".
.'hese bolts were procured to drawing 731E800 and specified to ASTM A-490.
The area was clean and dry.
No items of noncompliance or deviations were identified.
Exit Interview The inspector met with licensee representatives-(denoted in the Persons Contacted paragraph) on July 9, 1981. The inspector summarized the purpose and findings of the inspection, which were acknowledged by the licensee.
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