IR 05000341/1979021
| ML19210E427 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/16/1979 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19210E421 | List: |
| References | |
| 50-341-79-21, NUDOCS 7912050022 | |
| Download: ML19210E427 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-341/'9-21 s
Docket No. 50-341 License No. CPPR-87 Licensee: The Detroit Edison Company 2000 Second Avenue Detroit, MI 48226 Facility Name:
Enrico Fermi Nuclear Power Station, Unit 2 Inspection At:
Fermi Site, Monroe, Michigan Inspection Conducted: October 4-5, 1979 l'.k-l l
Inspector:
C. M. Erb
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Approved By:
D. H. Danielson, Chief
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Engineering Support Section 2 Inspection Summary Inspection on October 4-5, 1979 (Report No. :^ '?1/79-21)
Areas Inspected: Welding repair of torus; reactor vessel nozzle modificatien; storage of reactor pressure vessel; 50.55(e) items. This inspection involved a total of 15 inspector hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS Persons Contacted Detroit Edison (DECO)
- W. M. Everett, Project Superintendent
- H. A. Walker, Project QA Engineer, Site
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- J.
E. Bragg, Systems Analyst
- W.
M. Adair, Field Engineer
- C.
Carter, QA Engineer
- J.
G. Bolt, Project QA Manager, Daniel International
- D.
L. Vandergrif t, QC Electrical Engineer, Daniel International
- M.
Albertin, Assistant Proj ect Manager, Daniel International W. Alton, Engineer-Electrical, Sargent E Lundy N. Gnellings, Site QC Supervisor, Reactor Controls, Incorporated
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- Denotes those present at the exit meeting.
Licensee Action on Previous Inspection Findings (open) Unresolved Item (341/79-03-06):
Spent fuel storage racks.
Since many welas in these racks will require repair, the licensee stated that stainless steel high density racks may be ordered to replace the aluminum racks. A firm decision has not been made in this matter.
Licensee Action on 50.55(e) Items (0 pen) 50.55(e) Item (341/78-XX-05): Torus structure repair. A change was made to the Fermi FSAR requiring extensive strengthening of the torus structure. Inside ring girder welds to the skin were increased from 5/16" fillet to 3/4".
Shortly after the increased weld was added, cracks were noted at the toe of the weld. After an extensive investi-gation, the cracks were ascribed to hydrogen.
The follo ing steps were taken to correct the problem. Oracks were. ground out and a new weld progedure requiring (1) baked lectrodes 600-800 F.,
(2) preheat 300-400 F.,
(3) low heat input into the weld, (4) preheat continued after end of weld for certain time, (5) buttering ground out areas with MT and UT at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after end of bake period was implemented.
This procedure to date has apparently cured the cracking problem. However, with extensive
'1. ding yet to be done on the outside of the terus shell, a final inspection for cracks and inside of she~1 will be necessary after all welding is complete.
This item cannot be closed for several months, as the design for hold downs on the outside has not been finalized.
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The original primary containment was "N" stamped to conform to ASME Section III, 1968 Edition, Summer 1969 Addenda. ASME Section XI,1974 Edition, Winter 1976 Addenda applies to this modification work.
The containment modification used design rules and stress limits of "MC"Section III, 1977 Edition, Summer 1977 Addenda.
(open) 50.55(e) Item (341/79-XX-04):
SA-36 plate steel for electrical supports. A problem with laminations in 3/4" thick plate was identified in the RHR building.
Inspection by grinding of the galvanize on the
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plate edge has since shown that the problem is in other plate thick-nesses and will require further inspection in the Auxiliary Building and Reactor Building. At present, all plates being fabricated are visually examined, preferably before galvanize.
The licensee said they were ble to separate laminated plate in this way.
For installed plates, it '211 require either grinding plate edges and a visual or ultrasonic test.
The method here is not finalized.
An analysis made of one laminated plate revealed a different problem, namely, mixed steel. Chemical analysis and tensile tests gave the following results compared to A-36 requirements.
Ca rbon Sulfur Tensile Strength
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A-36 0.25 max.
0.05 max.
58,000 psi min.
Other 0.07 0.07 48,600 psi The "other" off analysis steel is known by heat number and constitutes 87 plates. All but 15 of the plates have been found and scrapped.
Until all the =aterial has been scrapped, this item will remain open.
(Closed) 50.55(e) Item (341/78-XX-04): Core Spray System impeller repair. Byron-Jackson, the pump manufacturer, recommended that nothing be done to the "B" (1 crack) and "C" (3 cracks) impellers. However, G. E., the supplier, recommended that the cracks be removed by carefully grinding to a radius. This was done on an NCR by Wismer & Becker and was inspected by the NRC inspector.
(open) 50.55(e) Item (341/79-XX-01): Handling damage to Core Spray System pump motor. Part No. XXXX002, a Core Spray 800 H.P. motor was damaged in handling and sent back to General Electric, to ascertain the extent of the damage. It was determined that the rotor was bent and the pump is being rebuilt by G. E.
This item remains open pending review of the motor testing results.
Functional or Program Areas Inspected 1.
Status of Reactor Vessel and Internals Work The reactor vessel entrances were locked and adequate controls were in place to protect it.
General Electric Installation and Service Engineering lef t the site in September 1979.
The following is the
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approximate status of work remaining in the subject area.
The QC
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supervisor for G. E. was auditing the work packages completed to date and turning them over to the licensee.
Work to be done:
Install 6 new Feedwater System safe ends with piston ring a.
seals to thermal sleeve, install spargers and connect to safe end.
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Weld in pipe from two Core Spray System spargers to nozzle safe ends.
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The insert and withdraw lines in CRD System are to be installed from modules to penetrations and from CRD housings to penetrations.
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The CRD Scram System is to be completed.
e.
The CRD System return nozzle is capped.
It may be modified to attach to another liquid control line.
2.
Plastic Sealant for Safety Related HVAC Systems
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The inspector asked the licensee what sealant was being used, and whether the material was qualified for the use.
Robert Irsay, the contractor for these systems is using G. E. No. 1200, but qualifi-cation records apparently had not been forwarded to the Licensee.
The licensee stated they would secure whatever information is available. This item is an unresolved matter.
(341/79-21-01)
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncom-pliance, or deviations. An unresolved item disclosed during the inspection is discussed in Paragraph 2.
Exit Interview The inspector met with staff representatives (denoted in Persons Contacted paragraph) at the conclusion of the inspection on October 5, 1979.
The inspector summarized the scope and findings of the inspection, which were acknowledged by the licensee.
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