IR 05000461/1979007
| ML19208B601 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 07/18/1979 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19208B595 | List: |
| References | |
| 50-461-79-07, 50-461-79-7, NUDOCS 7909210055 | |
| Download: ML19208B601 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMEh7
REGION III
Report No. 50-461/79-07 Docket No. 50-461 License No. CPPR-137 Licensee:
Illinois Power Company 500 South 27th Street Decatur, IL 62525 Facility Name:
Clinton Nuclear Power Station, Unit 1 Inspection At:
Clinton Site Inspection Conducted: June 26-28, 1979 C.w. 64 e
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Inspector:
C. M. Erb 7//P/ 79 h/bMr.
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Approved By:
D. H. Danielson, Chief 7!/ I 7 /
Engineering Support Section 2 Inspection Summary Inspection on June 26-28, 1979 (Report No. 50-461/79-07)
Areas Inspected:
Observe replacement of recirculation inlet nozzle to safe end welds; examination of weld data sheets and NDE results for recirculation replacement welds; radiographic results from bio shield welds; observation of a special safety related concrete pour. The inspection involved a total of 18 inspector-hours on site by one inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS Persons Contacted Licensee Employees (IPCo)
G. M. Brashear, Site Manager R. S. Unks, Director, QA J. F. Hampton, Supervisor, QA - Site R. J. Canfield, Construction Supervisor E. E. Connon, Assistant Supervisor Construction D. E. Korneman, Supervisor, Mechanical Construction M. Tindill, QA Engineer R. W. Folck, QA Specialist, Concrete Structural
T. Selva, Manager, Quality and Technical Services J. Linehan, Manager QC T. F. Walker, Senior QC Engineer W. Woolery, Technical Services, Welding J. W. Smart, Senior QA Engineer
- M.
Daniell, Technical Services
- T. Wilmott, Supervisor, NDE General Electric Company (GE)
S. G. Hall, Site QC Representative Reactor Controls (RCI)
J. Klaus, Site Manager C. Guarneri, Supervisor, QC Hartford Steam Boiler and Insurance Company (HSB)
M. J. King, Authorized Nuclear Inspector (ANI)
- Denotes those not present at the exit interview.
Functional or Program Areas Inspected 1.
Primary Coolant Recirculation Inlet Nozzle Welds
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The inspector examined the surface and contour of the above welds made by RCI and found them to be acceptable. All ten nozzle to safe end welds have been completed and NDE performed.
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The ten internal thermal sleeve to safe end welds have been made,
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using the Dimetrics automatic welding machine. These welds required practically no rework and were completed in four days. These welds are stainless steel to stainless steel and are given visual and penetrant examinations for acceptance.
Radiographs of welds at azimuth 30, 60, and 270 between the vessel nozzles and safe ends were examined. NCR 16-49 had been issued against the 270 weld, because of a slag indication in excess of the code allowable. The weld required two separate repairs with a weld repair sheet for each one.
These welds are Inconel to Inconel and use a consumable insert. The weld was qualified to procedure PRS-W-2 and involves a root by the Gas Tungsten Arc Welding process (GTAW) and completion by the Shielded Metal Arc process (SMAW). The welds are penetrant examined to procedure PE-2, radiographed to procedure RE-2 and ultrasonically examined to procedure UE-2.
Qualified welders making these welds are identified on the weld data sheets.
Hold points were indicated by the authorized nuclear inspector (ANI)
and the fabrication is being done to ASME Section XI, 1974 Edition, Winter 1976 Addenda.
Mock-up qualification for the brace arm to jet pump diffuser welds has begun and a PT of the mock-up was witnessed.
No items of noncompliance or deviations were identified.
2.
Radiographic Inspection of Bio Shield Welds Film for weld OV-1, M27RS60, which was an outside vertical weld 1 1/2" thick was examined. There were 14 exposures for this weld using a.035 penetrameter. These welds are examined to the require-ments of ASME Section III, 1974 Edition, Summer 1975 Addenda and were ground on both the inside and outside surfaces.
Film for weld 1-H, M27RS59 consisted of 13 exposures and was a Circumferential, unground weld 1" thick. A repair for excessive slag was made on area 65-66 and a repair for lack of fusion was made in Area 6-7.
Both the repairs met ASME Code acceptance standards.
These welds are required to be RT inspected only, but PT or MT may be used to aid in locating defects for repair.
No items of noncompliance or deviations were identified,.
3.
Concrete Pour in Bio Shield
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Pour No. CT-BW-1 of approxima;ely 80 yards was observed. This concrete was poured into the cteel Bio Shield welduent and a number of changes were made due to reinforcing plates and holes in steel diaphragm bracing.
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ECN1150 from Sargent and Lundy (S&L) which is appended to specification
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K-2944 is applicable to this pour.
Some changes were as follows:
a.
Type 1 cement may be used.
b.
Melmint a plasticizer to be added at pump with deposition of concrete to be made within an hour.
c.
Consolidation by vibrators deleted.
d.
Air content 4.0-7.0%.
e.
Slump 3 1/2 1 1 1/2 grior to addition of Melmint.
f.
Water temperature 75 max section less than 2 1/2".
Water temperature 70 max section 2 1/2-6".
Tests on the first five truck loads, each 8 yards, were as follows:
Slump Air Melmint Temperature Comment No. 1 8 1/4"
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Reject No. 2 6 1/4"
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Reject No. 3 7 1/2" Reject
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No. 4 6 1/2"
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Reject No. 5 4 1/4" 5.6 %
888 oz.
Accept The strength sample (4,000 lb) was placed in the cure box for 16-24 hours at 60 -80 F and then removed to the laboratory cure room.
No items of noncompliance or deviations were identified.
4.
Verification of Concrete Vibrator Testing The licensee showed the inspector that BAP 3.1.1, PCR 55-79, approved June 13, 1979, requires a calibration check by tachometer on vibrators used in safety related pours of concrete. Records for fifteen pours using from two to six vibrators each were examined and vibration figures for each vibrator, which were identified by number were given.
No items of noncompliance or deviations were identified.
Exit Interview The inspector met with site personnel (shown under Persons Contacted paragraph) at the conclusion of the inspection on June 28, 1979. The inspector summarized the scope and findings of the inspection, which were acknowledged by the licensee.
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