IR 05000456/1979009
| ML19249E777 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 08/21/1979 |
| From: | Danielson D, Erb C, Liverhore H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19249E776 | List: |
| References | |
| 50-456-79-09, 50-456-79-9, 50-457-79-09, 50-457-79-9, NUDOCS 7910020409 | |
| Download: ML19249E777 (4) | |
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$ , , U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-456/79-09; 50-457/79-09 Docket No. 50-456; 50-457 License No. CPPR-132; CPPR-133 Licennee: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name: Braidwood Station, Units 1 and 2 Inspection At: Braidwood Site Inspection Conducted: August 7-9, 1979 M Inspectors: C. M.
Erb [ 7f~
/ . & I i H.
Livermore [[/d// */[ . Approved By: D 8 2I ' Engineering Support Section 2 Inspection Summary Inspection on Aunust 7-9, 1979 (Report No. 50-456/79-09; 50-457/79-09) Areas Inspected: Observed canopy seal weld of reactor vessel head adaptor and control rod drive housing guide; welding of recirculation system piping weld inside dry well; placing of first vertical tendon in contain-ment; records on moving and setting Unit I reactor pressure vessel.
The inspection involved a total of 42 on site inspector-hours by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
q 7 910020 4 o7 1079 096
. ' s . DETAILS Persons Contacted Licensee (CECO) R. Cosaro, Superintendent Construction J. A. Pomoly, Supervisor QA J. W. Schlunz, Lead Structural Field Engineer C.-Mennecke, Lead Electrical Field Engineer R. J. Farr, QA Engineer J. T. Merwin, Lead Mechanical Engineer M. J. Callahan, QA Engineer K. C. Schleiter, Construction Engineer S. Gacomis, Ouality Assurance C. Gray, Station Construction Other Personnel M. Hrnyak, Electrical Construction, L. K. Comstock D. Craven, Construction, G.
K. Newberg T. J. Pruitt, Manager QA/QC, Nisco J. F. Burke, QC Inspector, Napoleon Steel T. Rich, QA Engineer, Napoleon Steel
- C. Zavada, QC Inspector, Napoleon Steel
- M.
Milem, Site Manager, Nisco D. R. Rayka, Construction Superintendent, Inryco
- Denotes those not present at the erit in t e rv i. ew.
, Licensee Action on Previous Inspection Finc'3gs (0 pen) Unresolved Item (456/78-10-01; 457/78-10-01): An NCR was issued against the Unit 1 and Unit 2 polar cranes because of poor welding and unacceptable paint.
The licensee stated that the welding repair had been accomp:Eshed, but the records were not available to the inspector.
The painting for Unit 2 will be performed later after the Unit 2 reactor vessel has been set.
The Unit 1 vessel was set about two months ago.
Functional or Program Areas Inspected 1.
Canopy Seal on CRDM Assembly This assembly is performed by Nisco. The assembly is held together by a screw thread which is torqued to 300 ft.lbs.
The canopy seal weld with a Y consumable insert tacked to one side of the mating members is next made.
Procedure SWPS 1328 utilizing Dyna Surge automatic equipment is used to make the veld without filler metal being added. Welder No. 8373 was qualified for the automatic weld and also for the manual tack to procedure WPS 80-2.
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. '. A penetrant test is made of the weld prep and of the final weld to procedure ES-100-2.
Procedure No. 132-2 is qualified for use when ' repairs to the real weld are necessary.
Each assembly is given a hydro at 3105-3220 psi after ccmpletion of the weld.
The pressure gauge for the hydro equipment bore a sticker indicating calibration on May 28, 1979.
This assembly is Class 1 and is made to the requirements of ASME Section III, 1977 Edition.
No items of noncompliance or deviations were identified.
, 2.
Welding of Recirculation Pipe Welding by Phillips Getschow on joint No. M-196-LP-3-FW-1 was witnessed.
This Class I weld was inside the biological shield and was made to procedure IA-MA-88, Rev. 10, by qualified welders No.
418 and No. 105.
The welders were working in areas 180? apart and the base material was type 316 to type 304 stainless steel with a 308L consumable insert.
A penetrant test is made at the half way point of the weld to procedure QAP-1, Rev.
1.
Radiography is performed on the weld to procedure QC-RT-1, Rev. 10.
No icer..s of noncompliance or deviations were identified.
3.
Prestressing Placing of the first vertical tendon, No. V-1 was witnessed.
The Braidwood tendons are 170 wire tendons with wire supplied by a Netherlands company. S&L specification L-2721, Addendum 2 and Revision 2, applies to the prestressing work.
Inryco is training personnel and giving technical direction, while Napoleon Company is furnishing the labor for this operation.
Receiving records for No. 280, 281 and 282 tendons were examined.
A test certificate was on file from Nederlaudse Draadindustrie which listed the chemical and mechanical properties of the individual wires.
The button heading test was also acceptable.
NCR 103 was issued against tendon V-1, because the uncoiler was underpowered and the tendon was dropped so fast that the bands holding the coil and spaced at approximate 8 foot intervals could not be removed.
The uncoiler could not reverse and pull the 75 feet of tendon out of its sbtath to remove the bands.
Changes will be made to the uncoiler to better control the speed of insertion and also to enable tendons to bc pulled back out of the cavity if required.
No items of noncompliance or deviations were identified.
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., '. 4.
Setting of Reactor Pressure Vessel - Unit 1 , Reliance Trucking Company performed this operation to procedure No. 114, Rev. 2.
The testing of the construction hoist equipment in the containment building was pertormed to procedure No. 188, Rev. 3.
The check sheets for the above operations covering, NDT, visual, erection, installation of the lift beam, and other stepe were signed off by responsible personnel.
While shipping the Unit I steam generator from Byron site to Braidwood, a blowdown nozzle sas sheared off.
The steam generator is now set - in place. However, Westinghouse is making the following modification to each of four stcan generators on site: a.
Add seven cletn out hand holes.
b.
Add one wet it.y up nozzle.
TF licensee stated tha W will replace the blowdown nozzle when the above modification is performed.
This is an unresolved item.
(456/79-09-01) The Unit 2 reactor vessel has been delivered to the Dresden barge slip and will be moved to the Braidwood site sometime in October, 1979.
No items of noncon-pliance 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. Unresclved items disclosed during the inspection are discussed in Paragraph 4.
Exit Meeting The inspector met with licensee representatives (denoted in the Parsons Contacted paragraph) at the conclusion of the inspection on August 9, 1979. The inspectorn summarized the scope and findings of the inspection.
The inspectors stated housekeeping was poor at the site.
The areas of most concern were at the 426 foot level where large quantities of pipe cable tray hangers, rebar and electrical equipment are distributed.
The general disorder makes damage to safety related equipment quite likely as well as loss of identification of certain materials.
It appears that each craft should be accountable for the care and protection of those items in their area of responsiblity. The licensee stated that steps would be taken to improve cleanliness and to tighten up on care and protection of equip nent by the craf ts.
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