IR 05000456/1980013
| ML19351E778 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/12/1980 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19351E776 | List: |
| References | |
| 50-456-80-13, 50-457-80-12, NUDOCS 8012190227 | |
| Download: ML19351E778 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION
's 0FFICE OF INSPECTION AND ENFORCEMENT
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REGION III
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i Reports No. 50-456/80-13; 50-457/80-12
Docket Nos. 50-456; 50-457 Licenses No. CPPR-132; CPPR-133
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Licensee: Commonwealth Edison Company
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P. O. Box 767 Chicago, IL 60690 A
Facility Name: Braidwood Station, Units 1 and 2 Inspection At: Braidwood Site, Braidwood, IL Inspection Conducted: October 22 - 23, 1980
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Inspector:
IM. Erb
)[/p/, /~, lifd
WbMYY M Approved By:
D. H. Danielson, Chief l' f ' A (f 0
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Engineering Support Section 2
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Inspection on October 22 - 23, 1980 (Reports No. 50-456/80-13; 50-457/80-12)
Areas Inspected: Preparation for reactor vessel move to containment; steam generator modification; class 1 valve documentation; previous inspection i
findings. The inspection involved a total of 13 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS'
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Persons Contacted Commonwealth Edison Company R. Cosaro, Project Superintendent
- T. R. Sommerfield, QA Supervisor
- E. F. Wilmere, QA Senior Inspector
- J.-T. Merwin, Project Mechanical Supervisor
- D. M. Kapinus, QA-Engineer
- W. Carlson, Station Construction J, Hawkinson, Construction Engineer Other Personnel L. Shoults, Site Manager, Westinghouse J. Feimster, Engineer, Westinghouse
- Denotes those present at the exit interview.
Licensee Action on Previous Inspection Findings (Closed)_ Unresolved Item (456/78-10-01; 457/78-10-01) Action was taken on both cranes by the licensee on NCR's 110 and 125 regarding repair welding and drilling of main drum. These items are closed for both units. However,
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NCR 134 regarding poor paint'is still open and will not be closed until this work is done.
Both cranes are installed, so scaffolding will be necessary for part of the repainting program.
(0 pen) Unresolved Item (456/79-09-01) Repair blowdown nozzle and other
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damage to steam generator S/N 1714 incurred during move from Byron site.
This work will be accomplished by W during the installation of the sur--
veillance ports, which should be complete in December 1980.
(Closed) Unresolved Item (457/79-04-01) Unit 2 polar crane is installed
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and working.
The polar crane has been reworked and now meets the'manu-facturers specification requirements.
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(Closed) Unresolved Item (456/79-04-02) The. main steam isolation valves for both Unit _1 and Unit 2 manufactured by Anchor-Darling are now housed
in a temporary shelter of Visqueen. The previous exposed condition for the valves has been remedied.
t Functional or Program Areas Inspected 1.
Setting of Reactor Pressure Vessel and Steam Generator Unit 2
The following procedures frem Reliance Truck were examined for trans-porting various components to the site.
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Procedure 101, Rev. 0 Off loading steam generator from barge o
and transporting to temporary storage.
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Procedure 102, Rev. 1 Off leading reactor vessel from barge and transporting to temporary storage.
Procedure 103, Rev._1 Off leading reactor vessel head from barge and transporting to temporary storage.
Procedure 104, Rev. 1 Off leading pressurizer from barge and transporting to temporary storage.
Procedure 113, Rev. 1 Moving steam generator from job site and setting in containment.
Procedure.118, Rev. 3 Load Testing construction hoist equipment in containment building.
Procedure 119, Rev. 2 Load testing construction hoist equipment in containment building.
Procedure 3, Rev. O Document Control.
Procedure 5, Rev. O Control Non-conforming Materials and Parts.
Procedure 6, Rev. O Corrective Action.
Procedure 8, Rev. O Audits.
The above precedures require NDE inspection by Level II or higher inspectors. A visual examination is performed by Reliance Truck Company and CECO.
The four Unit 2 generators are enroute from Tampa and are scheduled to be delivered at the Dresden barge dock this year.
No items of. noncompliance or deviations were identified.
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Steam Generator Modification - Unit 1 The generators will have seven new openings made for surveillance and one special nozzle for wet layup. W has developed the welding procedures, stress relief, and NDT required. The measures will be similar to those performed at Byron which were examined and accepted.
I Repair on the damaged nozzles on steam generator No. 1714 will be per-formed by W at the same time the above work is.done.
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No items of noncompliance or deviations were identified.
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Safety Related Components Unit 1 and 2
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~The documentation for several valves was examined as well as the
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hardware. Following is pertinent information on these valves.
Release-Size & Type Mfr.
Class Applicable ASME Code QR-25411 M.0. Gate Valve,-10" E NPV-1 Sect. III, 1974,'5'14, Cases 1553-1, 1649
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E NPV-1
. Sect. III, 1974, 574, Case QR-23271 Swing Check, 10" 1553-1
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K-4162 M.0. Gate, 12" E.
NPV-1.
Sect. III, 1974, S74 The required QC documentation was in order and the valves appeared to be acceptable. Limitorque Valve No. K-4162 was lying with the gear l
box elevated above the electrical gear. The licensee was asked to investigate whether this valve and others should be positioned dif-ferently since the grease scals may not-protect the electrical gear in certain positions.
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No items of noncompliance or deviations were identified.
Exit Interview The inspector met with licensee representatives (denoted under Persons-Contacted paragraph) at the conclusion of the inspection on October 23, 1980. The inspector summarized the purpose and findings of the inspection,-
which were acknowledged by the licensee.
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