IR 05000456/1979011
| ML19259D558 | |
| Person / Time | |
|---|---|
| Site: | Braidwood |
| Issue date: | 09/17/1979 |
| From: | Danielson D, Eric Lee NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19259D557 | List: |
| References | |
| 50-456-79-11, 50-457-79-11, NUDOCS 7910250080 | |
| Download: ML19259D558 (4) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-456/79-11; 50-457/79-11 Docket No. 50-456; 50-457 License No. CPPR-132; CPPR-133 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name: Braidwood Nuclear Power Station, Uaits 1 and 2 Inspection At: Braidwood Site, Braidwood, Illinois Inspection Conducted: September 12, 1979
),'J 9 7/7/
Inspectors:
E. W.
ee
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Accompanied By:
D. H. Danielson M ut b
Approved by:
D. H. Danielson, Chief 7/2/77_
Engineering Support Section 2
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Inspection Summary Inspection on September 12, 1979 (Report No. 50-546/79-11; 50-547/79-11)
Areas Inspected: Reactor Coolant Pressure Boundary and Safety Related Piping work activities, welding and procedures. The inspection involved seven inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS Persons Contacted Principal Licensee Personnel R. Cosaro, Project Superintendent
- R. Redinger, Field Engineer
- J.
Schlinz, Station Construction Lead Structural Engineer
- Denotes those present at the exit interview.
Licensee Action on Previous Inspection Findings (Open) Noncompliance Item (457/78-01) Surveillance of valves: The inspector reviewed the surveillance record of valves stored at warehouse No. 2 and established surveillances are being performed. However, differences still exist between surveillance criteria and the surveillance signoff sheet relative to the surveillance requirement of desiccant.
Functional or Program Areas Inspected 1.
Reactor Coolant Pressure Boundary Piping - Observation of Work and Work Activities (Unit 1)
a.
Handling and protection of Residual Heat Removal System Spool No.
RH8-6.
b.
Weld end preparation of Safety Injection System Weld No.
SI-5-FW10.
c.
Liquid penetrant examination of the weld end of Safety Injection System Weld No. SI-5-FW10.
The inspector determined that work activities were performed in accordance with applicable procedures, personnel performed the PT examination was currently qualified and good construction practices were adhered to.
No items of noncompliance or deviations were identified.
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2.
Reactor Coolant Pressure Boundary and Safety Related Piping -
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Welding Material Control (Units 1 and 2)
a.
Review of Documents The inspector reviewed the folloaing documents:
(1) Phillips, Getschow Company (PG) Procedure No. QCP-B3, Revision 2, " Control of Material Requisitions and Purchase Orders."
(2) PG Proccdure No. QCP-B8, Revision 3, " Issuance and Control of We!$ing Material."
(3) PG Procedure No. QCP-B9, Revision 1, " Receiving Inspection of Icems, Material or Equipment."
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(4) Purchase Oruer, Receiving Inspection Report and Certified Material Test Report for E308-16 welding rod with heat No.
586062 and lot No. 3287238; ER 303 welding rod with heat No. C1858, and lot No. 32613; E7018 welding rod with heat No. 411H7461, lot No. 02-1-E930T and heat No. 422H7301, lot No. 02-1-F914Q and E70S-2 welding rod with heat No. 065094.
It was determined that the above documents met the PSAR, 10 CFR 50, Appendix B and the applicable code requirements.
b.
Control of Materials The inspector toured the welding material issuing station located at PG's main warehouse. It was determined that (1) the welding materials are properly identified and segregated; (2)
the temperature of the rod ovens is maintained; (3) records are properly kept; and (4) issuance and return of welding materials are controlled in accordance with approved procedures.
No items of noncompliance or deviations were identified.
3.
Reactor Coolant Pressure Boundary Piping - Observation of Welding Activities (Unit 1)
The inspector observed weiding of Residual Heat Removal System Weld No. RH-1-FW8.
It was determined that (1) work was conducted in accordance with traveller; (2) proper welding materials were used; (3) welding procedure requirements were met; (4) work area was free of weld rod-stubs; and (5) physical appearance was acceptable.
No items of noncompliance or deviations were identified.
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4.
Safety Related Piping - Observation of Work and Work Activities
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Unit 1)
The inspectcc observed the fit-up of Containment Spray System Weld No.
CS-7-FW3.
It was determined that welding procedure requirements were met and tack weld was performed by qualified welder.
No items of noncompliance or deviations were identified.
5.
Reactor Coolant Pressure Boundary and Safety Related Piping - Welder Qualification (Unit 1 and 2)
The inspector reviewed the following documents:
a.
PG Procedure No. QAP-13, Revision 0, including Supplement.,
" Qualification of Welders and Welding Procedures."
b.
Qualification of welders with I. D. Nos. 143, 312 and 429.
The inspector determined that the above documents met the require-ments of ASME B & PV Code Section IX.
No items of noncompliance or deviations were identified.
6.
Safety Related Piping - Special Welding Applications (Unit 1)
The inspector observed removal of defects of Containment Spray System Weld No. CS9-FW34 by grinding. It was determined procedure requirements were met.
No items of noncompliance or deviations were identified.
Exit Interview The inspector met with licensee representatives (denoted in Persons Contacted paragraph) at the conclusion of the inspection on September 12, 1979. The inspector summarized the scope and findings of the inspection.
The licensee acknowledged the information.
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