IR 05000456/1978007

IE Inspec Repts 50-456/78-07 & 50-457/78-07 on 780706-0810 During Which No Items of Noncompliance Were Noted.Major Areas Inspected Included:Quality Assurance Implementing Procedures & Quality Records for Personnel Access

ML20197C225
Person / Time
Site:	Braidwood
Issue date:	10/18/1978
From:	Hayes D, Clint Jones NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20197C209	List: IR 05000456/1978007 ML20197C204
References
50-456-78-07, 50-456-78-7, 50-457-78-07, 50-457-78-7, NUDOCS 7811210027
Download: ML20197C225 (5)

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T U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION Ill Report No. 50-456/78-07; 50-457/78-07 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, Units 1 and 2 l

Inspection At: Braidwood Site, Braidwood IL I Inspection Conducted: July 6-7, 13-14, and August 9-10, 1978 0$ ""

Inspector: C. ones M - / '/ ~76 Approved by: D. W. Hayes, Chief )/

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Projects Section v

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Inspection Summarv

.' 1 Inspection on July 6-7, 13-14, and August 9-10, 1978 l (Reports No. 50-456/78-07: 50-457/78-07) l Areas Inspected: Quality assurence implementing procedures and quality l records for personnel access containment penetrations; status of construc- l tion, construction schedule and work in progress; quality assurance l records for the Essential Service Water Pond, and review of previously identified items of noncompliance and unresolved items. This inspection i I

involved a total of 48 inspector-hours onsite by one NRC inspecto Results: No items of noncompliance or deviations were identifie I

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, DETAILS Persons Contacted Commonwealth Edison Company

• T. E. Quaka, QA Supervisor l

• J. T. Merwin, Lead Mechanical Engineer i

• R. Cesaro, Project Engineer l

• M. Trumbill, QA Engineer i

• H. T. Cobbs, QA Engineer l

• T. A. Bobic, QA Engineer S. K. Tubbs, AW Engineer W. Vahle, Scheduling A. Carillo, Station Construction Department M. J. Callahan, QA Engineer Chicago Bridge and Iron Company

• R. D. Rogers, QA Supervisor D. A. Soehrer, Project Superintendent W. A. Wagnen, Assistant Welding and Quality Assurance, Manager - Nuclear l G. Mahan, Nuclear Welding Engineer l

l Pittsburg Testing Laboratory l l

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• M. R. Tallent, Site Manager l

• denotes those,present at the exit intervie l l

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f Construction Schedule Work is scheduled for Units 1 and 2 as follows:

Work to be done Estimated Start Date Piping in Containment #1 10-1-78 Cable pan erection Containment #1 10-1-78 Reactor pressure boundry piping, Unit #1 1-1-79 Electrical cable pulling In Progress Reactor coolant pumps and pressurizer 11-78 In Progress Polar crane 12-78, scheduled delivery Electrical penetrations Receive reactor vessel 10-78 Work in Unit #2 lags that in Unit #1 by approximately one to nine months as scheduled to expedite construction activities and manpower loading Licensee Action on Previous Inspection Findings (Closed) Unresolved item (458/78-04-02; 457/78-04-01) Small areas of honeycomb as described in the Gus K. Newberg QA Manual. The inspector observed small areas of honeycomb and rock pockets that remained after the forms had been removed. The contractor revised checklist 114 of Section 12 of the QA Fbnua. to provide a record of such defects for subsequent repair. The inspector reviewed the list of defects that had been compiled to update the procedure. He observed the completed repairs j for one defect documented on Gus K. Newberg Nonconformance Report No. 213-158 at elevation 397-0 on lines N and 2 Based on the repair of this defect and the minor nature of the other defects listed this item is considered diose (Closed) Unresolved item (456/78-03-01; 457/78-03-01) Use of fire resistant cabinets for temporary retention of safety related documentation. The inspector visually observed the cabinets being used by E. C. Ernst, and reviewed the safety analysis for the cabinet used by Canonie for storage of safety related records and considered them to be adequate for the short-term, fire-proof, water resistant storage intende i (Closed) Unresolved item (456/78-01) Calibration certification on 40 thermocouples supplied for recording heat treatment measurements. The l inspector reviewed the Calibration Certification for 40 thermocouples supplied by Western Stress Incorporated for stress relieving at Braidwood Station. The. thermocouple Calibration was referenced to a standard TC number TE-F-7501. Accuracy was stated to be within the terms of OPTS-68, with reference point held at 0 Maximum error recorded at 1200 F is

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. Functional or Program Areas Inspected l Lakes, Dams and Canals, Units 1 and 2 (IE Inspection Reports

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Number 50-456/78-03 and Number 50-357/78-03)

! The inspector had previously reviewed the QA implementing pro-j cedures and the records concerning instrument calibration and i

QC inspection. The inspector concentrated on record revie He observed during this inspection that excavation of the pond j had essentially been completed and that final grading of the j l 10:1 slopo of pond perimeter to lake bottom was in progres i i Final survey of the pond dimensions by a registered land surveyor I was nearing completio ;

The inspector toured a portion of the pond and observed 4 pat grade

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elevations conformed to the specified elevations of 584'-6",

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indicated by the survey stakes.

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No items of noncompliance or deviations were identified.

Containment Penetrations - Units 1 and 2

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The inspector selected to review the personnel emergency air locks as one of the designated penetration assemblies to be inspecte Review of Implementing QA Procedures The inspector reviewed the supplementing quality procedures for installing the emergency personnel locks in the containment building. The Nuclear Quality Assurance Manual, previously reviewed, included general installation procedures for the per-sonnel locks. Detailed instructions were included on the vendor drawings. The personnel locks were fabricated by Chicago Bridge and Iron Company in Birmingham, Alabana, for Commonwealth Edison Company's Braidwood Plan Previous reviews of the QA Manual indicated its agreement with the licensee's specifications and ASME B and PV code,Section III requirement The air locks were fabricated, heat treated and tested at the sho The field work remaining was to align the personnel lock with the barrel penetration assembly and complete the single circumferential weld joining the personnel lock to the containment. The single weld was designated as seam A. The weld prep was a single bevel on the inside with a 75 angl l nem 7 7 - - % g.gg,

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The alignment on the hatch for Unit 1 was very good and was well l below the code allowabl The appearance of the completed weld 1 was good. Five RT film of the completed weld were selected at random for review by the inspector. No defects were observe The film had been read by the contractor, CB & I, by the authorized inspector and the licensee's representative. One defect had been successfully repaire The weld was accepted based on the final RT, the only NDT specifie Record Review The air locks were fabricated in Birmingham, Alabama and shipped as a unit to the reactor site. The quality documentation was provided for review and then shipped to Houston, Texas for micro-filmin The air locks were received on site with a shop release for shipment check list which provided space to identify the shipment, describ the shipment and provide space for signoff of the QC inspectors shipping and receiving the shipment. This sheet also provided certification f or the air lock In addition the certificate was accompanied by a Form N-1A MANUFACTURERS' DATA REPORT FOR NUCLEAR VESSEL Unresolved Items Unresolved items are matters on which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations. There are no unresolved items in this repor Exit Interview The inspector met with the licensee representatives (denoted under Persons Contacted) on July 7, 14 and August 10, at the conclusion of each inspection and summarized the scope and findings of the inspectio l l

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