IR 05000456/1980040

Insp Rept 50-456/80-40 on 860805,07 & 19-21.No Violations or Deviations Noted.Major Areas Inspected:Verification of as-built Conditions Associated W/Structural Installations & Onsite Design Activities

ML20210H236
Person / Time
Site:	Braidwood
Issue date:	09/19/1986
From:	Danielson D, Liu W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20210H217	List: IR 05000456/1980040 IR 05000456/1986040
References
50-456-86-40, NUDOCS 8609260106
Download: ML20210H236 (7)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-456/86040(DRS)

Docket No. 50-456 License No. CPPR-132 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Braidwood. Station, Unit 1 Inspection At: Braidwood Site, Braidwood, IL Inspection Conducted: August 5-7 and 19-21, 1986 Inspector- . C. Liu O Date Approved By: D. H. Danielson, Chief O Materials and Processes Section Date Inspection Summary Inspection on August 5-7 and 19-21, 1986 (Report No. 50-456/86040(DRS))

Areas Inspected: Routine safety inspection of the verification of as-built conditions associated with structural installations (37051), and onsite design activities as.they relate to structural and mechanical construction (37055).

Results: No violations or deviations were identifie PDR ADOCK 05000456 G PDR

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DETAILS 1. Persons Contacted Commonwealth Edison Company (CECO)

• N. Kaushal, Project Field Engineering Manager

• E. Wendorf, Project Field Engineering Mechanical Supervisor

• A. D' Antonio, Regulatory Assurance

• D. Cecchett, Regulatory Assurance

• B. Acas, Construction Field Engineer

• D. Boone, Construction Field Engineer

• S. Mehta, Quality Assurance Sargent and Lundy Engineers (S&L)

• D. Gallagher, Project Manager, Field

• M. Flynn, Mechanical Field Coordinator

• A. Lundardini, Structural Field Coordinator F. Schallwane, Senior Structural Engineer NRC Inspectors

• W. Kropp, Senior Resident Inspector, Construction

• J. Muffett, Section Chief, Plant Systems The inspector also contacted and interviewed other contractor employee * Denotes those attending the final exit interview on August 21, 198 . Verification of As-Built Conditions (37051) Documents and Procedures Review The NRC inspector reviewed the relevant portions of the following documents and procedures pertaining to as-built structural-installations to determine whether appropriate procedures have been established and whether they comply with NRC requirements and the licensee's commitments. The NRC inspector noted that the procedures and. instructions appeared to be acceptable in terms of performing work activities associated with structural installation and inspectio * S&L Standard Specification for Fabrication of Structural Steel, May 10, 197 * S&L Standard Specification for Erection of Structural Steel, July 12, 196 __ _ -__

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• S&L General Structures Work, Section 5-2, Miscellaneous Metalwork, Structural Steelwork and Embedded Work, December 27, 198 * S&L Instruction PI-BB-08, Processing of Commonwealth Edison Site Non-conformance Reports, Onsite Contractors Non-conformance Reports, S&L Engineering Change Notices and Advance Design Changes, June 4, 198 * S&L Instruction PI-BB-13, Procedure for Processing Commonwealth Edison Company Field Change Requests (FCR's).

• G. K. Newberg Construction Company.QC Procedure Section 26, Welding, March 25, 198 * G. K. Newberg Construction Company QC Procedure Section 31, Erection and Inspection of Structural Steel, April 8, 198 b. Field Inspection of Structural Members The NRC inspector randomly selected the following structural beams and columns for a verification inspection to determine whether the as-built configurations are consistent with the design document * Containment Building:

Beam Nos. 31707, 31902, 42102, 51602, 62001, 70154, 70576, 72159 Column Nos. R31 at Elevation 404'-0" R33 at Elevation 404'-0"

• Auxiliary Building:

' Beam Nos. 8AB198, 8AB241, 8AB291N, 8AB261 8.5AB44N-2T, 8.5AB55N-2T, 8.5AB220 Column Nos. S-17 at Elevation 451'-0" V-18 at Elevation 451"-0" The above structural steel beams and columns were inspected with respect to the applicable design drawings for configuration, identification,-location / orientation, connections, member size, and damage / protection. In general, the appearance of the structures was acceptable and the structural members were installed in accordance with design document c. As-Built Structures Versus Final Load Check Program During the inspection, the NRC inspector noted that many structural members had been modified or redesigned as a result of the licensee's implementation of the final load check program. In the containment

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building for example,171 out of a total of 1423 structural members, including beams, columns, and braces had been modified in accordance with the latest design loads. Additionally, 1058 connections out of a total of 2846 had been modified in accordance with the latest design drawings. Structural evaluations in conjunction with the final load design calculations and field inspection of structural members is also addressed in Inspection Report No. 50-456/8603 Field _Insyection of Pipe Hangers During the field inspection of structural members, the NRC inspector also performed a visual examination of pipe hangers in the adjacent area to determine whether these hangers had properly been installed in accordance with established procedures. The NRC inspector noted that a discrepancy was identified on pipe hanger 1WO31012R, Revision B, in the chilled water system. This hanger was designed to withstand a vertical force of 1,792 pounds during the emergency condition. Upon inspection it was found that the hanger had a loose turnbuckle such that the hanger was not load bearing and a 7/16 inch gap was observed between the connections. This safety-related pipe hanger.had previously been inspected by the licensee's QC inspectors in accordance with the final linewalk verification checklist which requires that all nuts, bolts, turnbuckles, etc. be verified. The NRC inspector held discussions with licensee's representatives regarding the above concerns. Discrepancy Report No. DR-5436F and Nonconformance Report No. 6834 were subsequently issued as a result of the NRC's finding. In addition, four hangers in the adjacent area were reinspected by the licensee's QC inspector with no discrep-ancies being identified. -This activity was documented in Monitoring Report No. 13,354. The licensee also selected 27 additional hangers for further evaluation, as documented in Monitoring Report No. 13,40 Results of the above hanger reinspection revealed that no similar occurrences were identified. This matter is believed to be an isolated occurrence and is considered resolve Within the areas inspected, no violations or deviations were identifie . Onsite__DesignActivities (37055)

- Design Procedures Review Sargent and Lundy is the major organization responsible for onsite design activities associated with the construction of the Braidwood facility. S&L's engineering personnel are involved in various activities in the areas of piping stress analysis, pipe support design, and civil / structural modifications. The following procedures and instructions were selected for review:

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• S&L's DC-ST-03-BY/BR, Structural Project Design Criteria, Section 8: Codes, Standards, References, Design Reports, and Procedures, Revision 18, July 22, 198 * Structural Project Design Criteria, Section 10: Project Loads and Load Combinations, Revision 18, July 22, 198 * Structural Project Design Criteria, Section 37: Mechanical Component' Support Design Criteria, Revision 18, July 22, 198 * Project Instruction PI-BB-25, Activities of the Onsite Structural Design Group, Revision 2, June 4, 198 * Project Instruction PI-BB-28, Activities of the Braidwood Station Mechanical Engineering, Piping Design, Support Design, Analysis and HVAC Systems Field Personnel, Revision 7, June 4, 198 * Project Instruction PI-BB-29, Distribution and Control for Design Documents for S&L Field Personnel at Braidwood Station, Revision 3, December 5, 198 * Design Control Summary, Assumptions and Procedures for Large Bore Pipe Supports: Calculation Book No. 13.1.1 and 13.2.1, Revision 8, March 15, 198 * Design Control Summary, Assumptions and Procedures for Hot Small Bore Piping Supports: Calculation Book No.13.4.12, Revision 4, March 8, 198 The NRC inspector reviewed the relevant portions of the above procedures and instructions associated with onsite design activities to determine whether appropriate procedures / instructions have been established and whether they comply with NRC requirements and licensee commitments. The NRC inspector found that the aforementioned procedures / instructions pertaining to onsite design of piping systems and structures appeared to be acceptabl Design Process Review The NRC inspector randomly selected the following documents for review:

(1) Drawing Revisions Resulting from Design Changes Drawing N Piping System 1CCF107014T, Revision A Component cooling 1CV17105T, Revision B Chemical and volume control 1FW96C001T, Revision D Feedwater

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1MS93A002T, Revision C Main steam ,,,,

1RC21118G, Revision B ' Reactor coolant

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(2) Engineering Change Notice (ECN) Fertaining to Hanger field Problems  ;

Engineering Change -

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Notice N Pipe Hanger N J i

09490 1AF05065X, Revision EF

l 09500 1SX02072X, Revision F l 09504 1CV44037X, Revision B '

09508 1CCF38024G, Revision D e 09513 1RC110985, Revision C (3) Engineering Change Notice Associated with Structural Field *

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ECN N Verificdt. ion of ltaterial Str$ngth 32910 Structural Medific&tions 32921 Structurai " Nodificat. ions 32927 Structural Modifications 32928 Structural , Modifications -

(4) Field Change Request Pertaining to Mechanical'and Structural Problems ,

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FCR N Reason for Change Request 21868

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To meet separation criteria. '

21998 'To permit hydrotesting at 150 psig 22004 Lack of test isolation capability 22257 To permit performance of.hydrotest 22985 To expedite construction 23022 To expedite construction 23025 For fire damper accessibility 23035 To suit for field condition (5) Release of Latest Drawings to Contractors ,

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Structural Drawing N Location S-2112, Revision G Containment Building S-2125, Revision AP Containment Building M-913, Revision G Containment Building S-2147-BR, Revision AF i Auxiliary Building '

S-2155, Revision T Auxiliary Building '

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Pipe Hanger Drawing N Piping System ICCF107014T, Revision A Component cooling 1CV17105T, Revision B Chemical and volume control 1FW96C001T, Revision D Feedwater 1MS93A002T, Revision C Main steam 1RC21118G, Revision B Reactor coolant The NRC-inspector reviewed the relevant portions of the above selected documents with respect to the applicable procedures, instructions, NRC requirements, and the licensee's connitment Further, the NRC inspector verified that the latest structural and pipe hanger drawings issued by S&L were being used in the field. The NRC inspector also verified several design parameters with the ontite design engineers who performed the calculations resulting from the design change On the basis of the above review, it was detemined that, in general, onsite design activities were implemented in accordance with the established procedures and instruction Review of Licensee s QA Audit Report

The NRC inspector reviewed QA Audit Report No. 20-86-506 conducted by the licensee's QA Department on February 18-21, 1986. The purpose of the audit was to determine whether S&L was effectively implementing the applicable sections of its QA program. The major scope of the audit was design control and document / procedure control. Results of the audit revealed that the design calculations were reviewed and approved in accordance with procedural requirements, and that FCR's were properly incorporated in drawing revisions. ~ The audit concluded that S&L was properly implementing the requirements of its QA program in the areas reviewe Within the areas inspected, no violations or deviations were identifie . Exit Interview The inspector met with site representatives (denoted in Persons Contacted paragraph) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection noted in this report. The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify any such documents / processes as proprietary.

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