IR 05000456/1984013

Applicant Exhibit A-63,consisting of Forwarding Safety Insp Repts 50-456/84-13 & 50-457/84-13 on 840605- 0706 & Notice of Violation

ML20214F061
Person / Time
Site:	Braidwood
Issue date:	06/25/1986
From:	Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Reed C COMMONWEALTH EDISON CO.
References
OL-A-063, OL-A-63, NUDOCS 8705220390
Download: ML20214F061 (18)

Text

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. ,'* 6a asce, UNITED STATES .

= , , NUCLEAR REGULATORY COMMISSION

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Docket No. 50-456

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Docket No. 50-457 aounnto V -

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"" i Comonwealth Edison Company "

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ATTN: Mr. Cordell Reed w , ._

Vice President c,,,,, og,

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Post Office Box 767 out

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Chicago, IL 60690 C"*

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Gentlemen: pg_ . -S e d This refers to the routine safety inspection conducted by Messrs L. G. McGregor and R. D. Schulz of this office on June 5 through July 6, 1984, of activities

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at Braidwood Nuclear Power Station, Units 1 and 2, authorized by NRC Constructio s Permits No. CPPR-132 and No. CPPP.-133 and to the discussion of our findings with

Mr. D. Shamblin at the conclusion of the inspectio *

The enclosed copy of our inspection report identifies areas examined during

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the inspection. Within these areas, the inspection consisted of a selective

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examination of procedures and representative records, observations, and

. interviews with personnel, i

During this inspection, certain of your activities appeared to be in non-l compliance with NRC requirements, as specified in the enclosed Appendix.

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A written response is require In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure (s)

will be placed in the NRC Public Document Room unless you notify this office, by telephone, within ten days of the date of this letter and submit written application to withhold information contained therein within thirty days of l the date of this letter. Such application must be consistent with the re-quirements of 2.790(b)(1). If we do not hear from you in this regard within the specified periods noted above, a copy of this letter, the enclosure (s), and your response to this letter will be placed in the Public Document Roe The responses directed by this letter (and the accompanying Notice) are not subject to the clearance procedures of the Office of Management anc Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.

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8705220390 860625 YM i

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Commonwealth Edison Company 2

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We will gladly discuss any questions you have concerning this inspectio .

Sincerely, Y 'l.].w JAA'

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R. F. Warnick, Chief Projects Branch 1

Enclosures:

Appendix, Notice of-Violation

. Inspection Reports

- No.50-456/84-13(ORP);

No.50-457/84-13(DRP)

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REGION III==

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Report No. 50-456/84-13(DRP);50-457/84-13(DRP)

Docket Nos. 50-456; 50-457 Licenses No. CPPR-132; CPPR-133

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Licensee: Commonwealth Edison Company

' Post Office Box 767 Chicago, IL 60690 Facility Name: Braidwood Nuclear Power Station, Units 1 and 2

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Inspection Conducted: June 5 through July 6, 1984 Inspectors: L. G. McGregor

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a. D. Schul i Approved By: L , //o4 /N '

. Projects Section IA Date /

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Inspection Summary Inspection on June 5 through July 6, 1984 (Report No.'50-456/84-13(DRP);

50-457/84-13(DRP))

! Areas Inspected: Routine, unannounced safety inspection of licensee action l-on construction deficiency reports and bulletins, plant tours, preventive main-tenance, spent fuel storage racks, pipe supports, procurement, cable pan supports, audits, and reactor coolant pump supports. The inspection consisted of 164 inspector-hours onsite by two NRC inspectors including 4 inspector-hours onsite during off-shift Results: Of the nine areas inspected, no item of noncompliance or deviations

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l were identified in seven areas, two items of noncompliance were identified in l

the remaining areas, failure to specify the application of 10 CFR Part 21 to procurement documents (paragraph 7) and failure to control weld rod for cable pan welding (paragraph 8).

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DETAILS

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' Persons Contacted ,

Comonwealth Edison Company (Ceco)

M. Wallace, Project Manager C. Schroeder, Licensing and Compliance Superintendent

• D. L. Shamblin, Construction Superintendent

. *T. Quaka, Quality Assurance Supervisor L. Tapella, Engineer .

• L. M. Kline, Licensing Compliance

. S. Hunsader Quality Assurance Supervisor i, G. Fitzpatrick, Assistant Manager Quality Assurance Corporate

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• J. Purrazzo, Engineer

M. Curinka, Engineer

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• C. J. Tomashek, Startup Superintendent N. Tomis, 0AD Supervisory Engineer

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J. Enger, Senior Buyer R. Milne, Field Engineer .

K. Steele, Electrical Supervisor -

E. R. Netzel,- Quality Assurance Supervisor

*T. Ronkoske,-Engineer *

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• R. Wrucke, Licensing Engineer i

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• M. Gorski, Engineer '

i *D. A. Boone, Engineer i

l' Phillips Getschow Company (PGCo)

T. G. O'Connor, Site Manager J. Carlson, Quality control Supervisor L. J. Butler, Assistant Quality Control Supervisor M. Galloway, Assistant Project Engineer J. Strong, Quality Control Technician -

R. Tasmond, Quality Control Level II L. K. Comstock and Company. Inc. (LKC) ,

• I. Dewald, Quality control Manager L. G. Seese, Assistant Quality Control Manager Site R. M. Saklak, Quality Control Supervisor R. Brown, Lead Inspector Mechanical

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i R. Frisby, Level II Quality Control Inspector

• R. Seltman, Quality Assurance Engineer l

l Pittsburgh Testing Laboratory (PTL)

T. Frazier, Assistant Site Manager '

! R. Vanderhyden, Construction Engineer In addition, a number of other plant personnel .were contacte * Denotes those personnel attending the exit intervie' A9002256

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$1 Licensee Action on'Previously Identified Items 2.

! It2FR 50.55(irTitems

1 (Closed) 456/81-02; 457/81-02: During the stressing of a tendon on the Braidwood Unit I containment, a thread failure occurred between the shop anchorhead bushing and the stressing adapter due to bcth the lack of full thread engagement and undersized anchorhead thread Analysis showed that the in-place stressed anchorages are acceptabl Corrective action for unstressed anchorages included a checkpoint'in '

the strcssing procedures to assure full thread engagement and measure-ments of all anchorage components prior to stressin (Closed) 456/82-02A; 457/82-02A: Fifteen fire dampers may not close

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due to a deficiency in the fusable link. The defective links have

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been replaced. All future dampers will be checked for proper link

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installation..

,, (Closed) 456/82-11; 457/82-11: A potential problem existed with regard to rigid snubber strut pins. Subsequently, tensile testing

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resulted in no deformation of the pin material and no pins tested i- were found to have low yield strength. In addition, the pin is not -

considered to be a critical hanger componen *

(0 pen)456/83-15;457/83-15: Pacific Scientific (PS) snubbers supplied with capstan springs may be defective and fail during a seismic even .

Subsequent testing and metallurgical evaluation revealed that the

snubbers met design reouirements and there is no reportable deficienc However, a PS letter dated February 10, 1984 recommended that "due to

- the various potentially harsh environments on usage some snubbers might experience, these snubbers be the first to be inspected during nomally scheduled plant inservice or maintenance inspections." The inspector was unable to determine that the licensee had performed any evaluation

or scheduled any of the snubbers for the first plant inservice or maintenance inspection. This item will remain open until the licensee addresses the PS recomendation IE Bulletins -

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(4hesed)*IEBulletin83-01: Failure of Reactor Trip Breakers

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(Westinghouse 08-50) to Open on Automatic Trip Signal. The inspector i

examined the licensee's action relative to the reactor scram breaker failures to detemine whether a timely response was sent to the NRC, if the response addressed the appropriate technical questions, and whether the required actions had been accomplished. The Braidwood design incorporates four 05-416 rather than 08-50 breakers. In

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response to Bulletin 83-01 the licensee has received Westinghouse Change Notice (83) 823 which includes a procedure for changing the undervoltage trip assembly, mounting instructions and trip load and force checks for the breakers. The corrective action recomended by the manufacturer will be completed by the licensee before fuel load

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and a review of the breaker maintenance program for confomance to

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recomended Westinghouse program will be implemented, i-4900225'7 '

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((ansad) JE Bulletin 83-06: Nonconforming Material Supplied by Tube Line Corporation. The licensee has reviewed the list of purchasina

- and receiving companies given in Attachments 2 and 3 of the bulletin

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which may have been supplied by Tube.Line. The search of records has

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shown that four 3-inch 150 pound RF W/N flanges were supplied to the Braidwood Station by the Joliet Valve Co. Two of these flanges were installed in the Boric Acid System and two were installed in the Containment Spray System. One flange has subsequently been removed from the Containment Spray System and the remaining three flanges will

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be replaced upon receipt of new flange (Closed) IE Bulletin 83-07: Apparently Fraudulent Products Sold by Ray Miller, Inc. The licensee has addressed the subject bulletin by a review of corporate purchasing procedures with respect to the

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problems encountered with Ray Miller, Inc. and Tube Line Corporation

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(Bulletin 83-06 response). The licensee has reviewed the purchasing records for Braidwood Construction and Braidwood Operations Departments with no indication that material was purchased frcen Ray Miller In Ceco reviewed its Quality Assurance procedures for review of purchase

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documents and found them to be adeouat ..

(Closed)IEBulletin83-08: Circuit Breakers with An Undervoltage *

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Trip in Use in Safety-Related Applications Other Than the Reactor

,; Scram System. A review completed by the Ceco Braidwood technical

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staffhasconcludedthatytypeDB,EtypeDSandGEtypeAK-2with undervoltage trip attachments are not used in safety-related applica-r tions, outside the reactor scram syste No items of noncompliance or deviations were identified.'

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3. Plant Tours The inspectors observed work activities in-progress, completed work, and f plant status during general inspections of the plant. Observation of work

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included high strength bolting, safety-related pipe welding, anchor bolts,

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structural welds, and cable trays in the containments and auxiliary building. Particular note was taken of material identification, noncon-forming material identification, housekeeping, and equipment preservatio Craft personnel were interviewed as such personnel were available in the work area .

No items of noncompliance or deviations were identifie Preventive Maintenance f The maintenance program for mechanical and electrical equipment was reviewed l

to assure that pump shafts were being periodically rotated, rotating ecuip-

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ment was lubricated, equipment was properly covered for protection frem i

construction activities, insulation resistance testing was performed for

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motors and heat was being applied to electrical items, and desiccant, vapor inhibitors, or nitrogen purges were used to maintain proper humidity 4 A0002258

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I levels. The following pieces of installed equipment and their associated records were examined for the applicable elements stipulated above: ,

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. 2CC01PA, Component Cooling Pump and Motor

. ICS01PA, Containment Spray Pump and Motor

. 2C501PA, Containment Spray Pump and Motor

. 2AP73E, 480 Volt Switchgear Panel

. 2AP17E, 480 Volt Switchgear Panel

. 2RC01PB, Reactor Coolant Pump and Motor

. 2FWO1PA, Auxiliary Feedwater Motor

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. 2CV04AA, Letdown Heat Exchanger .

. 2FC01P, Spent Fuel Pit Pumps

. 2SX01PB, Essential Service Water Pump

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0 WOO 1PA, Main Control Room Chilled Water Pump

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. OWOO1PB, Main Control Room Chilled Water Pump

. 1RH01PA, Residual Heat Removal Motor

. . ISIO1PA, Safety Injection Motor

. 2SIO1PA, Safety Injection Pump and Motor

. 2CV01PB, Centrifugal Charging Pump

. 2RH01PA, Residual Heat Removal Pump ,

The inspector noted that the equipment was poorly covered for protection

> from construction activities. This is considered an open item (456/84-13-01> *

., 457/84-13-01k A review of Phillips, Getschow Co. Procedure, PGCP-37. Revision 1 Equipment Surveillance, revealed that equipment was divided into three categories:

. " Category A" - rotating equipment which requires periodic rotation and lubrication

. " Category B" - requires protective purge gas prior to attachment of piping systems

. " Category C" - other safety-related equipmen Phillips, Getschow Co. quality control inspectors performed surveillances of mechanical equipment, but their inspections mainly involved documenta-tion checks and were on a limited, random basis, not beino extensive enough to assure that all mechanical eouipment was properly maintained by the craftsmen. Although, based on the NRC sample inspection, craft records and maintenance appeared adequate, the mechanical ecufpment cuality assurance organization needs to establish an inspection program to verify adequate craft attention to the preventive maintenance function. Further-more, the inspector could not find inspection or surveillance records docu-

! menting that mechanical equipment quality control inspectors had witnessed any shaft rotations or lubrications. Pending licensee review of this area, including considering the examination of all mechanical equipment to assure that the equipment has been properly maintained; and subsecuent NRC review, l

! mechanical equipment maintenance will remain unresolved (456/94-13-02; 457/84-13-02).

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g The only mechanical items that required gas purges, as stipulated in PGCP-37, were the accumulators and the control room refrigeration units. Vapor inhibitors or the coating of internal parts was not a part of the mechanical

• contractor's preventive maintenance program. Options, especially for heat -

exchangers, employed by the nuclear industry include:

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Maintaining purges as long as possible prior to start-up and incorpora-tion into plant systems, and making piping connections las . The use of humidity indicators attached to or inside component '

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Desiccant used as vapor inhibitor ..

Internals specially coated by manufacturers for long tem storag . Vapor inhibitors, such as Cortec VCI-319. used for extended storage periods since the inhibitors can be flushed from the system (water

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soluble).

Humidity conditions can become extremely high for equipment stored in place as a result of concrete pours or other systems being flushed. The'

inspector has requested the licensee to assess the importance of these ,

options'considering the length of time items have not been in servic Pending licensee assessment, this issue will remain open (456/84-13-01; *

457/84-13-03).

The electrical contractor's (L. K. Comstock) preventive maintenance program

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was reviewed, including Procedure 4.10.2, Receiving and Storage, Revision A, and the inspector identified the following issues:

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. Although Procedure 4.10.2 required that electrical equipment be checked to assure that heaters were properly working, L. K. Comstock did not have a list of the equipment that required heaters and the L. K. Comstock quality control inspector did not document which equip-ment was being checked for heaters.

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The licensee did have a list of maintenance required for electrical l - equipment, such as' covers to protect the equipment and the use of motor winding heaters, but this list was not included in any proce-dure nor was objective evidence provided to the inspector documenting that manufacturer recomendations for maintenance were included in

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this list. L. K. Comstock's quality control organization was not aware of the licensee's lis The inspector has requested the licensee to review the electrical equiper t

maintenance requirements, taking into consideration manufacturer recomenda-tions and/or Sargent and Lundy recomendations. Subsequent to this review and the conclusions reached, the licensee should address L. K. Comstock's

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! responsibility in assuring the maintenance of electrical equipment, including the quality control inspection functio .

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The NRC will review the electrical maintenance program after:

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The licensee determines the adequacy of the electrical equipment *<

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maintenance program,

. The licensee conducts quality control inspections, if required,

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The licensee determines L. K. Comstock's responsibility in assuring l

maintenance of electrical equipment.

l Pending these licensee actions and NRC review, the electrical equipment l

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maintenance program will r'emain unresolved (456/84-13-04; 457/8413-04).

No items of noncompliance or deviations were identifie '

, Spent Fuel Storage Racks

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! The contractor that fabricated the 6x5 and 6x6 spent fuel storage racks

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was NUS Corporation. The inspector reviewed Specification F/L-2743, New

And Spent Fuel Storage Racks dated January 7, 1976 through Amendment 2 dated June 28, 1983, and NUS Corporation Specificartion 5106-M-200 Revision C, which was approved by Sargent and Lundy on January 13, 1978. These two

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documents established the fabrication recuirements for the storage rack The following drawings -delineated the dimensional requirements and weld ,

details:

. 5106M 2000 Revision 2

. 5106M 2001 Revision 7 -

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. 5106M 2002 Revision 8 After reviewing these drawings, a 6x5 rack and a 6x6 rack were examined for conformance to the drawings requirements, including:

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. Width and length dimensions

. Component dimensions - (shear plates, collar bars, corner support p plates, module support plates, support beams, and gusset plates)

. Separation dimensions

. Structural welds - (gusset plate to beam welds, plate to beam welds, . gusset plate to support plate welds, collar bar to support plate welds, and shear plate welds)

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One rack's flare plates at the end of the ' alignment box were damaged and one rack's support beams, (quantity of two), were deformed. The inspector identified these racks to the licensee and the licensee documented these conditions for resolution. Pending licensee evaluation and corrective action if necessary, and NRC review, the acceptance of these two spent fuel storage racks will remain unresolved (456/84-13-05; 457/84-13-05)..

It was noted that the welds attaching the 79" long collar bar to the

, .3" x 83" support plate were not symetrical. The pieces were connected by 9" long welds on the ends, and 3" long intennittent welds with centers

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I' ranging from 5 1/2" to 8 1/2". The inspector was unable-to identify this

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- particular weld detail on the drawings to determine weld acceptabilit Pending this information being supplied to NRC and subsequent review, this

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weld detail will remain an open item (456/84-13-06; 457/84-13-06).- .

The fabrication documentation was reviewed and the inspector identified the following items, which the licensee is presently investigating and

. evaluating for resolution:

. welding procedure qualifications as required by specification F/L-2743, identified as being used for specific welds or components.were not

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welder qualifications as required by specification F/L-2743, were not

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available for revie "

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. penetrant material test reports, as required by specification i 5106-M-200, were not aveilable for revie .

NUS Visual Weld Inspection Procedure 763, Revision 1, was not

, ; available for revie the majority of the visual weld inspection records for the root and

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' completed welds, as required by specification 5106-M-200, were not *

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available for revie '

. joint preparation inspection records for dimensional and cleanliness conformance, as required by specification 5106-M-700, were not available for revie ~

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surface roughness and interior edge inspection records, as recuired by l specification 5106-M-200, were not available for revie . penetrant test reports did not identify the specific components penetrant tested, nor if both the applicable root and final passes were inspected, as required by NUS Procedure 761. Revision 5, and

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specification 5106-M-20 .

the inspector was unable to trace the certified material test reports for the collar bars, as required by specification 5106-M-200, for the majority of the storage rack assemblie .

The inspector was unable to trace the certified material test reports I

for the welding materials to the specific joints or components, as

! recuired by specifications 5106-M-200 and F/L-2743.

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Penetrant Test Report, dated March 22, 1979, shop order #3913, was not traceable to a spent fuel storage rack assembly serial numbe The licensee stated that they believe adequate documentation does exist,

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'l review, documentation acceptability for the spent fuel storage racks will remain an unresolved issue (456/84-13-07; 467/84-13-07 ,

No items of noncompliance or deviations were ident~ifie . Pipe Supports Twenty pipe supports were examined for conformance with the drawing requirements. Attributes checked included:

. Configuration

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. Weld details

. Dimensional tolerances and offset gaps

. Location

. Correct components

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, Identified below are the installed component supports which were examined, the type of support, location, and if applicable, an engineering change

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notice (ECN), which revised the installation:

Support Type Location ECN N '

M-1SXO9044X sway-strut containment #1 16559 M-ISXO8038X rigid containment #1 12196 .

M-1CV05020R rigid containment #1 M-1CV05022X sway-strut containment #1 M-1CV05027R rigid containment #1 M-1CV05021X sway-strut containment #1

M-1CV05099X sway-strut containment #1 M-1CV05023R sway-strut containment #1 M-1CV050?4R sway-strut containment #1 M-1CV05025X sway-strut containment #1 M-1CV05026R rioid containment #1 M-1CV54004X sway-strut auxiliary building auxiliary building

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l M-1CV54005R rigid i M-1CV01028X rigid auxiliary building l M-1CC03073R rigid auxiliary building *

M-1CC03136R sway-strut auxiliary building M-1CC03150X sway-strut auxiliary building 15907 M-1CV54001R rigid auxiliary building M-1CVS4003X sway-strut auxiliary building M-1CCO2136X sway-strut auxiliary building No items of noncompliance or deviations were identifie . Procurement Procurement documents specifying material for the electrical discipline were checked for technical adequacy. 0A program requirements, 10 CFR 21 provisions, identification of items, and if the supplier was on the

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approved bidders list. In addition, Commonwealth Edison material receipt

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l inspection reports' and documentation, such as certified niaterial test reports and certificates of conformance, were reviewed for conformance to

, the procurement documents. .The following purchase orders and their associated receipt inspection documentation were examined: ,

Purchase Order N Vendor Product Type 728208 Northern Ill. Steel ASTM A36 plate 249282 Northern Ill. Steel ASTM A36 plate 266483 Haggerty Steel Structural Steel

- 259707 Haggerty Steel Tube Steel, Plate 256493 - Haggerty Steel Tube Steel, Plate 252162

Raychem Cor Heat Shrink Tubing 254434 Raychem Cor Heat Shrink Tubing 259782 Raychem Cor Heat Shrink Tubing

- 262155 Raychem Cor Heat Shrink Tubing

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265347 Raychem Cor Heat Shrink Tubing 270934 Raychem Cor Heat Shrink Tubing 276436 Raychem Cor Heat Shrink Tubing

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256523 Raychem Cor Heat Shrink Tubing

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272787 Raychem Cor Heat Shrink Tubing

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The procurement documents and receipt inspection records were in accordance I with regulatory requirements with the exception of six orders placed with ,

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Raychem Corporation. The heat shrinkable tubing was ordered under the

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' requirement that documentation shall include a certificate of compliance certifying that the material had been tested to the recuirements of IEEE 383-1974 for aging, radiation, and LOCA environment, as stipulated by Sargent and Lundy drawing 20-E-1-3503, dated February 1,1979, and L.K. Comstock Procedure 4.3.9, Cable Termination Installation, Para-graph 3.11.5 - Lug to Bus Connection, 4160V and 6900V Connections. The certification for aging, radiation, and LOCA environment was received for all the Raychem Corp. purchase orders delineated above. However, Raychen Corp. procurement documents, numbers 252162, 254434, 259782, 262155, 265347, and 270934 did not contain statements that 10 CFR Part 21, " Reporting of Defects And Noncompliance", applied to these heat shrink tubing order CFR 21.31 Procurement Documents states: "Each individual, corporation, partnership or other entity subject to the regulations in this part shall assure that each procurement document for a facility, or a basic component issued by him,. her or it on or after January 6,1978 specifies, when appli-cable, that the provisions of 10 CFR Part 21 apply."

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Detailed below are the procurement documents and their date of placement:

Procurement Document N Oate of Placement 252162 02/02/81 254434 08/03/81 259782 01/22/82 262155 04/1A/82 265347 06/23/82 270934 11/22/82

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Failure to specify the application of 10 CFR Part 21 to these procurement documents is a violation of 10 CFR 21.31 (456/84-13-08; 457/84-13-08) ,

8. Cable Pan Supports The structural supports for ten cable pans located in.the auxiliary building were examined for conformance to the drawings, including configuration, dimensions, and welding details. Detailed below are the cable pans and their applicable supports:

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Cable Pan Support M 21752J H-181. H-189 unistrut 21750J H-188 unistrut/breced

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21747J H-185, H-186, H-187 unistrut/H-186 braced

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21746J H-183, H-184, H-185 unistrut/H-183 braced 21779J H-160 tube steel

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21777J H-170, H-171 unistrut 21772J H-137, H-138 tube steel /H-137 braced 21773J H-175 unistrut '

. 21764J H-142 unistrut

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21765J H-140 unistrut/ braced

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. Sargent and Lundy drawings 20E-0-360 series and 20E-0-380 series

, for welding detail . Sargent and Lundy drawing 20E-0-3251 Cable Pan General Notes and Installation Details.

. Sargent and Lundy drawing 20-E-03278 for configuratio . Sargent and Lundy Hanger List for dimensional requirement '

Subseocently, the inspector reviewed L. K. Comstock inspection reports for these cable pan installations, and Pittsburgh Testing Laboratory inspectior reports that documented a 10% overview weld inspection. Procedures reviewed included L. K..Comstock Procedures 4.8.3, Weld Inspection and 4.3.10, l- Storage, Issue and Control of Welding Material. Inspection reports were l in accordance with procedure requirements and the weld rod was found to be ,

l stored in accordance with the procedure requirements, including oven tem-

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perature adherence. However, the inspector discovered that weld red was l

allowed to be stored overnight in the portable rod oven heaters, instead of

being returned to the issue stations. There are approximately one-hundred

portable ovens and quality control does not assure that these ovens are l plugged in at night and furthemore, surplus weld rod should be returned I

to the issue stations in order that it may be signed out to a specific

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l application / component for traceability control. The inspector discussed these points with the licensee and the licensee has decided that all

surplus weld rod must be returned to an issue station after the days shift, to facilitate optimum weld rod control. L. K. Comstock was notified of the '

licensee's decision and therefera, the inspector considers this issue close .

Over 300 filler metal withdrawal authorization forms, which document the release of weld rod for electrical installations, were . reviewed for the months of May 1982 through August 1982. This was the time frame the cable

n pans were installed. The filler metal authorization forms were specific as to the use of the weld rod, specifying one of the following on each form:

i . conduit hangers

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. cable support

. cable pan

. switchgear

. . junction box hangers

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However, the forms did not specify the specific component the rod was used

>, on and only listed general building locations, such as Auxiliary Building,

- elevation 463 feet. Nine fiiler metal withdrawal authorization forms .

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documented the assignment of E7018 weld rod for cable pan welding, even

though Sargent and Lundy drawing 20E-0-3251, Revision AC and L. K. Comstock *

Procedure 4.3.3, dated January 29, 1982, required the use of E60 Series weld rod for cable pan welds. Detailed below are the nine forms' documenting

the release of E7018 weld rod, by heat number, for cable pan welding:

Date of Designated l

Recuisition Area Heat N Class 5/25/82 Auxiliary Bldg., 383' 411P4161 *E6013 5/25/82 Auxiliary Bld P4161 *E6013 5/26/82 Auxiliary Bld P4161 *E6013

6/9/82 Auxiliary Bldg., 383' 411P4161 *E6013 6/10/82 Containment #1, 426' 411P4161 E7018 6/11/82 Auxiliary Bldg., 426' 421P4461 E7018 6/22/82 Auxiliary Bldg., 426' 402S9011 E7018 l

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7/13/82 .

Auxiliary Bldg., 463' 40259011 *E6013 7/28/82 Auxiliary Bldg. , 439' 40259011 E7018

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• Heat numbers 411P4161 and 40259011 were actually E7018 weld rod as the inspector reviewed the material certifications. The rod issue attendants apparently thought these heats of red were E6013. Note that the same heats, 411P4161 and 40259011, were handed out as both E6013 and E7018 weld ro Failure to control the use of weld rod for cable pan welding is a violation of 10 CFR 50, Appendix B, Criterion IX (456/84-13-09; 457/84-13-09).

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A0002266

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- Audits

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Comonwealth Edison recent site audits were reviewed. Past NRC inspection findings identified deficiencies in the Braidwood Site audit program with *

regard to depth of audits and corrective action. The recent audits revealed significant improvement in audit technique, depth, identification of problem areas, corrective action, and actions to prevent recurrence. The audits met the regulatory requirements and were carried out with the purpose of identifying and correcting any deficiencies that could affect the safe operation of the plant. The audits reviewed and area covered are detailed

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below: , , ,

Audit Dates Area Disdipline 6/11/84-6/16/84 Calibration, Measuring and HVAC

- Test Equipment Storage HVAC QC Inspections HVAC Welding / Weld Rod Control HVAC 4/17/84-4/27/84 Receiving and Material Piping s Control Piping .

Storage Piping Housekeeping Piping ,

Corrective Action Piping Small Bore Pipe Piping

. Piping / Support Layout . Piping Support Installation Piping Material Traceability Piping 4/16/84-4/23/84 Identification and Control Electrical of Equipment and Components OC Inspector Qualifications Electrical Welding / Weld Rod Control Electrical Re-inspection Program Electrical .

The audits included both documentation (software) and installation l (hardware) inspections.

No items of noncompliance or deviations were identifie . Inspection of Reactor Coolant Pump Supports l

l The inspector reviewed Sargent and Lundy design drawings No. S1107, 51109

- " Reactor Coolant Pump Support" Plan Elevation 393'2" and Teledyne Brown l

Engineering Drawing No. 22287 " Byron /Braidwood Station N.S.S.S. Support Framing Reactor Coolant Pump Lateral Support Erection" and noted dis-l l

crepancies between the as-built condition and the designed lateral suppor This lateral support modification affected just reactor coolant pump number 2 in units one and two. The inspector recuested documentatinn to substantiate the nonconfonnance which resulted in the modification, the

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l A0002267

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Engineering Change Notice, the Design Change review and approval, material specifications, qualified welding procedures, Quality Control records and

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inspections, and welder qualifications. Additionally, the inspector will determine if this modification was also installed on the Byron reactor .

coolant pumps. This matter is considered an unresolved item and will be reviewed during future inspections (50-456/84-13-10; 50-457/84-13-10),

11. Open Items Open items are matters which have been discussed with the licensee, which will be reviewed further by the inspector, and which involve some action on the part of the NRC or licensee or both' Open items .

disclosed during the inspection are discussed in Paragraphs 4 and 5.

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12. Unresolved Items

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l' Unresolved items are matters about wh.ich more information is required

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in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. Unresolved items disclosed durina the inspection are discussed in Paragraphs 4, 5 and 1 ,

13. Exit Interview

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The inspector met with licensee representatives (denoted under Persons *

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Contacted) durine and at the conclusion of the inspection on July 6, 1984 The inspector summarized the scope and findings of the inspectio '

The licensee acknowledged the information.

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