ML20097E301

Responds to NRC Re Violations Noted in Insp Rept 50-354/84-05.Corrective Actions:Nonconformance Rept 4061 Issued to Document & Control Instances of Excessive Spacing of tie-wraps & tie-wrapping of Cables to Other Cables

ML20097E301
Person / Time
Site:	Hope Creek
Issue date:	08/31/1984
From:	Martin T Public Service Enterprise Group
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8409180149
Download: ML20097E301 (3)

Text

j Thomas J. Martin Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/430B316 Vied President Engineering and Construction August 31, 1984 Dr. Thomas E. Murley, Administrator U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

NRC INSPECTION REPORT 50-354/84-05 NO. 1 UNIT HOPE CREEK GENERATING STATION Your letter dated July 31, 1984, transmitted the above referenced Inspection Report which contained a Notice of Violation citing two (2) items of noncompliance. The following respenses are provided in accordance with the Notice of Violation.

I. As described in the referenced Inspection Report, Tie-wraps used to fasten electrical cable to tray rungs were not fastened to tray rungs in accordance with procedural requirements but to other cables in the tray.

Tie-wraps used to fasten electrical cable to tray rungs were spaced in excess of procedure requirements.

An electrical conduit support was reworked without issuance of rework documentation which is not in accordance with procedural requirements.

A. Corrective Steps Taken and Results Achieved On June 6,1984, our Architect / Engineer and Constructor, Bechtel, issued Nonconformance Report (NCR) No. 4061 to document and control instances of excessive spacing of tie-wraps and the tie-wrapping of cables to other cables. Upon completion of Bechtel's investigation, 8409180149 840831 PDR ADOCK 05000354 PDR (0}

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Dr. T. E. Murley 2 8/31/84 all similar discrepancies will be included in NCR-4061.

Rework will be performed in accordance with the dispo-sition of NCR-4061.

On June 8, 1984, Bechtel issued Nonconformance Report (NCR) No. 4076 to document the cracked torque paint condition noted on conduit support No. C-046. A reinspection of the expansion anchor bolts having broken torque paint revealed that the torque values were within acceptable limits.

We have determined that the problem is limited to the two (2) expansion anchor bolts used to attach the conduit support. to the building wall. The torque paint was intact on the three (3) bolted connections securing three (3) conduits to the same support. Also, an examination of twenty-five (25) additional conduit support installations in the same area found no other instances of cracked or questionable torque paint.

NCR No. 4076 was closed on June 27, 1984.

B. Corrective Steps Taken to Preclude Recurrence The appropriate Construction and Quality Control per-sonnel received immediate reinstruction in the require-ments for use of tie-wraps in vertical cable tray sections. This will be followed by formal training sessions which will include craft and supervisory personnel.

Responsible personnel were reminded of the requirements for control of rework activities. Field engineers were reminded of their responsibilities to be aware of activities in their areas which may lead to rework and to assure that required control procedures are followed.

C. Date of Full Compliance The date of full compliance will be November 22, 1984.

i II. As - described in the referenced Inspection Report, Contrary to the above, as of June 19, 1984, the safety-related Control Room Console had shims missing under a vertical framing element, and fillet welds smaller than -

0.25 inch had been used to attach Control Room Console shims to imbedded channels. Further QC inspections accepted these conditions and thereby were not executed so as to verify conformance with the governing documents.

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Dr. T. E. Murley 3 8/31/84 A. Corrective Steps Taken and Results Achieved Bechtel conducted a reinspection of accessible areas of the control console to determine if there were other cases of missing shims or undersized welds.

No further discrepancies were identified. The missing shims were documented on Startup Deviation Report (SDR)

No. RL-0500. The undersized weld condition has been identified on SDR No. RL-0542.

In accordance with the disposition of SDR No. RL-0500, the missing shims wil] be installed as necessary to meet design requirements. The undersize weld condition will be evaluated by Engineering to determine the need for rework. The results of this evaluation will be documented as the disposition of SDR No. RL-0542.

B. Corrective Steps Taken to Preclude Recurrence The responsible Construction and Quality Control per-4 sonnel have been reinstructed in the requirements for noting and documenting all deviations from design

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requirements when performing final inspections. The methods of gap measurement, the need for attention to detail, use of design criteria and the need to e report nonconformances in a timely manner were stressed.

C.- Date of Full Compliance The date of full compliance will be October 15, 1984.

Very truly yours v C . Office of Inspection and E" orcement Division of Reactor Construction Inspection Washington , D.C. 20555 NRC Resident Inspector - Hope Creek P. O. Box 241 Hancocks Bridge, NJ 08038

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