ML20132D232

Insp Rept 50-267/85-15 on 850521-24.Violation Noted:Cable Assemblies Ordered by Purchase Order N5755 & Suppl 1 on 850130 Released W/O Identifying Hold Status Per Nonreceipt of Purchase Order Required Fatigue Test Data

ML20132D232
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/05/1985
From:	Barnes I, Ireland R, Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20132D202	List: ML20132D196 ML20132D211 ML20132D232
References
50-267-85-15, NUDOCS 8507310252
Download: ML20132D232 (5)

See also: IR 05000267/1985015

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APPENDIX B

U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-267/85-15 License: OPR-34

Docket: 50-267

Licensee: Public Service Company of Colorado (PSC)

P. O. Box 840

Denver, Colorado 80201

Facility Name: Fort St. Vrain Nuclear Generating Station

Inspection At: Fort St. Vrain (FSV) Site, Platteville, Colorado

Inspection Conducted: May 21-24, 1985

Inspector: W 7/1/PT

I. Barnes, Reactor Inspector, Project Section A, Date

Reactor Project nch 1

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Approved: C/-u P 7 d

Jaudpn, Chi , Project Section A, Reactor Datef

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R. 'E.' Ireland, Chief, Special ' Projects and D' ate /

Engineering Section, Reactor Project Branch 1

8507310252 850716

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Inspection Summary

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j Inspection Conducted May 21-24, 1985 (Report 50-267/85-15)

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l Areas Inspected: Routine, unannounced inspection of maintenance activities

associated with the control. rod drive refurbishment program. 'The inspection

involved 27 inspector-hours onsite by one NRC inspector.

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Results: Within the one area inspected, one violation was identified (failure

to follow procedures, paragraph 2).

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DETAILS

1. Persons Contacted

PSC

• J. W. Gahm, Manager, Nuclear Production

• R. L. Craun, Manager, Nuclear Site Engineering

• W. L. Franek, Superintendent, Operations

J. Jackson, Quality Assurance (QA)/ Quality Control (QC) Supervisor

• F. J. Novachek, Manager, Technical / Administrative Services

• T. C. Prenger, QA Engineering Supervisor

• L. W. Singleton, Manager, QA

Others

• G. L. Plumlee, III, NRC Resident Inspector

• Denotes those present during the exit interview held on May 24, 1985.

The NRC inspector also contacted other licensee site engineering employees

during the inspection.

2. Maintenance

a. Drive Assembly Criteria: A comparison was made between the criteria

being utilized for assembly of the control rod drives with respect to

available information on original assembly criteria. This was

accomplished by review of Section 3.8, " Control Rods and Drives

Reserve Shutdown System," of the Updated Final Safety Analysis

Report, Issue 2, and evaluation of technical requirements contained

in bearing drawings (i.e., -222, 256, 257, 258, 259, 260 and 261) and

assembly drawings SLR D 1201-100 and -200. The original GA

methodology was ascertained from review of GA document GA 9807,

1977 Revision, " Installation, Operation, and Maintenance Manual for

the Control and Orificing Assembly for the FSV Reactor." The noted

requirements were then compared against the detailed drive assembly

instructions contained in FSV Fuel Handling Procedure Work Packets

(FHPWPs). The method used to evaluate individual bearing preload and

shim requirements was observed to dif fer from the criteria contained

in GA 9807. The differences were assessed by interview of site

engineering personnel and observation of the techniques used for

measurement of bearing dimensions. Use of micrometers and dial

indicators with current calibration status was verified during this

review. The inspector also verified that the standards were

traceable to the National Bureau of Standards.

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The NRC inspector additionally examined the results of a contractor

comparison review of differences in requirements between FHPWPs and

control rod drive and orifice assembly (CR00A) drawings. Current

assembly process control compliance was assessed by review of

FHPWP-100-10.

Within this area of inspection, no violations or deviations were

identified.

b. Procurement Control: The NRC inspector reviewed the following procurement

related procedures:

• Administrative Procedure Q-4, Issue 6, Effective Date May 7, 1984,

" Procurement Document Control"

• Administrative Procedure Q-7, Issue 6, Effective Date August 27,

1984, " Control of Procured Materials and Services"

• Procedure MRIM-1, Issue 4, Effective Date December 10, 1984, " General

Receiving Inspection"

Purchase Order (PO) N5755 through Supplement 01 dated January 30, 1985,

which pertained to cable assemblies, was selected for review as a result

of the PSC decision to change cable material from Type 347 austenitic

stainless steel to Inconel 625. The P0 to GA Services required their

performance of a fatigue test on a cable sample with the results to be

supplied to PSC. Examination of vendor-furnished documentation for the

cable assemblies showed that this information had not been furnished to

PSC by GA as of this inspection. The NRC inspector was informed by QA

personnel that the cable assemblies had been released by FSV receiving

inspection based upon the P0 being still open and the knowledge that the

fatigue test had not been completed. The failure of receiving inspection

to identify a hold condition in regard to the required certification is an

apparent violation (50-267/8515-01).

The NRC inspector noted, during review of GA PO 035022 for the manufacture

of the Inconel 625 wire, that the wire was required to be lubricated with

molybdenum disulfide prior to the final draw. On ascertaining from site

engineering personnel that the maximum service temperature experienced in

the cable length was approximately 1700 F, the NRC inspector requested

information concerning corrosion susceptibility of the cable wires to the

molybdenum disulfide surface film. The NRC inspector was informed that

this subject had been reviewed, but that the responsible engineer was not

in office. This is considered an open item pending review of applicable

information on the subject (50-267/8515-02).

The NRC inspector additionally noted during documentation review that the

P0 and the cable drawing required removal of drawing lubricants from the

Inconel 625 wire prior to molybdenum disulfide application and final wire

reduction. Review of a GA report for a source inspection at the wire

manufacturer's facility showed,' however, that the manufacturer had used a

drawing compound after molybdenum disulfide application for final wire

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reduction. This document, which was not contractually required by PSC,

did not indicate any actions taken by GA as a result of the apparent

violation of GA procurement requirements by the wire manufacturer. A GA

limited analysis of the compound used, Apex SP2 soap, was present in the

documentation' and showed 0.26% by weight chlorides. A GA analysis of the

molybdenum disulfide used by the wire manufacturer had also been provided

to PSC and showed a reported 15 ppm fluorides,16 ppm chlorides, and

145 ppm sulfates. A documented evaluation of the acceptability of the

wire after use of the drawing compound for final reduction was not present

in the submitted GA information. This is considered an open item pending

review of such information (50-267/8515-03).

3. Exit Interview

An exit interview was conducted on May 24, 1985, at the FSV site with

those personnel denoted in paragraph 1 of this report. The NRC inspector

summarized the scope and findings of the inspection.