ML20215D808

Forwards Insp Rept 50-267/86-29 on 861001-1115.No Violations or Deviations Noted.Actions Taken Re Previously Identified Insp Findings Also Examined

ML20215D808
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/05/1986
From:	Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
Shared Package
ML20215D811	List: IR 05000267/1986029 ML20215D808
References
NUDOCS 8612170045
Download: ML20215D808 (2)

See also: IR 05000267/1986029

Text

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DEC 5 1986

In Reply Refer To:

Docket: 50-267/86-29

Public Service Company of Colorado

ATTN: R. O. Williams, Jr.

Vice President, Nuclear

Operations

P. O. Box 840

Denver, Colorado 80201

Gentlemen:

This refers to the inspection conducted by Messrs. R. E. Farrell and P. W. Michuad

of this office during the period October 1 through November 15, 1986, of activities

authorized by NRC Operating License DPR-34 for Fort St. Vrain Nuclear Generating

Station, and to the discussion of our findings with Mr. J. W. Gahm and other

members of your staff at the conclusion of the inspection.

Areas examined during the inspection included operational safety verification,

licensee action on licensing event reports, followup of Allegation 4-86-A081,

maintenance, engineered safety features, and security. Within these areas, the

inspection consisted of selective examination of procedures and representative

records, interview:: with personnel, and observations by the NRC inspector. The

inspection findings are documented in the enclosed inspection report.

Within the scope of the inspection, no violations or deviations were

identified.

We have also examined actions you have taken with regard to previously

identified inspection findings. The status of these items is identified in

paragraph 3 of the enclosed report.

Should you have any questions concerning this inspection, we will be pleased to

discuss them with you.

Sincerely,

0:Ls' -,4

9,

J. Z. C; ,e3

J. E. Gagliardo, Chief

Reactor Projects Branch

Enclosure:

Appendix - NRC Inspection Report

50-267/86-29 7

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