ML20151S143

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Forwards Insp Rept 50-285/88-19 on 880601-30.No Violations or Deviations Noted.Understands That Licensee Will Investigate & Determine Root Cause of Apparent Failure of Licensed Individual to Receive Sys Design Change Training
ML20151S143
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 08/08/1988
From: Callan L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Morris K
OMAHA PUBLIC POWER DISTRICT
Shared Package
ML20151S146 List:
References
NUDOCS 8808150084
Download: ML20151S143 (2)


See also: IR 05000285/1988019

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In Reply Refer To:

Docket: 50-285/88-19

0maha Public Power District

ATTN: Mr. Kenneth J. Morris

Division Manager-Nuclear Operations

1623 Harney Street

Omaha, Nebraska 68102

Gentlemen:

This refers to the inspection conducted by Messrs. P. H. Harrell and T. Reis of

this office during the period June 1-30, 1988, of activities authorized by NRC

Operating License DPR-40 for the Fort Calhoun Station, and to the discussion of

our findings with Mr. W. G. Gates and other members of your staff at the

.

conclusion of the inspection.

Areas examined during the inspection included followup on previously identified

items, licensee event report followup, operational safety verification, plant

tours, safety-related system walkdowns, monthly maintenance observations,

monthly surveillance observations, security observations, radiological

protection observations, in-office review of periodic and special reports, and

new fuel receipt activities. Within these areas, the inspection consisted of

selective examination of procedures and representative records, interviews with

personnel, and observations by the NRC inspectors. The inspection findings are

documented in the enclosed inspection report.

Within the' scope of the inspection, no violations or deviations were identified.

One enresolved item related to licensed operator training is identified in

paragraph 9 of the enclosed inspection report. It is our understanding that you

will investigate and determirie the root cause of the apparent failure of a

licensed individual to receive training in system design change information.

We have also examined actions you have taken with regard to previousi.y

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,

Yu ~ l '.

L. J. Callan, Director

Division of Reactor Projects

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. Enclosure:

-Appendix - NRC Inspection Report

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~ 50-285/88-19

cc w/ enclosure:

W. G. Gates, Manager

Fort Calhoun Station

P.O. Box 399

Fort Calhoun, Nebraska 68023

Harry H. Voigt, Esq.

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LeBoeuf, Lamb, Leiby & MacRae

i 1333 New Hampshire Avenue, NW

Washington, DC 20036

Nebraska Radiation Control Program Director

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