ML20135D939

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Forwards Insp Rept 50-285/96-12 on 961015-1101 & Notice of Violation
ML20135D939
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/04/1996
From: Gwynn T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Tira Patterson
OMAHA PUBLIC POWER DISTRICT
Shared Package
ML20135D942 List:
References
NUDOCS 9612100273
Download: ML20135D939 (5)


See also: IR 05000285/1996012

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T. L. Patterson, Division Manager

Nuclear Operations

Omaha Peblic Power District

Fort Calhoun Station FC-2 4 Adm.

P.O. Box 399, Hwy. 75 - North of Fort Calhoun

Fort Calhoun, Nebraska 68023-0399

SUBJECT: NRC INSPECTION REPORT 50-285/96-12 AND NOTICE OF VIOLATION

Dear Mr. Patterson:

An NRC inspection was conducted October 15 through November 1,1996, at your Fort

Calhoun Station reactor facility. Following the exit meeting the results of this inspection

were discussed with you and members of your staff on December 2,1996. The enclosed

report presents the scope and results of that inspection.

During this inspection, the NRC inspectors identified one violation of the Technical

Specifications. The violation involved adding reactivity to the reactor core at a time when

available wide range logarithmic power channels were not able to provide adequate

continuous flux monitoring due to their distance from the fuel assemblies being loaded into

the reactor vessel. Your staff disagreed with this potential violation during the exit

meeting. This disagreement was discussed during our conversation on December 2,1996.

We believe that continuous neutron flux monitoring during core alteration is required to

provide indication of unexpected changes. We believe that the available data supports our

contention that a violation did occur. We are concerned about your ability to detect

reactivity anomalies or any unsafe condition during refueling operations, as described in the

bases of the Technical Specifications and the Updated Safety Analysis Report. Our

concern is heightened by the condition of reactor cavity water clarity during refueling and

the apparent lack of concern by operators when changing core reactivity conditions did not

provide a corresponding change in neutrun count rate.

The violation is cited in the enclosed Notice of Violation (Notice) and the circumstances

surrounding this violation are described in detail in the enclosed report. Please note that

you are required to respond to this letter and should follow the instructions specified in the

enclosed Notice when preparing your response. The NRC will use your response, in part,

tc determine whether further enforcement action is necessary to ensure compliance with

regulatory requirements.

it is our understanding that, during the exit meeting, on November 1,1996, you stated

Omaha Public Power District would evaluate Operating Procedure OP-11, " Reactor Core

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Refueling," Revision 23, to determine the need for establishing requirements that would

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cause an evaluation of fuel reload sequence to occur in the event of an inoperable

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logarithmic power channel. Please confirm this regulatory commitment in writing within 30

days of the date of this letter that our understanding of this commitment is correct.

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in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter,

its enclosure (s), and your response will be placed in the NRC Public Document Room. To

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the extent possible, your response should not include any personal privacy, proprietary, or

safeguards information so that it can be placed in the Public Document Room without

redaction.

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

them with you.

Sincerely,

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/ homas P. Gwynn, Di ector

Division of Reactor S fety

Docket No.: 50-285

License No.: DPR-40

Enclosures:

Notice of Violation

NRC Inspection Report

50-285/96-12

cc w/ enclosures:

Perry D. Robinson, Esq.

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Winston & Strawn

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1400 L. Street, N.W.

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Washington, D.C. 20005-3502

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Jack Jensen, Chairman

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Washington County Board of Supervisors

Blair, Nebraska 68008

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