ML19270G852

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IE Insp Rept 50-285/79-06 on 790405.No Noncompliance Noted. Major Areas Inspected:Previously Identified Insp Findings & LER 78-040
ML19270G852
Person / Time
Site: Fort Calhoun 
Issue date: 04/17/1979
From: Randy Hall, Rosenberg A, Tapia J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML19270G849 List:
References
50-285-79-06, 50-285-79-6, NUDOCS 7906210018
Download: ML19270G852 (3)


See also: IR 05000285/1979006

Text

.

U. S. NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEfiEfiT

,

REGION IV

Report No. 50-285/79-06

Docket No. 50-285

License No. DPR-40

Licensee: Omaha Public Power District

1623 Harney Street

Omaha, Nebraska

68102

Facility Name:

Fort Calhoun Station - Unit 1

Inspection at:

Fort Calhoun Station, Blair, flebraska

Inspection conducted:

April 5,1979

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4 -/7 '79

Inspectors:

3

J. I. Tapia; Reactor Inspector, Engineering Support

Date

Section

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f7.B.Rosenberg,ReactorInspector, Engineering

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Support Section

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)D. L. Kelley, Reactor Inspector, Reactor Operatio

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Reviewed:

Date

and fluclear Support Branch

Approved:

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R. E. Hall, Chief, Engineering Support Section

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Reactor Construction and Engineering Support Branch

Inspection Summary:

Inspection on April 5,1979 (Report flo. 50-285/79-06_)

Areas Inspected:

Routine, unannounced inspection of previously identified

inspection findings and Licensee Event Report No. 78-40 (LER 78-40).

The

inspection consisted of sixteen hours on site by two flRC inspectors.

Results:

Of the two areas inspected, no apparent item's of noncompliance

or deviations were identified.

"

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79062100le

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DETAILS

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1.

P_ersons Contacted

  • R. L. Andrews, Plant Manager

M. Core, I&C Engineer

  • W. G. Gates, Supervisor, Operations

G. R. Peterson, Supervisor, I&C and Electrical Field Maintenance

The IE inspectors also interviewed other licensee employees during

the inspection.

  • denotes those attending the exit interview

2.

Licensee Action on Previous Inspection Findings

(Closed) Unresolved Item (.50-285/77-06) (7706-4):

Calculation of

Containment Leak Rate.

During a previous inspection, the IE inspec-

tor could not verify that the calculational technique stated in the

Reactor Containment Integrated Leak Rate Test (CILRT) report, dated

December 29, 1978, was, in fact, the one used.

During this inspection,

the IE inspectors reviewed an Omaha Public Power District letter,

dated July 20, 1977, which transmitted a revised page to the Reactor

CILRT report that specified the mass plot method as the one used in

the CILRT calculations.

The IE inspector verified, from the raw data, that the method used

for calculations was the mass plot method. The 95% confidence level

of the leakage was also verified to be below the maximum allowable

limit (0.075%/ day).

This matter is considered closed.

(Closed) Unresolved Item (.50-285/77-06) (7706-5):

Dew-Point Sensor

Calibration Correction.

During a previous inspection, the IE inspec-

tor questioned the appropriateness of using the uncalibrated dew-point

temperatures in the calculations when containment air temperatures and

pressures were calibration corrected.

Duringthisinspectfon,theIE

inspectors determined that the calibration adjustment of 1 F to the

dew-point temperatures would have little effect on the calculated

leakage of 0.025%/ day when the maximum allowable limit was 0.075%/ day.

The licensee comitted to review the application of calibration

correction for all sensors used in the next CILRT.

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3. . Review of Licensee Event Report 78-40 (LER 78-40)

.

LER 78-40, which concerned the containment purge supply and exhaust

penetration local leak rates being in excess of the Technical Speci-

fication limits during the 1978 refueling outage, was reviewed to

verify that:

reporting requirements were met; appropriate corrective

action was taken; licensee procedures were followed in the review

and evaluation of the event; and safety of continued operations was

maintained. The penetration valve's seals and packing were replaced.

The retest showed compliance with the Technical Specifications.

No items of noncompliance or deviations were identified.

4.

Exit Interview

The IE inspectors met with licensee representatives (denoted in

paragraph 1) at the conclusion of the inspection. The IE

inspectors summarized the scope and findings of the inspection.

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