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Discusses Findings from Insp on 870817-21 & Forwards Insp Rept 50-285/87-22.Findings Considered Open Items & Will Be Forwarded to Mechanical Engineering Branch for Resolution During Review of Updated Inservice Testing Program
	ML20237E167
Person / Time
Site:	Fort Calhoun
Issue date:	12/22/1987
From:	Crutchfield D; Office of Nuclear Reactor Regulation
To:	Andrews R; OMAHA PUBLIC POWER DISTRICT
Shared Package
ML20237E169	List: IR 05000285/1987022; ML20237E167;
References
	NUDOCS 8712280190
	Download: ML20237E167 (4)
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NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D. C. 20555

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December 22, 1987

Docket No. 50-285

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Omaha Public Power District

ATTN:

R. L. Andrews, Division Manager

Nuclear Production

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1623 Harney Street

Omaha, Nebraska 68102

Gentlemen:

SUBJECT:

INSPECTION N0. 50-285/87-22

This refers to the inspection performed by Messrs. E. T. Baker and P. J. Prescott

of the Nuclear Regulatory Commission (NRC), Vendor Inspection Branch on

August 17-21, 1987, at Fort Calhoun Station of activities authorized by NRC

License No. DPR-40.

At the conclusion of the inspection, we discussed our

findings with Mr. J. Fisicaro and others of your staff.

We reviewed the check valve testing program at Fort Calhoun Station.

Particular

attention was directed to the ability of the testing program to establish disk

and seat integrity, location of check valves in relation to sources of turbulence,

maintenance and failure history, and your response to the Institute of Nuclear

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Power Op.eration's (INP0's) Significant Operating Event Report (50ER) 86-03

concerning inspection and testing of check valves.

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The NRC inspectors found that (1) e maintenance procedure for post-maintenance

testing did not ' cover the appropriate valves; (2) a maintenance order was

written to investigate a noise in check valve AC-104 and cancelled because no

parts were available tc perform the maintenance; no evidence existed that any

maintenance was perfonned after the maintenance order was cancelled; and

(3) check valves are not being tested to ensure that all safety functions,

pressure isolation as well as passing flow, are being adequately tested. The

Ft. Calhoun program does not appear to aggressively address the issue of

ensuring that check valves are functional. This was reflected in the

Ft. Calhoun response to SOER 86-3.

In addition, a number of check valves were

noted to be located immediately downstream of pumps or other turbulence

generators.

It was also noted that the vast majority of the maintenance

performed was corrective, as opposed to preventive maintenance.

8712280190 871222

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Omaha Public Power District

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December 22, 1987

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Findings 1, 2, and 3 are considered open items, 50-285/87-22-01, 50 285/87 22-02,

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and 50-285/87 22-03 respectively. Open Item 87-22-03 will be forwarded to the

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Mechanical Engineering Branch for resolution during the review of your updated

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Inservice Testing Program.

The other two open items will be tracked by Region IV

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personnel. Should you have any questions on this matter, we would be pleased

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to discuss them with you.

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Sincerely,

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Original signed by

Dennis M. Crutchfield

Dennis M. Crutchfield, Director

Division of Reactor Project III/IV/V

Office of Nuclear Reactor Regulation

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DISTRIBUTION:

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Docket File No. 285

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Omaha Public Power District

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December 22, 1987

Findings 1, 2, and 3 are considered open items, 50-285/87-22-01, 50-285/87-22-02,

and 50-285/87-22-03 respectively. Open Item 87-22 03 will be forwarded to the

Mechanical Engineering Branch for resolution during the review of your updated

Inservice Testing Program.

The other two open items will be tracked by Region IV

personnel. Should you have any questions on this matter, we would be pleased

to discuss them with you.

.

Sincerely,

Original signed by

Dennis M. Crutchfield

Dennis M. Crutchfield, Director

Division of Reactor Project III/IV/V

Office of Nuclear Reactor Regulation

DISTRIBUTION:

NRC PDR

Local PDR

Docket File No. 285

VIB Reading

DRIS Reading

JPartlow

BGrimes

JStone

EBaker

PPrescott

ABournia

JCalvo

DCrutchfield

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See previous concurrence page.

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December 22, 1987

Findings I, 2, and 3 are considered open items, 50-285/87-22-01, 50-285/87-22-02,

and 50-285/87-22-03 respectively. Open Item 87-22-03 will be forwarded to the

Mechanical Engineering Branch for resolution during the review of your updated

Inservice Testing Program.

The other two open items will be tracked by Region IV

personnel. Should you have any questions on this matter, we would be pleased

to discuss them with you.

Sincerely,

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u'tch ie

irector

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Division of Reactor P ject III/IV/V

Office of Nuclear Reactor Regulation

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ML20237E167

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