ML19323F159

Interim Deficiency Rept Re Pump Failures of Comsip,Inc,post- LOCA Analyzers.Util Evaluating Comsip Design Change to Prevent Excessive Outlet Pressure Buildup by Valve Closed Downstream.Final Rept Will Forwarded by 800829

ML19323F159
Person / Time
Site:	Perry
Issue date:	05/22/1980
From:	Davidson D CLEVELAND ELECTRIC ILLUMINATING CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 8005280600
Download: ML19323F159 (2)

Text

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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY l

CLEVELAND May 22, 1980 Mr. James C. Kappler Director Region III Offic of Inspection and Enforcement U.S clear Regulatory Commission asevelt en Ellyn, IL 60137 l RE: Perry Nuclear Power Plant Interin Report on Pump Failures of Comaip Post-LOCA H 2 A"*17****

Dear Keppler:

letter is an interim report as required by 10CTR50.55(e) (3) on the deficiency concerning Consip Incorporated, Delphi Systems Division, Contain-n; c as Monitoring System. This problem was identified to Mr. Jack Hughes or c C Region III, Office of Inspection and Enforcement on April 22, 1980 by Mr. . R. Edelman of The Cleveland Electric Illuminating Company.

2: 2. aption of Deficiency The Cleveland Electric Illuminating Company awarded a contract to Consip Incorporated for the design, fabrication, assembly, testing, inspection and delivery of the hydrogen analyser systema for the Perry L'uclear Power Plant--

Unit and 2. During a functional testing of one of the units, a pump j fa because one of the panel outlet valves was closed when the pump was l ted. This design did not consider that excessive outlet pressure of the l a ple pump could cause mechanical separation of the connecting rod and i a rank shaft, which in turn, could rupture the pump diaphragm. This problem

< restes two safety hasards:

4) Containment gas could be released to the outside atmosphere.

2) The containment gas monitoring system would be inoperable.

Detailed information concerning this problem can be found in the enclosed  !

letter that Consip sent to Mr. Robert H. Engelken, Director of Region V per  !

requirements of 10CFR21.

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Mr. Jame] G. Kepplcr May 22, 1980 l

Corrective Action The Cleveland Electric Illumicating Company is currently evaluating a proposed design change by Consip which incorporates a relief bypass valve across the pump that will prevent excessive outlet pressure build up by any valve being closed downstream of the pump. If this review results in acceptance of this new design, Consip will be requested to physically test it. Based on ac-captance of the new design and satisfactory results from its testing, a final et should be submitted by August 29, 1980.

Very truly yours, 1

THE CLEVELA D ELECTRIC II.LUMINATING CO.  !

Dalvyn i. Davidson Vice President System En31 neering and Construction t DRD:taF l

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u. tor Stello, Director  ;

O [ce of Inspection and Enforcement I Nuclear Regulatory Commission hington, DC 20555

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s. (213)442 0882 Telex 67 4768 3 April 1980 Mr. Robert H. Engelken -

Director, Region V Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 1990 N. California Boulevard,. Suite 202 ,

Walnut Creek, California 94596 Sub' ject: 10CRF21 Requirements /

Existence of a Defect Gentlemen:

As required by the subject regulation, the following report is made in triplicate.

Firm Identification: Comsip, Inc.

Delphi Systems Division 10650 E. Rush Street .

So. El Monte, California 91733 (213)442-0882 Responsible Officer making Report:

Claude Varinois, President Type of Business Activity:

Manufacturers; Containment Gas Monitoring Systems Notification of Defect as follows: -

I was notified yesterday, 2 April 1980, that while in-house testing was being conducted, the following failure occured.

The contents of the report made to me by one of our Test Technicians follows:

Subject:

80-637 "K" Pump Malfunction During the testing of 80-637, one of the panel outlet valves was closed while the panel was shut-down. The pump was then started with the valve still closed. The following occurred;

1) The pump deadheaded for no longer than 20 Seconds,

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2) The pressure at the pump outlet exceeded 150 psig,

3) The pressure buildup caused the connecting rods to separate from the crank shaft causing a tremendous strain on the diaphragms.

It is conceivable that these diaphragms could have ruptured, thereby breaching the integrity of the system. The panel valves are one cause for such

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an event, but also the "N" stamp containment isolation valves, which are sometimes automatically closed, could cause the same malfunction.

To remedy the problem, we could install a check valve across the inlet and outlet of the pump.

In the event of any valves being closed in the system, the check valve would prevent any damaging build-up of pressure."

The above report makes clear that either of thd following two safety hazards exist:

1) up to one litre of containment gas could be released into the outside atmosphere, should the failure as defined above occur; and/or

2) if the input / outlet valve is closed while the pump is in operation or if the containment isolation valve inside the containment is closed, there is a risk in damaging the system, thereby rendering the system -

inoperable.

Location of Facilities where the component exists:

- Pennsylvania Power and Light Susquehanna/ Units 1 & 2

- Mississippi Power and Light Grand Gulf / Units 1 S 2

- Detroit Edison Enrico Termi/ Unit 2 l

- Alabama Power Company l Jos. M. Farley/ Units 1 S 2 l

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- Houston Lighting and Power Company J South Texas Project / Units 1 & 2 1

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- Tennessee Valley Authority Sequoyah/ Units 1 S 2

- Tennessee Valley Authority Watts Bar/ Units 1 S 2

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- Arizona Nuclear Project Palo Verde / Units 1, 2 S 3

- Georgia Power Company ,

Hatch / Unit 2 To the best of our knowledge, none of the plants to which this component has been supplied is currently in operation with the exception of Georgia Power Company, which is currently shut down for maintenance.

Corrective Action to be Taken:

We are in the process of putting a by-pass on the discharge of the pump to prevent deadheading, thereby preventing any damage.

This corrective action will be introduced on the Cleveland Nuclear Plant and will be added on all future jobs.

Notification of Facilities / Purchasers: .

Notification will be made to the above facilities immediately of the defect and the corrective actions being taken and that a kit will provided them as soon as possible which will totally correct any possibility of failure / damage.

1 1

For further information, the work necessary to complete this  ;

corrective action is very minor in nature and can be easily I accomplished on site by a qualified pipefitter. 1 1

Should your organization require any further information, I suggest you contact directly our Technical Director, Mr. Al Robinson. j Sincerely, COMSIP, Inc.

Delohi Systems Division I

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~ O k M" Claude Varinois l President CV:ns l