ML17261B009

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Special Rept:On 900213,inoperable Fire Damper I-411-21-P Found.Caused by Improper Damper Installation.Replacement Damper in Procurement Process & Will Be Installed by Jul 1990
ML17261B009
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/16/1990
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Russell W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 9003270020
Download: ML17261B009 (4)


Text

ACCELERATED DISTIUBUTION DEMONSTF&TION SYSTEM 0

SUBJECT:

Special rept: on 900213,inoperable f DISTRIBUTION CODE:

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9003270020 DOC.DATE: 90/03/16 NOTARIZED:

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FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATXON MECREDY,R.C.

Rochester Gas

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION RUSSELL,W.T.

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ROCHESTER GAS AND ELECTRIC CORPORATION

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0 a~ra -c r>>e 5~6 R March 16, 1990 Mr. William T. Russell, Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406

Subject:

Thirty (30)

Day Special Report Inoperable Fire Damper I-411-.21-P R.E.

Ginna Nuclear Power Plant, Unit No.

1 Docket No. 50-244

Dear Mr. Russell:

In accordance with Technical Specification 3.14.6.1 (a),

this thirty day special report on Fire Dampers is being submitted.

On February 13, 1990, during performance of PT-13.26, Testing of Fire Dampers, it was determined that Ruskin fire damper, model number

IBD23, type "A" had a

missing side wall damper blade track.

As a result, this fire damper would not properly close and the damper was declared inoperable at 1540 hrs.

On February 13, 1990 an hourly surveillance was established in accordance with Technical Specification 3.14.6.1.

Damper I-411-21-P is located at elevation 278'-4>> between column lines 4 and 5 in the controlled Auxzliary Build>,ng, Fire damper I-411-21-P is installed in a

3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rated bar'rier between the controlled Auxiliary Building and the controlled Intermediate Building at elevation. 278'4".

3 A new Ruskin fire damper, model number IBD23, type A, 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> UL A labeled fire damper has been ordered.

The replacement damper is in the procurement, process and plans are to 'install the damper by

July, 1990.

The most probable root cause of the damper failure can be attrib-uted to impr'oper original damper installation.

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Although this fire damper was declared a non-intact fire barrier seal on February 13,

1990, the barrier degradation does not prevent the plant from attaining safe shutdown in the event of a fire.

This conclusion is based on the actual fire loadings:

1.

Fire damper I-411-21-P separates fire zone ABO-3W (Auxiliary Building Operating Level West) and fire zone IBS-2 (Intermediate Building Operating Level South).

Fire zone ABO-3W'omprises 2500 square feet.

The maximum design basis fire loading for this zone is 240,000 BTU's/SqFt.

Existing fire loading is 8,721 BTU S/Sq.Ft with an available heat release of 1120 degrees F.

The fire resistance for the actual fire loading condition would be 0.11 'ours for complete fire fuel reduction.

Fire zone IBS-2 comprises 2385 square feet.

The maximum design basis fire loading for the zone is 160,000 BTU/Sq.Ft.

Existing fire loading for this zone is 20,470 BTU's/Sq.Ft.

with an available heat release of 1415 degrees F.

The fire resistance for the actual fire loading conditions would be 0.26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> for complete fire fuel reduction.

2 ~

These two fire zones/areas (ABO-3W and IBS-2) are monitored by their respective fire detection systems.

In addition, fire extinguisher and hose stations are available for each fire zone/area.

Actions that have been taken or will be taken to prevent future problems with fire dampers:

1 ~

2 ~

Completion of 1004 inspection of the fire dampers by drop testing by April 1991.

Each subsequent

year, 104 of the dampers will be drop tested each year.

Inspection of 1004 of the fire dampers once every eighteen (18) months. This program was implemented on January 1990.

Ve truly yours, Robert C.

M cred Division Man ge Nuclear Production xc: U.S. Nuclear Regulatory Commission (original)

Document Control Desk Washington, D.C. 20555 Ginna Senior Resident Inspector