ML18038B596

Provides Periodic Special Rept for Secondary Containment Integrated Leak Rate Test Required by TS 6.9.2.8

ML18038B596
Person / Time
Site:	Browns Ferry
Issue date:	01/05/1996
From:	Salas P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9601160391
Download: ML18038B596 (8)

Text

CATEGORY j.

't REGULAT INFO~TION DISTRIBUTION

'STEM (RIDS)

ACCESSION NBR:9601160391 DOC.DATE: 96/01/05 NOTARIZED:

NO DOCKET FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH.NAME AUTHOR AFFILIATION SALASgP.

Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Provides periodic special rept for secondary containment integrated leak rate test required by TS 6.9.2.8.

DISTRIBUTION CODE: A017D COPIES RECEIVED:LTR ENCL SIZE:

TITIE: OR Submittal:

Append J Containment Leak Rate Testing NOTES:

RECIPIENT ID CODE/NAME PD2-3 WILLIAMS,J.

INTERNAL: A'CRS NRR/DE/ECGB OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK/

ROOM OWFN 5D"5(EXT. 415-2083)

TO ELIMINATE YOUR NAME,FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 16

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Tennessee Valley Authority, Post Office Box 2000, Oecatur, Afabama 35609 January 5,

1996 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of Tennessee Valley Authority Docket Nos.

50-259 50-260 50-296 BROWNS PERRY NUCLEAR PLANT (BFN) - SECONDARY CONTAINMENT LEAK RATE (SCLR)

TEST RESULTS This letter provides the periodic special report for the Secondary Containment integrated leak rate test required by Technical Specification 6.9.2.8.

The SCLR test was performed on October 12, 1995, in preparation for Unit 3 refueling.

The overall leak rate was 10,393 cubic feet per minute (cfm).

This leak rate was below the allowable limit of 12,000 cfm specified by Surveillance Requirement 4.7.C.1.a.

and was acceptable.

The specific parameters of the test are provided in the Enclosure.

There are no commitments contained in this letter. If you have any questions regarding this report please contact me at (205) 729-2636.

Sincere Salas Manager of Site Licensing Enclosure cc:

See page 2

'tf60i160391 960i05 PDR ADQCK 0500025tf p

PDR 180b4'p

U.S. Nuclear Regulatory Commission Page 2

January 5,

1995 Enclosure cc (Enclosure):

Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road

Athens, Alabama 35611 Mr. J.

F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS ii 2~

AND 3 SECONDARY CONTAINMENT LEAK, RATE TEST 1.0

~Re out BFN Secondary Containment Leak Rate Test Report, per Technical Specification 6.9.2.8.

2.0

~Pur oee This report describes the results and analysis of the test data taken during the October 12,

1995, leak rate testing of the BFN secondary containment.

This report satisfies the reporting requirements of Technical Specification 6.9.2.8.

3.0 Procedure Surveillance Instruction (SI) 0-SI-4.7.C-l, Combined Zone Secondary Containment Integrity Test, outlines the procedures followed during the secondary containment leak rate test.

4.0 The SI was performed in a combined zone configuration.

The following is the data measured during the test:

1.

Standby Gas Treatment System Flow Rate:

10,393 cubic feet per minute (cfm)

Refueling Zone Reactor Zones 6,002 cfm 4,391 cfm 2.

Reactor Building Differential Pressures:

Unit Unit Unit Unit Unit Unit 1 Reactor Zone 2 Reactor Zone 3 Reactor Zone 1 Refuel Zone 2 Refuel Zone 3 Refuel Zone

0. 28" H~Q Oe 29n H~O 0 28 ii H20

0. 25" H~O 0 28 ii H20 0'8ii H20 3.

Wind Speed:

4.

Wind Direction:

2.6 miles per hour (mph) 345'zimuth

5.

Reactor Building Air Temperature 6.

Outside Air Temperature 5.0 Anal sis and Inter retation 79.9oF 73.30F The combined zone secondary containment (all three zones and the common refueling zone) was leak rate tested on October 12, 1995, using O-SI-4.7.C-1.

The purpose of this test was to confirm secondary containment operability prior to the Unit 3 Cycle 6 refueling.

Performance of Surveillance Instruction, O-SI-4.7.C-l, demonstrates secondary containment's capability to maintain at least (0.25) inch water vacuum under calm wind (( 5 mph) conditions with a system leakage rate of not more than 12,000 cfm.

The test results showed an inleakage rate of 10,393 cfm while maintaining a vacuum of greater than 0.27 inches of water, which met the acceptance criteria specified by Surveillance Requirement 4.7.C.1.a.