ML18031B270

Forwards 90-day Rept on Secondary Containment Leak Rate Testing for Unit 3,per Tech Spec Section 6.7.3.C.1.a

ML18031B270
Person / Time
Site:	Browns Ferry
Issue date:	04/01/1987
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8704080008
Download: ML18031B270 (6)

Text

REGULATO INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION>> NBR;8700080008 DOC ~ DATE'e 87/04/01 NOTARIZED'O DOCKE~T FACIL".50; 259 Browns Ferry Nucleary Power, Stations Unit 1< Tennessee 05000259 50.-260 Browns Ferry Nuclear Power Stations Unit 2'~ Tennessee'5000260 50-296'rowns Ferry Nucleary Power. Stationi. Unit 3,. Tennessee'5000296 AUTH;NAME" AUTHOR AFFILIATION GRIDLEY,R. Tennessee- Valley Authority RECIP ~ NAMEI RECIPIENT AFFILIATION Document Conti ol Branch (Document Control Desk)

SUBJECT:

-- Forwards 90 day rept on se'condary containment leak- rate testing for. Unit 3iper Tech- Spec Section 6 '>3,C ~ 1 ~ a.

COPIES'ECEIVED!LTiR DISTR'IBUT'ION CODE: A017D ENCL. 'IZE':

TITLE'. OR Submittal: Append J. Containment Leak Rate Testing NOTES:Zwolinski 5~ eye 1 cy ea to: Axelrad<EbnetergS,Richardson'g 05000259 "L.i awi G ~ Zechi OI'i OIA, Zwolinski 5l cy. 1cy ea to: Axelrad~EbnetergS.Richardson'IA 05000260 Li awi G Zechi OI i

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TENNESSEE VALLEY AUTHORITY 5N 157 Lookout Place APR iI I ]<87 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 3 REACTOR BUILDING CONTAINMENT LEAK RATE TEST 90-DAY REPORT Enclosed is the report on secondary containment leak rate testing for BFN unit

3. This report is submitted pursuant to BFN technical specifications section 6.7.3.C.1.a.

If you have any questions or need additional information, please get in touch with J. L. Turner at (205) 729-2853.

Very truly yours, TENNESSEE VALLEY AUTHORITY R. G idley, irector Nuclear Safety and Licensing Enclosure cc (Enclosure):

Mr. G. G. Zech, Assistant Director Regional Inspections Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission Region II 101 Marietta St., NW, Suite 2900 Atlanta, Georgia 30323 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant P.O. Box 311 Athens, Alabama 35611 i

8704080008 870401 pe PDR ADQCK 05000259 PDR An Equal Opportunity Employer

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ENCLOSURE SECONDARY CONTAINMENT LEAK RATE TEST BROWNS FERRY NUCLEAR PLANT (BFN) 1.0 BFN Unit 3 Secondary Containment Leak Rate Test Report per technical specification 6.7.3.C.l.a.

2.0 ~r<<ose This report describes the results and analysis of the test data taken during leak rate testing of the BFN secondary containment system pursuant to technical specification 4.7.C.1.a.

3.0 Procedure Surveillance Instruction (SI) 4.7.C outlines the procedure followed during secondary containment leak rate testing.

4.0 Data The Surveillance Instruction was performed concurrently on all zones.

Surveillance Instruction 4.7.C data sheets list the following test. data.

1. Standby gas treatment system flowrate 11,329 CFM

2. Reactor Building differential pressures Unit 1 Reactor Zone .28 inch of H20 Unit 2 Reactor Zone .29 inch of H20 Unit 3 Reactor Zone .26 inch of H20 Unit 1 Refuel Zone .28 inch of H20 Unit. 2 Refuel Zone .28 inch of H20

.Unit 3 Refuel Zone .28 inch of H20

3. Wind Speed 2.6 MPH

4. Wind Direction 288~ (WNW)

5. Temperatures Outside Temperature 57.8 F Inside Temperature <100~F

5.0 Anal sis and 1'nte retation Surveillance Instruction 4.7.C demonstrates secondary containment capability to maintain one-fourth inch of water negative gauge pressure under calm wind (<5 MPH) conditions with a system leakage rate of not more than 12,000 CFM. The technical specification allowable inleakage value of 12,000 CFM has been conservatively reduced by 500 CFM. This reduction was administratively imposed because of previously identified conditions concerning the seismic qualification of auxiliary boiler penetrations into secondary containment. The secondary containment (all three reactor zones and the common refuel zone) was leak rate usted on January 13, 1987. The test was satisfactorily performed, showing secondary containment capability of maintaining a gauge pressure of .26 inch of H20 with less than 11,500 CFM of inleakage.