ML18032A433

Forwards 90-day Rept on Secondary Containment Leak Rate Testing.All Three Reactor Zones & Common Refuel Zone Tested on 870504.Test Satisfactorily Performed

ML18032A433
Person / Time
Site:	Browns Ferry
Issue date:	07/14/1987
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8707210652
Download: ML18032A433 (7)

Text

REGULA j AY INFORMATION DISTR IBUTIQN SYSTEM (RIDS)

ACCESSION NBR: 8707210652 DOC. DATE: 87/07/14 NOTARIZED: NO DOCKET 5 FACIL: 50-259 Browns Ferry Nuclear Power Station j Unit 1 j Tennessee 05000259 50-260 Browns Ferry Nuclear Power Stationj Unit 2j Tennessee 05000260 50-296 Browns Ferry Nuclear Power Stationj Unit 3j Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION GRIDLEYj R. Tennessee Valley Authority RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards 90 day rept on secondary containment leak rate testing. All three reactor zones 5 common refuel zone tested on 870504. Secondary containment capability of maintaining less than . 25 inches H20 w/less than 12j 000 CFM inleakage.

DISTRIBUTION CODE: A017D COPIES RECEIVED: LTR l ENCL TITLE: OR Submittal: Append J Containment Leak Rate Testing J SIZE:

NOTES: Zwolinski 3 cy. 1 cy ea to: Axelradj Ebneterj S. Richardsonj 05000259 Liawj G. Zechj OIj QIA.

Zwolinski 3 cy. icy ea to: Axelradj Ebneterj B. Richardsonj 05000260 Liawj G. Zechj OI j OIA.

Zwolinski 3 cy. icy ea to: Axelradj Ebneterj B. Richardsonj 05000296 Liawj G. Zechj QI j OIA.

REC IP IENT CQP IES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL JAMERSQN j C 1 0 PD, 5 5, GEARSj G 1 STANG j J 1 INTERNAL: ACRS 10 10 ARM/DAF/LFMB 1 0 N ST/PBB 1 1 OGC/HDB2 1 1 EG FIL 01 1 RES DEPY GI 1 1 RDI J 1 REB/DE/EIB 1 1 REB/DE/SBEB 1 1 REB/DRAA/SAID 1 1 REB/DRPB/RPBIB 1 1 EXTERNAL: LPDR 1 NRC PDR NBIC 1 1 NOTES: 12 12 TOTAL NUMBER OF COPIES REQUIRED: LTTR 43 ENCL 41

~ l P

F

~ i u

TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 5N 157B Lookout Place JUL I.4 1987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of the Application of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) REACTOR BUILDING CONTAINMENT LEAK RATE TEST 90-DAY REPORT Enclosed is the report on secondary containment leak rate testing for the Browns Ferry Nuclear Plant. The secondary containment for all three reactor zones and the common refuel zone was leak rate tested on May 4, 1987. This report is submitted pursuant to Browns Ferry technical specifications section 6.7.3.C.l.a. If you have any questions, please call G. W. Morris at (205) 729-3583.

Very truly yours, TENNESSEE VALLEY AUTHORITY

. Gridley, Safety and Licensing Di'rector'uclear Enclosure cc: See page 2

'I 87072i0b52 8707~259' 050 PDR ADOCN pD R~ 01$

An Equal Opportunity Employer

U.S. Nuclear Regulatory Commission 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 Mr. J. A. Zwolinski, Assistant Director for Projects Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission 4350 East West Highway EMW 322 Bethesda, Maryland 20814 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant P.O. Box 311 Athens, Alabama 35611

l.

fZf)

I "y ylgf) y' f i(k

'ly' y ~" y i yy yl "V (~ f yy'

,r yy y

ff y 'j,"I y 'yyyyf Q- yy yy "I lyy 'p I f jl~uyg f ill f yyiif

", 'rf',

~ I ly y g yy y lf 'lj,'ffyl C

yy f fy t f't',

g' ~

f II ~

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

2.0 ~ttose This report describes the results and analysis of the test data taken during leak rate testing of the BFN secondary containment system. The test was performed to verify the status of the secondary containment before commencement of outage activities conducted in and around the, fuel pool.

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

4.0 Data The SI was performed concurrently on all zones. SI 4.7.C data sheets list the following test data:

1. Standby Gas Greatment System flowrate: 9986 CFM

2. Reactor Building differential pressures Unit 1 Reactor Zone .29 in H20 Unit 2 Reactor Zone .31 in H20 Unit 3 Reactor Zone .29 in H20 Unit 1 Refuel Zone .29 in H20 Unit 2 Refuel Zone .30 in H20 Unit 2 Refuel Zone .29 in H20

3. Wind Speed 3.0 MPH

4. Wind Direction 332

5. Anal sis and Inte retation Technical specification 3.7.C.3. requires that secondary containment integrity be maintained in the refueling zone when performing operations over spent fuel pools. SI 4.7.C demonstrates secondary containment integrity by assessing the capability of the secondary containment system to maintain 1/4" water vacuum under calm wind (< 5 MPH) conditions with a system leakage rate of not more than 12,000 CFM (specified in BFN technical specification 4.7.C.l.a).

The secondary containment (all three reactor zones and the common refuel zone) was leak-rate tested per BFN SX 4.7.C on May 4, 1987.

The test was satisfactorily performed. The results proved the secondary containment capability of maintaining less than .25 inches H20 with less than 12,000 CFM inleakage.