ML20044C313
| ML20044C313 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/17/1993 |
| From: | Zeringue O TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9303220163 | |
| Download: ML20044C313 (4) | |
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1 TeEeE va$,*t$os PoAcmo % zm recur. coabama ms zxo MAR l'.I 1993 O.J 'ike"Zenngue va rese.t tuowns i eur Nucea. nwn U.S.
Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C.
20555 Gentlemen In the Matter of
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Docket Nos. 50-259 Tennessee Valley Authority
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50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - SECONDARY CONTAINMENT LEAK RATE (SCLR)
TEST REPORT This letter provides the periodic special report on the integrated leak rate test of Secondary containment that is required by Technical Specification 6.9.2.8.
On January 30, 1993, the SCLR test was performed.
The specific parameters of the test are provided in Enclosure 1.
The overall leak rate was 10,011 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.
There are no commitments contained in this letter.
If you have any questions, please contact G. D. Pierce, Interim Manager of Site Licensing, at (205) 729-7566.
Sincerely,
/ YON'ffd(
O. J.
Zeringue 220074 t
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U.
S. Nuclear Regulatory Commission MAR 171993 Enclosure cc (Enclosure):
NRC Resident Inspector
[
Browns Ferry Nuclear Plant Route 12, Box 637 l
Athens, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North i
11555 Rockville Pike
[
Rockville, Maryland -20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission i
Region II l
101 Marietta Street, NW, Suite 2900
.i Atlanta, Georgia 30323 i
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ENCLOSURE BROWNS FERRY NUCLEAR PLANT (BFN)
SECONDARY CONTAINMENT LEAK RATE TEST 1.0 Report Browns Ferry Nuclear Plant Secondary Containment Leak Rate Test Report, per Technical Specification 6.9.2.8.
2.0 Purpose This report describes the results and analysis of the test data taken during leak rate testing of the Browns Ferry Nuclear Plant secondary containment.
This report satisfies the report requirement of Technical l
Specification 6.9.2.8.
3.0 Procedure Surveillance Instruction (SI) 0-SI-4.7.C-1, combined Zone Secondary I
Containment Integrity Test, outlines the procedures followed during the secondary containment leak rate testing.
i 4.0 Data l
The SI was performed in a combined zone configuration. The friAowing is the data measured during the test:
1)
Standby Gas Treatment System flowrate:
10,011 cfm Refueling Zone 5,796 cfm i
Reactor Zones 4,215 cfm F
- 2) Reactor Building differential pressures I
Unit 1 Reactor Zone
- 0.27" H O 2
Unit 2 Reactor Zone
- 0.30" H:0 l
Unit 3 Reactor Zone
- 0.28" HO l
2 Unit 1 Refuel Zone
- 0.26" H O 2
Unit 2 Refuel Zone
- 0.26" H0 Unit 3 Refuel Zone
- 0. 2 5" H O 2
1
- 3) Wind Speed:
4.2 mph
- 4) Wind Direction 18.4*
1
- 5) Reactor Building air temperature 72.2*F l
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- 6) Outside air temperature 24.8'F I
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ENCLOSURE rasr 2 y2 BROWNS FERRY NUCLEAR PLANT (BFN)
SECONDARY CONTAINMENT LEAK RATE TEST (CONTINUED) 5.0 Analysis and Interpretation The combined zone secondary containment (all three zones and the common refueling zone) was leak rate tested on January 30, 1993 using 0-SI-4.7.C-1.
The purpone of this test was to confirm secondary containment operability prior to the Unit 2 Cycle 6 refueling.
0-SI-4.7.C-1 demonstrates secondary containment's capability to maintain inch water vacuum under calm wind (< 5 mph) conditions with a system leakage rate of not more than 12,000 cfm.
The test showed an inleakage rate of 10,011 cfm while maintaining a vacuum of greater than inches of water, which met the acceptance criteria specified by Surveillance Requirement 4.7.C.1.a.
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