ML20035H645
| ML20035H645 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/28/1993 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| NUDOCS 9305060147 | |
| Download: ML20035H645 (4) | |
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nn Tennessee Valley Authonty. Post Othce Box 2000. Decatur, Alabama 3%09 APR 2 81993 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
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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 April 21, 1993,.the SCLR test was performed.
The specific parameters of the test are provided in Enclosure 1.
The overall leak rate was 9,102 cubic feet per minute (cfm).
This leak rate was below the allowable limit of 12,000.cfm I
specified by Surveillance Requirement 4.7.C.1.a.
There are no commitments contained in this letter.
If you have any questions, please telephone me at (205) 729-2636.
Sincerely 7
Salas Manager of Site Licensing f'f C A D C R i\\
9305060147 930428.
PDR ADOCK 05000259:
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Nuclear Regulatory Commission APR 2 81993 l
Enclosure l
cc (Enclosure) :.
NRC Resident Inspector I
Browns Ferry Nuclear. Plant Route 12, Box 637 Athens, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900.
Atlanta, Georgia 30323
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I ENCLOSURE BROWNS FERRY NUCLEAR PLANT (BFN)
SECONDARY CONTAINMENT LEAK RATE TEST l
1.0 Reoort l
Browns Ferry Nuclear Plant Secondary Containment Leak Rate i
Test Report, per Technical Specification 6.9.2.8.
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2.0 Purcose l
This report describes the results and analysis of the test i
data taken during leak rate testing of the Browns Ferry j
Nuclear Plant secondary containment.
This report satisfies i
l the report requirement of Technical Specification 6.9.2.8.
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l 3.0 Procedure Surveillance Instruction (SI) 0-SI-4.7.C-1, Combined Zone Secondary Containment Integrity Test, outlines the j
procedures followed during the secondary containment leak rate testing.
4.0 Data 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: 9,102 cfm Refueling Zone 5,571 cfm Reactor Zones 3,531 cfm
- 2) Reactor Building differential pressures:
Unit 1 Reactor Zone
- 0.34" H O 2
Unit 2 Reactor Zone
- 0.34" H O 2
Unit 3 Reactor Zone
- 0.36" H O 2
Unit 1 Refuel Zone
- 0.33" H O 2
Unit 2 Refuel Zone,
- 0.32" H O 2
Unit 3 Refuel Zone The Unit 3 Refuel Zone Reactor Building differential pressure instrument could not be read due to the presence of lead shielding.
The Units 1 and 2 Refuel Zone Reactor Building differential pressure instruments were considered adequate for the performance of this test.
I ENCLOSURE Page 2 of 2 -
BROWNS FERRY NUCLEAR PLANT (BFN)
SECONDARY CONTAINMENT LEAK RATE TEST l
(CONTINUED) 4.0 Data (Continued)
- 3) Wind Speed:
10.8 mph
- 4) Wind Direction 327.7*
- 5) Reactor Building air temperature 78'F
- 6) Outside air temperature 44.9"F 1
5.0 Analysis and Interoretation l
The combined zone secondary containment (all three zones and the common refueling. zone) was leak rate tested on April 21, 1993 using 0-SI-4.7.C-1.
The purpose.of-this test was to confirm secondary containment operability prior to the Unit 2 Cycle 6l 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 9,102 cfm while maintaining a vacuum of greater than 0.283 inches of-water (correction added for the i
wind speed in excess of 5 mph), which met the acceptance criteria specified by Surveillance Requirement 4.'7~C.1.a.
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