ML20117N696
| ML20117N696 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/17/1996 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9606240095 | |
| Download: ML20117N696 (4) | |
Text
l Tennessee Valley Authority. Post Othce Box 2000. Decatur, Alabama 35609 June 17, 1996 I
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) - UNITS 1, 2, AND 3 -
SECONDARY CONTAINMENT LEAK RATE (SCLR) TEST RESULTS This letter provides the periodic special report for the BFN SCLR test required by Technical Specification 6.9.2.8.
The SCLR test was performed on March 22, 1996, in preparation for Unit 2 refueling.
The overall leak rate was 10,532 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 ccmmitments contained in this letter.
If you have any quest ions regarding this report, please contact me at (205) 729-26'6.
Sinc
.ly edro Salas Manager of Site Licensing Enclosure cc:
See page 2 24002G 9606240095 960617 DR ADOCK 05000259 I
U.S. Nuclear Regulatory Commission Page 2 June 17, 1996 Enclosure cc (Enclosure):
Mr. Mark S. Lesser, Branch Chief j
U.S. Nuclear Regulatory Commission Region II l
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 i
Mr. J.
F. Williams, Project Manager U.S. Nuclear Regulatory Commission one White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
l I
ENCLOSURE I
TENNESSEE VALLEY AUTHORITY
(
BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 i
SECONDARY CONTAINNENT LEAK RATE (SCLR) TEST REPORT 1.0 ReDort BFN SCLR Test Report, per Technical Specifi>.ation (TS) 6.9.2.8.
2.0 Purpose This report describes the results and analysis of the test data taken during the March 22, 1996, leak rate testing of the BFN secondary containment.
This report satisfies the reporting requirements of TS 6.9.2.8.
3.0 Procedure Surveillance Instruction (SI) 0-SI-4.7.C-1, Combined Zone Secondary Containment Integrity Test, outlines the procedures followed during the SCLR test.
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:
10,532 cubic feet per minute (cfm)
Refueling Zone 6,021 cfm Reactor Zones 4,511 cfm 2.
Reactor Building Differential Pressures:
Unit 1 Reactor Zone
- 0. 310" H O 2
Unit 2 Reactor Zone
- 0. 3 2 0" Hp3 Unit 3 Reactor Zone
- 0. 315" H O 2
Unit 1 Refuel Zone
- 0.285" H O 2
Unit 2 Refuel Zone
- 0.295" Hp0 Unit 3 Refuel Zone
- 0.300" Hy3 3.
Wind Speed:
3.86 miles per hour (mph) 4.
Wind Direction:
343' azimuth 5.
Reactor Building Air Temperature 69.1*F 6.
Outside Air Temperature 51*F 1
l l
~
-5.0" Analysis and Interoretation The combined zone secondary containment (all three zones and the common refueling zone) was leak rate tested on March 22, 1996, using 0-SI-4.7.C-1.
The purpose of this 4
test was to confirm secondary containment operability prior to Unit 2 Cycle 8 refueling.
The SI results demonstrated secondary containment's capability to maintain (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 10,532 cfm while maintaining a vacuum of greater than 0.285 inches of water, which met the acceptance criteria (s 12,000 cfm) specified by BFN TS Surveillance Requirement 4.7.C.1.a.
j 1
I