ML20137X291
| ML20137X291 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/11/1997 |
| From: | Abney T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9704210210 | |
| Download: ML20137X291 (4) | |
Text
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Tennessee Valley Authority, Post office Box 2000, Decatur, Alabama 35609-2000 April 11, 1997 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 i
BROhWS FERRY NUCLEAR PLAN'I' (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 February 21, 1997, in' preparation for the Unit 3 Cycle 7 refueling outage.
The overall leak rate was 9,419 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 commitments contained in this letter.
If you have any questions regarding this report, please contact me at (205) 729-2636.
f
- Mncerely, 1
f i
n Mana of Licenifdf f
]
an Industry Affairs Enclosur cc:
See page 2
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9704210210 970411 DR ADOCK 0500 9
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- U.S;' Nuclear Regulatory Commission
[
'Page 2 April 11, 1997 l
Enclosure l
cc (Enclosure):
Mr. Mark S. Lesser, Branch Chief i
U.S. Nuclear Regulatory Commission Region II i
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. J.
F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 i
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ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 i
SECONDARY CONTAINMENT LEAK RATE (SCLR) TEST REPORT 1.0 Report BFN SCLR Test Report, per Technical Specification (TS) 6.9.2.8.
2.0 Purpose This report describes'the results and analysis of the test data taken during the February 21, 1997, 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: 9,419 cubic feet per minute (cfm)
Refueling Zone 5,452 cfm Reactor Zones 3,967 cfm 2.
Reactor Building Differential Pressures:
Unit 1 Reactor Zone
- 0.290" H 0 i
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Unit 2 Reactor Zone
- 0. 310 " H O 2
Unit 3 Reactor Zone 0.280" H O 2
Unit 1 Refuel Zone
- 0.290" H O 2
Unit 2 Refuel Zone
- 0.280" E0 2
Unit 3 Refuel Zone
- 0.300" H O 2
3.
Wind Speed:
' 7 miles per hour (mph) 4.
Wind Direction:
196* azimuth 5.
Reactor Building Air Temperature 71.4*F P
6.
Outside Air Temperature 66.8*F 5.0 Analysis and Interuretation The combined zone secondary containment (all three reactor zones and the common refueling zone) was leak rate tested on February 21, 1997, using 0-SI-4.7.C-1.
The purpose of this test was to confirm secondary containment operability prior to Unit 3 Cycle 7 refueling.
The SI results demonstrated secondary containment's capability to maintain > (0.25) inch water vacuum under calm wind
(< 5 mph) conditions with a l
system leakage rate of not more than 12,000 cfm.
The test results showed an inleakage rate of 9,419 cfm while i
maintaining a vacuum of greater than 0.263 (corrected value for 7.7 mph wind velocity) inches of water, which met the acceptance criteria (s 12,000 cfm) specified by BFN TS Surveillance Requirement 4.7.C.1.a.
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