ML20236M649
| ML20236M649 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/01/1998 |
| From: | Abney T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9807140181 | |
| Download: ML20236M649 (4) | |
Text
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na Tennessee Valley Authonty. Post Othee Box 2000, Decatar, Atabama 35609 July 1, 1998 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 TEST REPORT This letter provides the 90-day special report for the BFN Secondary Containment Leak Rate (SCLR) test required by Technical Specification 6.9.2.8.
The SCLR test was performed on April 7, 1998, in preparation for the Unit 3 Cycle 8 mid-cycle outage to replace several fuel elements.
The overall leak rate was 9,363 cubic feet per minute (cfm).
This leak rate was below the allowable limit of 12,000 cfm l
specified by Surveillance Requirement 4.7.C.1.a.
The specific I
test parameters 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 (256) 729-2636.
S ncerel, g)
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Manager Lice oing _
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and Indus.ry Affa'rs AD!<
Enclosure cc:
See page 2 I
9807140181 980701 PDR ADOCK 05000259 p
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U.S. Nuclear Regulator 3 Commission Page 2 July 1, 1998 Enclosure cc (Enclosure):
p Regional Administrator U.S. Nuclear Regulatory Commission
' Region II l
61-Forsyth Street, S.W.
Suite 23T85 Atlanta, Georgia 30303 Mr. Harold O. Christensen, Branch Chief U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S.W.
Suite 23T85 Atlanta, Georgia 30303 NRC Resident Inspector
-Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. Albert W.
De Agazio,. Project Manager U.S. Nuclear Regulatory Commission One White Flint, North I
11555 Rockville Pike Rockville, Maryland 20852 l
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ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 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 April 7.
1998, 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 data were measured during the test:
1.
Standby Gas Treatment System Flow Rate:
9,363 cubic feet per minute (cfm)
Refueling Zone 5,433 cfm Reactor Zones 3,930 cfm 2.
Reactor Building Differential Pressures:
Unit 1 Reactor Zone
- 0.270" EbO Unit 2 Reactor Zone
- 0. 310" H O 2
. Unit 3 Reactor Zone
- 0.250" H O 2
Unit 1 Refuel Zone
- 0.2 60" H O 2
Unit 2 Refuel Zone
- 0.270" EbO Unit 3 Refuel Zone
- 0.260" H O 2
3.
Wind Speed:
2.6 miles per hour (mph)
)
_ _ _ = _ _ _ _ _ _ _ _
4.
Wind Direction:
179 azimuth 5.
Reactor Building Air Temperature 75.7* F 6.
Outside Air Temperature 70.3 F 5.0 Analysis and Interpretation The combined zone secondary containment (three reactor zones and the common refueling zone) was leak rate tested on April 7, 1998, using 0-SI-4.7.C-1.
The purpose of this test was to confirm secondary containment operability prior to the Unit 3 Cycle 8 mid-cycle outage to replace several fuel elements.
The SI results demonstrated secondary containment's capability to maintain greater than or equal to 0.25 inches of 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 9,363 cfm while maintaining a vacuum of greater than or equal to 0.250 inches of water, which met the acceptance criteria (s12,000 cfm) specified by BFN TS Surveillance Requirement 4.7.C.1.a.
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