ML20106J129
| ML20106J129 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/11/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8411010075 | |
| Download: ML20106J129 (3) | |
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot 400 Chestnut ytreet Tower II d, DCTI5 October 11,e r189844 l U.S. Nuclear Regulatory Commission
-Region IIe ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323
Dear Mr. O'Reilly:
BROWNS FERRY NUCLEAR PLANT UNIT 2 - REACTOR BUILDING CONTAINMENT LEAK RATE TEST DAY REPORT Enclosed is the report'on secondary containment leak rate testing for the Browns Ferry Nuclear Plant unit 2.
This report is submitted pursuant to Browns Ferry Technical Specifications Section 6.7.3.C.1.a.
If you have any questions, please call Jim Domer at FTS 858-2725.
To the best of my knowledge, I declare the statements contained herein are complete and true.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Ma ager Nuclear Licensing Enclosure oc (Enclosure):
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 l
An Equal Opportunity Employer g
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. ENCLOSURE SECONDARY-CONTAINMENT LEAK RATE TEST BROWNS FERRY NUCLEAR PLANT-UNIT 2 1.0' Browns Ferry Nuclear Plant Unit 2 Secondary Containment Leak Rate Test Report per Technical Specification 6.7.3.c.1.a.
2.0 Purcose This report describes the results and analysis of the test data taken during leak rate testing of the Browns Ferry Nuclear Plant Unit 2 secondary containment pursuant to Technical Specification 4.7.C.1.a.
3.0 Procedure Surveillance Instruction (SI) 4.7.C outlines the procedures followed.
during secondary containment leak rate testing.-
4.0 Dahn The surveillance instruction was performed concurrently on all zones.
The attached surveillance instruction data sheets list the following test data:
1.
Standby gas treatment system flowrate:
9,509 CFM 2.
Reactor building d "feren-tial pressures Unit 1 Reactor Zone
.50 in H 0
~
Unit 2 Reactor Zone
.36 in H 0 Unit 3 Reactor Zone
.365 in H 0 Unit 1 Refuel Zone
.37 in H 0 Unit 2 Refuel Zone
.37 in H 0 Unit 3 Refuel Zone
.37 in H 0 3.
Wind Speed 4.5 MPH 4.
Wind Direction 191 4
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a
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Page 2 5.0 Analysis and Interoretation
. Technical Specification 4.7.C.1.a requires that secondary containment capability to maintain 1/4" water vacuum under calm (15 MPH) wind conditions with a total system inleakage of not more than 12,000 CFM shall be demonstrated at each refueling outage prior to refueling.
The technical specification allowable inleakage value of 12,000 CFM has been conservatively reduced by 800 CFM. This reduction was administratively imposed because of an Engineering Design identified nonconformance concerning the seismic qualifications of auxiliary boiler penetrations into secondary containment.
The secondary containment (all three reactor zones ar,d the comon refuel zone) was leak rate tested on September 12, 1984. The test was satisfactorily performed. The results proved the secondary containment capability of maintaining less than.25 in H O with less than 11,200 CF14 of 2
of inleakage.
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