ML18033A684
| ML18033A684 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/21/1989 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8903270359 | |
| Download: ML18033A684 (12) | |
Text
, gI:CELE~TED Dj/TRIBUTION DEMONST+TIO.'i SYSTEM I * ~
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8903270359 DOC.DATE: 89/03/21 NOTARIZED: NO FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee AUTH.NAME AUTHOR AFFILIATION GRIDLEY,R.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET 05000260
SUBJECT:
Forwards results of secondary leak rate containment rept per Tech Specs 6.9.2.8.
DISTRIBUTION CODE: A017D, COPIES RECEIVED:LTR J ENCL SIZE-TITLE: OR Submittal:
Append J Containment LeakMate Tes ing NOTES:1 Copy each to: S.Black,D.M.Crutchfield,B.D.Liaw,L.Watson 05000260 S
RECIPIENT ID CODE/NAME SIMMS,M GEARS,G INTERNAL: ACRS NRR/DEST/PSB 8D OGC/HDS2 RES TELFORD,J RES/DSIR/SAIB EXTERNAL: LPDR NSIC NOTES:
COPIES LTTR ENCL 1
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RECIPIENT ID CODE/NAME PD ARM/DAF/LFMB NUDOCS-ABSTRACT
@KG NML 01 RES/DE/SEB RES/DSR/RPS B NRC PDR COPIES LTTR ENCL 5
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1 NOTE TO ALL "RIDS" RECIPIEZIS:
PLEASE HELP US TO REDUCE WASTE!
OONI'ACZ '%HE DOQJMEN1'ONZBOL DESK, ROOM Pl-37 (EXT. 20079)
KO IKIMlMTHRKR NAME FROM DISTRIBUTION LISTS POR DOCUMENTS YOU DON'T NEED)
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TOTAL NUMBER OF COPXES REQUIRED:
LTTR 29 ENCL 27
e,
TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 5N 157B Lookout Place Ng 81%%
U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen;
, Docket No. 50-260 In the Matter of
)
Tennessee Valley Author) ty
)
BROWNS FERRY NUCLEAR PLANT (BFA) SECONDARY CONTAINMENT LEAK RATE (SCLR)
TEST REPORTS In accordance with the BFN Technical, Specifications (TS) 6.9.2.8 on the reporting of SCLR testing, TVA is providing the results of its tests.
On November 24,
- 1988, the SCLR test was performed (enclosure 1), the leak rate was 11,076 cubic feet per minute (cfm) (TS limit 12,000 cfm).
The leak rate was below TS limits, but because the procedure had been changed to allow for the use of additional air compressors (Surveillance Instruction limit 10,500 cfm), the secondary containment failed the test.
On November 26,
- 1988, a second SCLR test was performed (enclosure
- 2) after the air. compressors were removed from service, the result showed a leak rate of'1,853 cubic feet per minute.
Because of the high flow rate into secondary containment an effort was made to discover and repair the leakage sources.
On December 20, 1988 a
third test was performed resulting in a lower leak rate of 10,767 cfm (enclosure 3).
Please refer any questions or comments to Patrick P. Carier at (205) 729-3570.
Very truly yours, TENNESSEE V LLEY AUTHORITY Enclosures cc:
See page 2
R. Gridley, anager Nuclear Li nsing and Regulatory Affairs 8903270359 S9032i PDR ADOCK 05000260 P
PDC An Equal Opportunity Employer
Ei
U.S. Nuclear Regulatory Commission cc (Enclosures):
Ms.
S.
C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Ms. L. J.
Watson, Acting Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637
- Athens, Alabama 35609-2000
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ENCLOSURE 1
SECONDARY CONTAINMENT LEAK RATE TEST BROWNS FERRY NUCLEAR PLANT (BFN)
. 1.0
~Re ort Browns Ferry Nuclear Plant Secondary Containment Leak Rate Test
- Report, per Technical Specification 6.9.2.8.
2.0
~Per ose This report describes the results and analysis of the test data taken during leak rate testing of the Browns Ferry Nuclear Plant secondary containment, pursuant to Technical Specification 4.7.C.l.a.
3.0 Procedure Surveillance Instruction (SI) 4.7.C.outlines the procedures followed during secondary containment leak rate testing.
4.0 Data The SI was performed concurrently on all zones.
The following is the test data:
1.
Standby Gas Treatment System Flowrate:
2.
Reactor Building Differential Pressures Unit 1 Reactor Zone Unit 2 Reactor Zone Unit 3 Reactor 7one Unit 1 Refuel Zone Unit 2 Refuel Zone Unit 3 Refuel Zone 3.
Wind Speed 4.
Wind Direction 5 ~
Reactor Building Air Temp'erature 11,076 cfm
.31 in.
H,O
.28 in.
H>0
.25 in.
H,O
.30 in.
H,O
.30 in.
H,O
.29 in.
H,O 4.8 mph 29.50'5'F 6.
Outside Air Temperature 5.0 Anal sis and Inter retation 40.97'F The secondary containment (all three zones and the common refuel zone) was leak rate tested on November 24, 1988 using SI 4.7.C.
The purpose of this test was to establish secondary containment operability prior to loading fuel into the unit 2 reactor.
SI 4.7.C demonstrates secondary containment capability to maintain
.25 inch water vacuum under calm wind (<
5 mph) conditions with a system leakage rate if not more than 12,000 cfm.
The test showed an inleakage of 11,076 cfm while maintaining a vacuum of.25 inches water, which meets the acceptance criteria specified by technical
ENCLOSURE 1
Page 2 of 2 specifications, but did not met the site acceptance criteria of 10,500 cfm specified in the procedure.
The acceptance criteria had been reduced to allow the use of additional air compressors to provide service air for modifications activities.
The air compressors were then removed from service and the test was run again'n November 26, 1988.
,~
ENCLOSURE 2
SECONDARY CONTAINMENT LEAK RATE TEST BRONNS FERRY NUCLEAR PLANT (BFN) 1.0 2.0
~Re ort Browns Ferry Nuclear Plant Secondary Containment Leak Rate Test
- Report, per Technical Specification 6.9.2.8.
~Pur ose This report describes the results and analysis of the test data taken during leak rate testing of the Browns Ferry Nuclear Plant secondary containment, pursuant to Technical Specification 4.7.C.l.a.
3.0 Procedure 4.0 Surveillance Instruction (SI) 4.7.C is the procedure followed during secondar'y containment leak rate testing.
Data The SI was performed concurrently on all zones.
The following is the test data:
5.0 1.
Standby Gas Treatment System Flowrate:
2.
Reactor Building Differential Pressures Unit 1 Reactor Zone Unit 2 Reactor 7one Unit 3 Reactor Zone Unit 1 Refuel Zone Unit 2 Refuel Zone Unit 3 Refuel Zone 3.
Hind Speed 4.
Hind Direction 5.
Reactor Building Air Temperature 6.
Outside Air Temperature Anal sis and Inter retation 11,853 cfm
.32 in.
H,O
.30 in.
H20
.255 in.
H>0
.31 in.
H,O
.31 in.
H20
.31 in.
H>0 6.03 mph 159.61'1'F 59.88 'F The secondary containment (all three zones and the common refuel zone) was leak rate tested on November 26, 1988 using SI 4.7.C.
The purpose of this test was to establish secondary containment operability prior to loading fuel into the unit 2 reactor.
SI 4.7.C demonstrates secondary containment capability to maintain.25-inch water vacuum under calm wind (<
5 mph) conditions with a system leakage rate of less than 12,000 cfm.
The test showed an inleakage of 11,853 cfm while maintaining a minimum vacuum of.25 inches water, which meets the technical specification
ENCLOSURE 2
Page 2 of 2 acceptance criteria.
Investigations of the high flow rate revealed several leakage sources which were repaired and the test was run again on December 20, 1988.
V ENCLOSURE 3
SECONDARY CONTAINMENT LEAK RATE TEST BROWNS FERRY NUCLEAR PLANT (BFN) 1.0 2.0
~Re ort Browns Ferry Nuclear Plant Secondary Containment Leak Rate Test
- Report, per Technical Specification 6.9.2.8.
~Per ose This report describes the results and analysis of the test data taken during leak rate testing of the Browns Ferry Nuclear Plant secondary containment, pursuant to Technical Specification 4.7.C.l.a.
3.0 Procedure 4.0 Surveillance Instruction (SI) 4.7.C is the procedure followed during secondary-containment leak rate testing.
Data The SI was performed concurrently on all zones.
The following is the test data:
1.
Standby Gas Treatment System Flowrate:
10,767 cfm 2.
Reactor Building Differential Pressures Unit 1 Reactor Zone Unit 2 Reactor Zone Unit 3 Reactor Zone Unit 1 Refuel Zone Unit 2 Refuel Zone Unit 3 Refuel Zone
.31
.29
.25
.28
.30
.25 in.
H,O in.
H20 in.
H>0 in.
H~O in.
H~O 5.0 3.
Wind Speed 4.
Wind Direction 5.
Reactor Building Air Temperature 6.
Outside Air Temperature Anal sis and Inter retation 4.91 mph 165'0'F 47.5'F The secondary containment (all three zones and the common refuel zone) was leak rate tested on December 20, 1988 using SI 4.7.C.
The purpose of this test was to establish secondary containment operability prior to loading fuel into the unit 2 reactor.
SI 4.7.C demonstrates secondary containment capability to maintain.25-inch water vacuum under calm wind (<
5 mph) conditions with a system leakage rate of less than 12,000 cfm.
The test showed an inleakage of 10,767 cfm while maintaining a minimum vacuum of.25 inches water, which meets the technical specification acceptance criteria.
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