ML18032A592
| ML18032A592 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/07/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8710140151 | |
| Download: ML18032A592 (14) | |
Text
REGULATORY FORMATION DISTRIHUTION SY M <RIDS)
ACCESSION NHR: 8710140151 DOC. DATE: 87/10/07 NOTARIZED'O FACIL: 50-259 Hrowns Ferry Nuclear Power Stations Unit ii Tennessee 50-260 Hrowns Ferry Nuclear Power Stationi Unit 2i Tennessee 50-2S'6 Hrowns Ferry Nuclear Power Stations Unit 3i Tennessee AUTH. NAME AUTHOR AFFILIATION QRIDLEYiR.
Tennessee Valley Authority RECIP. NAME RECIPIENT AFFILIATION Document. Control Branch
<Document Control Desk)
SUBJECT:
Forwards repts on secondary containment leak rate testing For Planti per Tech Specs Section
- 6. 7. 3. C. 1. a. Secondary conatainment for all three reactor zones Sc common refuel zone leak tested on 870708i 9. 12 5 24.
DIETRIBUTIQN CODE:
AOITD CQPIEB RECEIVED: LTR J ENCL J SIZE:
TITLE:
OR Submittal:
Append J Containment Leak Rate Testing NOTES: Zwolinski 3 cg.
1 cg ea to: Axelradi Ebneteri S.
Richardson'iawi Q. Zechi Oli OIA.
Zwolinski 3 cg. icy ea to:
Axe)radar Ebneteri S. Richardsoni Liawi G. Zechi Oli OIA.
Zwolinski 3 cg. icy ea to: Axelradi Ebneteri B. Richardsoni Liawi G. Zechi Oli OIA.
DOCKET O
05000259 05000260 0500029'6 05000259 05000260 05000296 REC IP IENT ID CODE/NAME JAMERSONi C GEARS' INTERNAL: ACRS N
RE 01 S
TELFORD> J RES/DRAA/BAIH EXTERNAL:
LPDR NSIC NOTES:
COP IEB LTTR ENCL 1
0 1
1 10 10 1
1 1
1 1
1 1
1 1
1 12 12 RECIPIENT ID CODE/NAME PD ST*NQ> J ARM/DAF/LFMH OQC/HDS2 RES DEPY QI RES/DE/SSEH RES/DRPB/RPSIH NRC PDR COP IEB LTTR ENCL 5
5 1
1 1
0 1
1 1
1 1
1 1
1 1
TOTAL NUMHER OF COPIES REQUIRED:
LTTR 42 ENCL 40
lW ll
TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE S7401 5N 157B Lookout Place OQT 07 I87 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
2055S Gentlemen:
In the Matter of the Tennessee Valley Authority Docket Nos. 50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) REACTOR BUILDING CONTAINMENT LEAK RATE TEST 90-DAY REPORT Enclosed are four reports on secondary containment leak rate testing for the BFN.
The secondary containment for all three reactor zones and the common refuel zone were leak rate tested on July 8, 9, 12, and 24, 1987.
These reports are submitted pursuant to BFN technical specifications section 6.7.3.C.l.a.
If you have any questions, please call G.
W. Morris at (205) 729-3583.
Very truly yours, TENNESSEE VALLEY AUTHORITY R. Gridley, Director Nuclear Licensing and Regulatory Affairs Enclosure cc:
See page 2
8710i40151 871007 PDR ADDCK 05000259 p
PDR An Equal Opportunity Employer
n P
II,,
U.S. Nuclear Regulatory Commission cc (Enclosure):
Mr. G.
G. Zech, Assistant Director Regional Inspections Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission Region II 101 Marietta St.,
NW, Suite 2900 Atlanta, Georgia 30323 Mr. J.
A. Zwolinski, Assistant, Director For Projects Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission 4350 East West Highway EWW 332
- Bethesda, Maryland 20814 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant P.O.
Box 311
- Athens, Alabama 35611
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Enclosure SECONDARY CONTAINMENT LEAK RATE TEST PERFORMED JULY 8, 1987 BROWS FERRY NUCLEAR PLANT (BFN) 1.0 BFN Secondary Containment Leak Rate Test Report per Technical Specification (TS) 6.7.3.C.l.a.
2.0 Putuose This report describes the results and analysis of the test data taken during leak rate testing of the BFN secondary containment
- system, pursuant to TS 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 Data The SI was performed concurrently on all zones.
SI 4.7.C data sheets list the following test data:
1.
Standby gas treatment system flowrate:
13,374 CFM 2.
Reactor building differential pressures Unit 1 Reactor Zone Unit 2 Reactor Zone Unit 3 Reactor Zone
.25 in H20
.28 in H20
.26 in H20 Unit 1 Refuel Zone Unit 2 Refuel Zone Unit 2 Refuel Zone
.28 in H20
.30 in H20
.26 in H20 3.
Wind Speed 4.
Wind Direction 5.
Anal sis and Inte retation 2.8 MPH 152 TS 4.7.C.l.a specifies that secondary containment be capable of maintaining 1/4-inch water vacuum under calm wind (< 5 MPH) conditions with a system leakage rate of not more than 12,000 CFM.
The secondary containment (all three reactor zones and the common refuel zone) was leak rate tested on July 8, 1987, The test results did not satisfy the leakage acceptance criteria of 12,000 CFM, however, the system was able to maintain a vacuum of.25 inches of water.
An investigation into the cause of the unacceptable leakage was begun.
This investigation revealed a
possible cause for the unacceptable test results and the test was run again on July 9, 19&7.
SECONDARY CONTAINMENT LEAK RATE TEST PERFORMED JULY 8, 1987 BROWNS FERRY NUCLEAR PLANT (BFN)
(continued)
Licensee Reportable Event Determination (LRED) 87-123-287 was generated.
Based on the conditions of the plant relative to TS limiting conditions for operation, the event was determined as not reportable.
SECONDARY CONTAINMENT LEAK-RATE TEST PERFORMED JULY 9, 1987 BROWNS FERRY NUCLEAR PLANT (BFN) 1.0 BFN Secondary Containment Leak Rate Test Report per Technical Specification (TS) 6.7.3.C.l.a.
2.0 Putu>ose This report describes the results and analysis of the test data taken during leak rate testing of the BFN secondary containment
- system, pursuant to TS 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.
SI 4.7.C data sheets list the following test data:
1.
Standby gas treatment system flowrate:
121420 CFM 2.
Reactor building differential pressures Unit 1 Reactor Zone Unit 2 Reactor Zone Unit 3 Reactor Zone
.29 in H20
.29 in H20
.29 in H20 Unit 1 Refuel Zone Unit 2 Refuel Zone Unit 2 Refuel Zone
.30 in H20
.31 in H20
.29 in H20 3.
Wind Speed 4.
Wind Direction 5.
Anal sis and Inte retation 2.5 MPH 54 TS 4.7.C.l.a specifies that secondary containment be capable of maintaining 1/4-inch water vacuum under calm wind (< 5 MpH) conditions with a system leakage rate of not more than 12,000 CFM.
The secondary containment (all three reactor zones and the common refuel zone) was leak rate tested on 'July 9, 1987.
The test results revealed an inleakage of 12,420 CFM while maintaining a vacuum of.29 inches water, which does not meet the leakage acceptance
- criteria, A search for areas of inleakage was initiated. This search revealed several major areas of air inleakage which were repaired, and the test was run again on July 12, 1987.
r
SECONDARY CONTAINMENT LEAK RATE TEST PERFORMED JULY 24, 1987 BROWNS FERRY NUCLEAR PLANT (BFN) 1.0 BFN Secondary Containment Leak Rate Test Report per Technical Specification (TS) 6.7.3.C.l.a.
2.0 Puru>ose This report describes the results and analysis of the test data taken during leak rate testing of the BFN secondary containment
- system, pursuant to TS 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 Data The SI was performed concurrently on all zones.
SI 4.7.C data sheets list the following test data:
1.
Standby gas treatment system flowrate:
10,762 CFM 2.
Reactor building differential pressures Unit 1 Reactor Zone Unit 2 Reactor Zone Unit 3 Reactor Zone
.30 in H20
.30 in H20
.30 in H20 Unit 1 Refuel Zone Unit 2 Refuel Zone Unit 2 Refuel Zone
.30 in H20
.31 in H20
.29 in H20 3.
Wind Speed 4.
Wind Direction 5.
Anal sis and Inte retation 6.2 MPH 320 TS 4.7.C.l.a specifies that secondary containment be capable of maintaining 1/4-inch water vacuum under calm wind (< 5 MPH) conditions with a system leakage rate of not more than 12,000 CFM.
The secondary containment (all three reactor zones and the common refuel zone) was leak rate tested on July 24, 1987 after repairing additional leaks that were found subsequent to the test performed on July 9, 1987.
The test was performed under wind conditions which were slightly higher than specified in the TS, however, in accordance with SI 4.7.C the wind conditions were taken into account, and the differential pressure requirement was adjusted from 0.25 to 0.255 inches of water vacuum.
The test data revealed an inleakage of 10,762 CFM while maintaining a vacuum of.29 inches water, which meets the acceptance criteria.
go 0
SECONDARY CONTA1NMENT LEAK RATE TEST PERFORMED JULY 12, 1987 BROWNS FERRY NUCLEAR PLANT (BFN) 1.0 BFN Secondary Containment Leak Rate Test Report per Technical Specification (TS) 6.7.3.C.l.a.
2.0
~ttose This report describes the results and analysis of the test data taken during leak rate testing of the BFN secondary containment
- system, pursuant to TS 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 SZ was performed concurrently on all zones.
SZ 4.7.C data sheets list the following test data:
1.
Standby gas treatment system flowrate:
10)935 CFM 2.
Reactor building differential pressures Unit 1 Reactor Zone Unit 2 Reactor Zone Unit 3 Reactor Zone
.27 in. H20
.28 in H20
.27 in H20 Unit 1 Refuel Zone Unit 2 Refuel Zone Unit 2 Refuel Zone
,28 in H20
.29 in H20
.27 in H20 3.
Wind Speed 4.5 MPH 4.
Wind Direction 275o 5.
Anal sis and Inte retation TS 4.7.C.l.a specifies that secondary containment capable of maintaining 1/4-inch water vacuum under calm wind (< 5 MPH) conditions with a system leakage rate of not more than 12,000 CFM.
The secondary containment (all three reactor zones and the common refuel zone) was leak rate tested on July 12, 1987.
The test data revealed an inleakage of 10,935 CFM while maintaining a vacuum of.27 inches water, which meets the acceptance criteria.
V 1