ML18038B014

Forwards Periodic Special Repts on Integrated Leak Rate Testing of Secondary Containment Required by TS 6.9.2.8

ML18038B014
Person / Time
Site:	Browns Ferry
Issue date:	11/15/1994
From:	Salas P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9411220184
Download: ML18038B014 (12)

Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9411220184 DOC.DATE: 94/11/15 NOTARIZED: NO FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION SALAS,P.

Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards periodic special repts on integrated leak rate testing of secondary containment required by TS 6.9.2.8.

DISTRIBUTION CODE:

A017D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal:

Append J Containment Leak ate Te ting NOTES DOCKET 05000259 05000260

'5000296 RECIPIENT ID CODE/NAME PD2-4 WILLIAMS,J.

INTERNAL: ACRS OGC/HDS3 RES/DSIR/SAIB EXTERNAL: NOAC COPIES LTTR ENCL 1

0 2

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1 RECIPIENT ID CODE/NAME PD2-4-PD

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1 RES/DE/SEB NRC PDR COPIES LTTR ENCL 1

1 1

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1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE KVASTE!CONTACTTHE DOC! 'MENTCONTROL DESK. ROOM Pl-37 (EXT. 504-2083 ) TO ELlih!INATE YOUR. JAME FROII DISTRIBUTIONLISTS I'OR DOCUMENTS YOU DON"I'LED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 16 ENCL 15

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Tennessee Valley Authority. Post Office Box 2000, Decatur, Alabama 35609 November 15, 1994 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of Tennessee Valley Authority

)

Docket Nos.

50-259

)

50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)

SECONDARY CONTAINMENT LEAK RATE (SCLR)

TEST REPORTS This letter provides the periodic special reports on the integrated leak rate testing of Secondary Containment that is required by Technical Specification 6.9.2.8.

On September 30, 1994, at the start of the Unit 2 Cycle 7

refueling outage, the SCLR test was performed.

The specific parameters of the test are provided in Enclosure 1.

The overall leak rate was 9,270 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.

Subsequent to this SCLR test, planned maintenance was performed on the secondary containment boundary, with special emphasis on the seals for the isolation dampers.

The SCLR test was again performed on October 19, 1994.

The specific parameters of the test are provided in Enclosure 2.

The overall leak rate was 7,951 cfm.

This leak rate was also below the allowable limit of 12,000 cfm specified by Surveillance Requirement 4.7.C.1.a.

9411220i84 94illS PDR ADOCK 0500025'sf PDR

U.S. Nuclear Regulatory Commission Page 2

November 15, 1994 There are no commitments contained in this letter. If you have any questions, please telephone me at (205) 729-2636.

Sincerel Pedro Salas Manager of Site Licensing Enclosures cc:

see page 3

h

U.S. Nuclear Regulatory Commission Page 3

November 15, 1994 Enclosures cc(Enclosures):

Mr. Mark S. Lesser, Section Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

.NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637

Athens, Alabama 35611 Mr. J.

F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852

P

ENCLOSURE 1

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS'g 2g AND 3 SECONDARY CONTAINMENT LEAK RATE TEST

1. 0 Rior t BFN Secondary Containment Leak Rate Test Report, per Technical Specification 6.9.2.8.

2.0

~Pur oee This report describes the results and analysis of the test data taken during the September 30, 1994 leak rate testing of the BFN secondary containment.

This report, satisfies the report requirement of Technical Specification 6.9.2.8.

3.0 Procedure Surveillance Instruction (SI) O-SI-4.7.C-1, Combined Zone Secondary Containment Integrity Test, outlines the procedures followed during the secondary containment leak rate testing.

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:

9,270 cfm Refueling Zone Reactor Zones 5,592 cfm 3,678 cfm 2.

Reactor Building differential pressures:

Unit 1 Unit 2 Unit 3 Unit 1 Unit 2 Unit 3 Reactor Zone Reactor Zone Reactor Zone Refuel Zone Refuel Zone Refuel Zone

0. 28>>

H20

0. 29>>

H~O

0. 28>>

H~O 0 27>>

H20 0'27>>

H20

0. 27>>

H~O

4.0 Data Continued 3.

Wind Speed:

4.

Wind Direction 2.68 mph 102 'o 5.

Reactor Building air temperature 80.2'F 6.

Outside air temperature 73.3oF 5.0 Anal sis and Inter retation The combined zone secondary containment (all three zones and the common refueling zone) was leak rate tested on September 30, 1994 using O-SI-4.7.C-1.

The purpose of this test was to confirm secondary containment operability prior to the Unit 2 Cycle 7 refueling.

O-SI-4.7.C-1 demonstrates secondary containment's capability to maintain

> inch water vacuum under calm wind (< 5 mph) conditions with a system leakage rate of not more than 12,000 cfm (11,967 cfm for secondary containment and 33 cfm for the Unit 2 post.-accident sampling system).

The test showed an inleakage rate of 9,270 cfm while maintaining a vacuum of greater than 0.27 inches of water, which met the acceptance criteria specified by Surveillance Requirement 4.7.C.1.a.

E1-2

ENCLOSURE 2

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1i 2i AND 3 SECONDARY CONTAINMENT LEAK RATE TEST

1. 0

~Re ort BFN Secondary Containment Leak Rate Test Report, per Technical Specification 6.9.2.8.

2.0

~Pur ose This report describes the results and analysis of the test data taken during the October 19, 1994 leak rate testing of the BFN secondary containment.

This report satisfies the report requirement of Technical Specification 6.9.2.8.

3.0 Procedure Surveillance Instruction (SI) O-SI-4.7.C-1, Combined Zone Secondary Containment Integrity Test, outlines the procedures followed during the secondary containment leak rate testing.

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:

7,951 cfm Refueling Zone Reactor Zones 4,756 cfm 3, 195 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

0. 27" H~O

0. 27'r H~O 0 27" H~O

0. 26" H~O

0. 26" H~O

0. 26" HRO

4.0 Data Continued 3.

Wind Speed:

4.

Wind Direction 5.

Reactor Building air temperature 6.

Outside air temperature 3.4 mph 178 o 82.1~F 68~F 5.0 Anal sis and Inter retation The combined zone secondary containment (all three zones and the common refueling zone) was leak rate tested on October 19, 1994 using 0-SI-4.7.C-1.

The purpose of this test was to confirm secondary containment operability, after the maintenance was performed on the secondary containment boundary and prior to the Unit 2 Cycle 7

refueling.

O-SI-4.7.C-1 demonstrates secondary containment's capability to maintain

> inch water vacuum under calm wind

(< 5 mph) conditions with a system leakage rate of not more than 12,000 cfm (11,967 cfm for secondary containment and 33 cfm for the Unit 2 post-accident sampling system).

The test showed an inleakage rate of 7,951 cfm while maintaining a vacuum of greater than 0.26 inches of water, which met the acceptance criteria specified by Surveillance Requirement 4.7.C.l.a.

E2-2

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