ML19261C196

Forwards 90-day Technical Rept on Secondary Containment Leak Rate Testing

ML19261C196
Person / Time
Site:	Browns Ferry
Issue date:	03/14/1979
From:	Gilleland J TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19261C197	List: ML19261C196 ML19261C198
References
NUDOCS 7903190336
Download: ML19261C196 (1)

Text

fs TENNESSEE VALLEY AUTHC.EITY CH ATTANOOGA. TENNESSEE 37401 500C Chestnut Street Tower II ,

MAR 141979 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Region Il 101 Marietta Street, NW., Suite 3100 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

BROWNS FERRY NUCLEAR PLANT UNIT 3 - SECONDARY CONTAINMENT LEAK RATE TEST DAY REPORT In accordance with Browns Ferry Technical Specifications 6.7.3.C, we are submitting our summary technical report on secondary containment leak rate testing for unit 3 at Browns Ferry performed on September 9, 1978.

Very t uly yours, TENNESSEE VALLEY AUTHORITY J. E. Gilleland Assistant Manager of Power Enclosure cc (Enclosure):

Director (15)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Director (2) (

Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555

/

\

0'

'7 79031903% \ \

An Equal Opportunity Employer

1.0 Browns Ferry Nuclear Plant Unit 3 Secondary Containment Leak Rate e

Test Report 2.0 Purpose This report describes the results and analysis of the test data taken during leak rate testing of the Browns Ferry Nuclear Plant unit 3 secondary containment pursuant to Tech.ical Specification 4.7.C.l.c before the first refueling outage.

3.0 Procedure The attached surveillance instruction (SI), SI 4.7.C-1, outlines the procedures followed during secondary containment leak rate testing.

4.0 Data The attached surveillance instruction data sheets list the following test data:

(1) Standby gas treatment system flow rate: 9,000 scfm (2) Reactor building differential pressures:

Unit 1 reactor zone: -0.32" H 0 Unit 2 reactor zone: -0.27" H 0 Unit 3 reactor zone: -0.35" H O 2

Refueling zone average: -0.34" H 2O (3) Wind Speed: 2.7 mph (4) Wind direction: north 5.0 Analysis and Interpretation Technical Specification 4.7.C.l.c requires that secondary containment capability to maintain 1/4-inch water vacuum under calm (<5 mph) wind

Page 4 BF SI 4.7.C SI 4.7.C Secondary Containment Capability

3. PREREQUISITES (Continued) 3.10 Verify that a drywell or suppression chamber purge is not in process or planned during this test.

3.11 Verify on Data Sheet SI 4.7.C-1 that each of the doors are closed for the respcctive zones to be tested or the doors indicated by number (See Table 3.11 of Data Sheet SI 4.7.C-1) for all four zones.

4. PRECAUTIONS 4.1 Do not allow the main steam line tunnel temperature on any unit in operation to exceed 160 F. If this temperature is approached to within 10 F, stop the test and reestablish normal ventilation per OI 30 or provide another means for ventilating the main steam line tunnel to prevent a unit trip (trip point is 186 F).

4.2 Attempt to restrict testing time to 30 minutes.

5. LIMITATIONS AND ACTIONS 5.1 None

6. PROCEDURE 6.1 Initial and perform the indicated sections on the configuration to be tested on Data Sheet SI 4.7.C-1 and perform steps indicated below.

6.1.1 UlRZ - Perform section 6.2 and section 6.4.

6.1.2 U2R2 - Perform section 6.2 and section 6.4.

6.1.3 U3RZ - Perform section 6.2 and section 6.4.

6.1.4 RFZ - Perform section 6.3 and section 6.4.

6.1.5 UlRZ and RFZ - Perform sections 6.2, 6.3 and section 6.4.

Page 5 BF SI 4.7.C SI 4.7.C Secondary Containment Capabilities

6. PROCEDURE (Continued) 6.1.6 U2RZ and RFZ - Perform sections 6.2, 6.3 and section 6.4.

6.1.7 U3RZ and RFZ - Perform sections 6.2, 6.3 and section 6.4.

6.1.8 Reactor Building - Perform section 6.2 for each RZ, and section 6.3 for the RFZ and section 6.4 6.2 Manual Isolation of a Reactor Zone NOTE: HS-64-ll7, HS-64-120, HS-64-119, & HS-64-122 are spring return to normal.

6.2.1 Place HS-64-ll7 (Panel 9-25) in the TEST position for the reactor zone to be isolated. (Inboard and common valves) 6.2.2 Place HS-64-120 (Panel 9-25) in the TEST position for the reactor zone to be isolated. (Outboard valves) 6.2.3 Start SGTS trains A and B in accordance with 01 65 and verify actions and/or take data as indicated on Data Sheet SI 4.7.C-1 for the reactor zone that is being isolated.

NOTE: If a reactor zone is the only zone to be isolated, go to Section 6.4 and if the refuel zone is to be isolated complete Section 6.3 before going to Section 6.4.

6.3 Manual Isolation of the Plant Refueling Zone 6.3.1 Place HS-64-119 (Panel 9-25-1) in the TEST position.

(Inboard and common valves) 6.3.2 Place HS-64-122 (Panel 9-25-1) in the TEST position.

(Outboard valves) 6.3.3 Start SGTS trains A and B, if not already running, in accordance with OI 65 and verify actions and/or take data as indicated on Data Sheet SI 4.7.C-1 for the refueling zone.

' Page 13 BF SI 4.7.C DATA SIEET SI 4.7.C-1 (Continued) 5/11/76 Component / Process variable Verify and/or Record Initials /Date g

Configuration

' Ald

.- 6.1.1 UlRZ Configuration MA 6.1.2 U2RZ

'6 .1,. 3 U3RZ Configuratiort 6.1.4 RFZ Configuration U1RZ and RFZ Configuration alm-6.1.5 U2RZ and RFZ Configuration MM

, 6.1.6

'8 6.1.7 U3RZ and RFZ Configuration 6.1.8 Reactor Building Configuration I.]

1-HS-64-117. TEST Position /./A 6.2.1 2-HS-64-117 TEST Position A/d 3-HS-64-117 TEST Position ,

TEST Position 4)M 6.'2.2 1-HS-64-120

-] l/

/M 2-ES-64-120 TEST Position

' 3-HS-64-120 TEST Position START 6.2.3 SGTS Train A

~

START MA_

. or SGTS Train B or SGTS Train C START [AM

/

.2 Unit 1 Reactor Zone U-1 Reactor Zone Ventilation Sys. Shutdown i M

1-FCO-64-13 Closed

. 1-FCo-64-14 ,

closed 1-FCo-64-42 Closed T,[

1-FCo-64-43 Closed t

a

.