ML20140F625

From kanterella
Jump to navigation Jump to search
Secondary Containment Leak Rate Test,Browns Ferry Nuclear Plant Unit 1
ML20140F625
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 06/07/1985
From: Hufham J
TENNESSEE VALLEY AUTHORITY
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8507120146
Download: ML20140F625 (4)


Text

{{#Wiki_filter:. ENCLOSURE SECONDARY CONTAINMENT LEAK RATE TEST BROWNS FERRY NUCLEAR PLANT UNIT 1 1.0 Browns Ferry Nuclear Plant Unit 1 Secondary Containment Leak Rate Test x Report per Technical Specification 6.7 3.C.1.a. 2.0' Purpose This report describes the results and analysis of the test data taken during leak rate testing of the Browns Ferry secondary containment system pursuant to Technical Specification 4.7.C.I.a. 30 Procedure Surveillance Instruction (SI 4.7.C) outlines the procedure followed during secondary containment leak, rate testing.. 4.0 Data The surveillance instruction was performed concurrently on all zones. SI 4.7.C data sheets list the following test data. 1. Standby gas treatment system flowrate: 10,947 CFM 2. Reactor building differen-tial pressures Unit 1 Reactor Zone .35 in H 0 Unit 2 Reactor Zone .27 in H 0 Unit 3 Reactor Zone .26 in H 0 Unit 1 Refuel Zone .29 in H 0 Unit 2 Refuel Zone .275 in H 0 Unit 3 Refuel Zone .275 in H 0 3 Wind Speed 7.38 MPH 4. Wind Direction 359 (north) 4 0507120146 850607 PDR ADOCK 05000259 M1 P PENT Jg

Page 2 5.0 Analysis and Interpretation Technical Specification 4.7.C.1.a requires that secondary containment capability to maintain 1/4" water vacuum under calm wind (55 MPH) conditions with a system leakage rcte of not more than 12,000 CFM shall be demonstrated at each refueling outage prio.c to refueling. Performance of SI 4.7.C is permissible under conditions of higher wind speeds (>5 MPH) provided a more stringent acceptance criteria is imposed on the differential pressure measured in each zone. The modified A P is shown in Table 1 (attached). The technical specification allowable inleakage value of 12,000 CFM has been conservatively reduced by 850 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 and the common refuel zone) was leak rate tested on April 16, 1985. The test was satisfactorily performed, showing secondary containment capability;of maintaining a vacuum of.26 in H O with less than 11,150 CFM of inleakage. 2

e' TABLE 1 f Zono Static Pressuro Requirements for Given Wind Velocity at 33 feet ] P 1 .25 -{3.44 x 10-4 (y2 - 25}(1) ~ yind Velocity Reauired 3 P (iL% 0-5 (!!PH) .250 ~ 6 .254 7 .258 h 8 .263 s 9 4 .269 } 10 >.276 11 .283 12 .291 1 13 .299 14 .309 j 15 .319 3 16 .329 17 .341 18 .353 19 .365 il l, 20 .379 l 21 .393 22 .400 l) 23 .423 24 .439 25 .456 >25 Calculate using the formuis above l l (1) Equation devcioped fr m FSAR section 12.2.2.9. [

9 TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 37401 400 Chestnut Street Tower II US JUll 13,1l0,. o 7 June 7, 1985 U.S. ' Nuclear Regulatory Comission Region II ATTN: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, Suite 2900 Atlanta, Coorgia 30323

Dear Dr. Crace:

BROWNS FERRY NUCLEAR PLANT UNIT 1 - REACTOR BUILDINC CONTAINMENT LEAK RATE TEST DAY REPORT Enclosed is the report on secondary containment leak rate testing for the Browns Ferry Nuclear Plc.nt unit 1. This report is submitted pursuant to Browns Ferry Technical Specifications Section 6.7.3.C.1.a. If you have any questions, please call R. E. Rogers 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 J. W. Hufh , Manager Li. ensing a Regulations Enclosure cc (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 Comission 7920 Norfolk Avenue Bethesda, Maryland 20814 1 An Equal Opportunity Employer -}}