ML18038B118
| ML18038B118 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/06/1995 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18038B119 | List: |
| References | |
| NUDOCS 9502090305 | |
| Download: ML18038B118 (6) | |
Text
P R.IC)R.IT V 7'ACCELERATED RIDS PROCESSli REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
SUBJECT:
Forwards "Reactor Containment Bldg ILRT Brown Ferry Nuclear Plant Unit 2 Conducted 941105-07."
Requests NRC approval of BFN subsequent CILRT (Type A test) schedule, since as-found primary containment total leak rate exceeded TS limit.
DISTRIBUTION CODE:
A017D COPIES RECEIVED:LTR 4 ENCL SIZE:
TITLE: OR Submittal,:
Append J 'Containment Leak Rate Testing
+ ///
NOTES ACCESSION,NBR:9502090305 DOC.DATE: 95/02/06 NOTARIZED: NO DOCKET FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, ennessee 05000260 AUTH.NAME AUTHOR AFFILIATION SALAS,P.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Documen Control Desk)
RECIPIENT ID CODE/NAME PD2-4 WILLIAMS,J.
INTERNAL: ACRS NRR/DE/ECGB OGC/HDS3 RES/DSIR/SAIB EXTERNAL: NOAC COPIES LTTR ENCL 1
0 1
1 6
6 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD2-4-PD
~E -CE 1
NRR/DS SA/S CS B RES/DE/SEB NRC PDR COPIES LTTR ENCL 1
1 1
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1 Y'OTE TO ALL"RIDS" RECIPIENTS:
PLEASE HEL'P VS TO REDUCE KVKSTE!CONTACT I HE DOCL'CLIENT CONTROL DESK. ROOII I'Pl-37 IEXT. 504-~083 ) TO I'.LIXIINATEYOLR %ANILPRO%I DISTRI0 VTIONLISTS I:OR DOCI:4!EN'I'S YOI'ON"I'L'ED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 17 ENCL 16 I
(nlrb
45
Tennessee Valley Authority. Post Oftice Box 2000, Decatur, Alabama 35609 10 CFR 50, Appendix J February 6,
1995 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Nashington, D.C.
20555 Gentlemen:
In the Matter of
)
Tennessee Valley Authority
)
Docket No. 50-260 BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST (CILRT)
In accordance with 10 CFR 50, Appendix J, Section V.B.1 and BFN Technical Specification (TS) Section 6.9.2.5, TVA submits in the enclosure a copy of BFN's Unit 2 CILRT.
In addition, TVA requests NRC approval of BFN's subsequent CILRT (Type A test) schedule.
BFN TS requires a CILRT be performed as part of the surveillance program to demonstrate the continuing leak-tight integrity of the reactor containment building primary containment.
TVA conducted an as-left CILRT on BFN Unit 2 from November 5 through 7, 1994, in preparation for return to power operation.
The as-left test was successfully completed.
However, during the performance of Type C local leak rate
- tests, one penetration path (X-26 Heating and Ventilation
- system, drywell exhaust) leaked.
This path consists of primary containment isolation valves 2-FCV-64-29 (inboard isolation valve) and 2-FCV-64-30 (outboard isolation valve).
The leakage from this penetration path resulted in a minimum path leakage in excess of the TS limit of 0.75 L,.
As a result, the calculated as-found primary containment total leak rate (as-found Type A test) also exceeded the 0.75 L, TS requirement.
Since the as-found primary containment total leak rate exceeded the 0.75 L, TS limit, BFN TS Section 4.7.A.2.b requires the test schedule for subsequent Type A tests to be reviewed and approved by NRC.
Since the cause of the as-found test failure was due to excessive leakage from one penetration
- path, TVA concludes that the conditions which caused the excessive leakage can best be addressed through
'tt5020'st 0305 95020b PDR ADOCK 05000260 p
U.'S. Nuclear Regulatory Commission Page 2
February 6,
1995 local leak rate testing.
Therefore, TVA requests NRC approval to continue with the, normal CILRT testing schedule.
The next CILRT is scheduled to be performed during the Unit 2 Cycle
.9, refueling outage which is,currently scheduled for March 1998.
The enclosure includes the following information:
(1) Introduction, (2)
- Summary, (3) Test Purpose And Results, (4) Conduct Of Test, (5) Measurements And Calculations, (6) Analysis Of Test Data, (7) Conclusion.
There are no commitments contained in this letter. If you have any questions please contact me at (205) 729-2636.
Sin Salas Manager of Site Licensing Enclosure cc (Enclosure):
'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'thens, Alabama 35611 I.
Mr. J,.
F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike,.
Rockville, Maryland 20852 I.
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