ML18029A558
| ML18029A558 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/10/1985 |
| From: | Domer J TENNESSEE VALLEY AUTHORITY |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8505300394 | |
| Download: ML18029A558 (8) | |
Text
REGULATORY I " RMATION DISTRIBUTION SYS
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ACCESSION NBR;8505300394 DOC ~ DATE: 85/05/10 NOTARIZED:
YES DOCKET FACIL:50-259 Browns Ferry Nuclear Power Stationi Unit 1~
Tennessee 05000259 50 260 Browns Ferry Nuclear Power Stations Un)t 2"~ Tennessee 05000260 50-296 Browns Ferry Nuclear Power Stations Unit 3i Tennessee 05000296 AUTH,NAME A/THOR AFFILIATION DOMERiJ.A, Tennessee Valley Authority RECIP ~ NAME, RECIPIENT AFFILIATION VASSALLO~D ~ BE Operating Reactor s Branch 2
SUBJECT:
Informs that reactor bldg closed cooling water sys does not meet closed loop acceptance criteria,8 will be backfitted to accommodate'ype C testing per 10CFR50iApp J<Mods scheduled during next refueling outage'ISTRIBUTION
-CODE:
A017L COPIES RECEIVED:LTR "ENCL SIZEe TITLE':
OR Submittal:
Append J Containment Leak Rate Testing NOTES:NMSS/FCAF
- 1cy, 1cy NMSS/FCAF/PM, OL:06/26/73 NMSS/FCAF 1cy ~
1cy NMSS/FCAF/PM, OL:06/28/74 NMSS/FCAF 1cy, 1cy NMSS/FCAF/PM'L:07/02/76 05000259 05000260 05000296 REC IP IENT ID CODE/NAME NRR ORB2 BC 01 INTERNAL; ACRS 07 ELD/HDS4 08 NRR/DSI/CSB 06 RGN2 COPIES LTTR ENCL>>
7 7
10 10 1,
1 1
1 1
R~CI~IENT ID CODE/NAME ADM/LFMB SB REG FILE 04 COPIES LTTR ENCL' 1
EXTERNAL+ LPDR NSIC NOTES; 03 05 1
1 1
1 2
2 NRC PDR 02 1
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TOTAL NUMBER OF COPIES REQUIRED!
LTTR 28 ENCL '7
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0 TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37@01 400 Chestnut Street Tower II May 10, 1985 Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactor Branch No.
2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Vassallo:
In the Matter of the Tennessee Valley Authority Docket No. 50-259 50-296~
50-296 I
Please refer to D. G. Eisenhut',s letter to H. G. Parris dated October 24, 1984 regarding 10 CFR 50 Appendix J compliance for. Browns Ferry Nuclear Plant.
In the referenced letter, NRC denied TVA's request for exemption of type C testing of the Reactor Building Closed Cooling Water (RBCCW) system isolation valves unless it could be shown that, the RBCCW system meets the closed-loop acceptance criteria stated in Standard Review Plan section 6.2.4.
TVA has reviewed the RBCCW system and found it not to meet the closed-loop acceptance criteria; therefore, the RBCCW system will be backfit to accommodate type C testing in accordance with 10 CFR 50 Appendix J.
The required modifications ar e scheduled for each unit during the next refueling outage which involves a type A test (integrated leak rate test),
beginning with the current unit 1 refueling outage.
As a result of an extensive review, Browns Ferry's Appendix J type B and C testing program is being expanded to include the components listed in the enclosure.
Each potential leak path identified in the enclosur e is currently tested during our Appendix J type A test program with satisfactory results; therefore, immediate action is not being taken.
Each new component test will require modifications on the respective system.
These additional tests will be added to the Appendix J program following modifications scheduled dur ing the next refueling outage which involves a type A test, beginning with the current unit 1 refueling outage.
An Equal Opportunity Employer
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Director of Nuclear Reactor Regulation May 10, 1985 If there are regulatory concerns or questions regarding this implementation, please get in touch with us thr ough the Browns Ferry Project Manager.
Ver y truly yours, Subscr ibe sworn to fore me thi
~day of
. A. Domer, Chief Nuclear Licensing Branch 1985.
Notary Public My Commission Expires Enclosur e cc (Enclosure);
U.S. Nuclear Regulatory Commission Region II ATTN: Dr. J. Nelson Grace, Regional Administr ator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue
- Bethesda, Maryland 20814
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ENCLOSURE Residual Heat Removal
~Com onent Identification No./Unit Modification Re uired RHR Air Return Valves FCV 74-102, FCV 74-103, FCV 74-119, FCV 74-120 (All units)
Add block valves, vent valves and test connections to type C test valves.
RHR.Suppression Chamber Spray Valve Bonnet FCV 74-58'Unit 2 and 3)
Orientate valve so the bonnet is tested during the type C test.
RHR Recirculation and Pump Test Valve Bonnet FCV 74-59 (Unit 3)
Orientate valve so the bonnet is tested during the type C test.
Hi h Pressure Coolant In'ection
~Com onent Minimum Flow Valve Bonnet Identification No. /Unit FCV 73-30 (All units)
Modification Re uired
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Add block valve and test connection so bonnet is-tested during type C test.
Reactor Core Isolation Coolin Component Identification No. /Unit Modification Required Minimum Flow Valve Bonnet FCV 71-34 (All units)
Install block valve to test bonnet.
Orifice Minimum flow orifice Install block valve to test orifice.
Auxilia Boiler
~Com onent Identification No./Unit Modification Re uired Auxiliary Boiler to RCIC Bonnet HCV 12-742 (All units)
Install block valve to test bonnet.
(Continued}
Core S ra
~Com anent Identification'o./Unit Modification Re unbred Suppression Chamber Pool High Level Control Valve Bonnet FCV 75-57 (All units)
Add block valve to test.
bonnet or cut out.valve and cap.
Containment Air Dilution CAD Supply Valves FSV 84-8A, FSV 84-8B FSV 84-8C, FSV 84-8D'dd block valves and test connec'tions to test valves in correct direction.