ML18029A558

Informs That Reactor Bldg Closed Cooling Water Sys Does Not Meet Closed Loop Acceptance Criteria & Will Be Backfitted to Accommodate Type C Testing Per 10CFR50,App J.Mods Scheduled During Next Refueling Outage

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)

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REGULATORY I " RMATION DISTRIBUTION SYS '< (RIDS)

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 "ENCL SIZEe outage'ISTRIBUTION

-CODE: A017L COPIES RECEIVED:LTR TITLE': OR Submittal: Append J Containment Leak Rate Testing NOTES:NMSS/FCAF 1cy, 1cy NMSS/FCAF/PM, 05000259 OL:06/26/73 NMSS/FCAF 1cy ~ 1cy NMSS/FCAF/PM, 05000260 OL:06/28/74 NMSS/FCAF 1cy, 1cy 05000296 NMSS/FCAF/PM'L:07/02/76 REC IP IENT COPIES R~CI~IENT COPIES ID CODE/NAME LTTR ENCL>> ID CODE/NAME LTTR ENCL' NRR ORB2 BC 01 7 7 INTERNAL; ACRS 07 10 10 ADM/LFMB ELD/HDS4 08 1, 1 SB NRR/DSI/CSB 06 1 REG FILE 04 1 RGN2 1 1 EXTERNAL+ LPDR 03 1 1 NRC PDR 02 1 1=

NSIC 05 1 1 NOTES; 2 2 TOTAL NUMBER OF COPIES REQUIRED! LTTR 28 ENCL '7

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0 TENNESSEE VALLEY AUTHORITY 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 Docket No. 50-259 Tennessee Valley Authority 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 refueling 1 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,

. A. Domer, Chief Nuclear Licensing Branch Subscr ibe sworn to fore me thi ~day of 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 FCV 74-102, FCV 74-103, Add block valves, vent Valves FCV 74-119, FCV 74-120 valves and test connections (All units) to type C test valves.

RHR .Suppression FCV Orientate valve so the is tested during 74-58'Unit Chamber Spray 2 and 3) bonnet Valve Bonnet the type C test.

RHR Recirculation FCV 74-59 Orientate valve so the and Pump Test (Unit 3) bonnet is tested during Valve Bonnet the type C test.

Hi h Pressure Coolant In'ection

~Com onent Identif ication No. /Unit Modification Re uired /

Minimum Flow FCV 73-30 Add block valve and test Valve Bonnet (All units) connection so bonnet is-tested during type C test.

Reactor Core Isolation Coolin Component Identification No. /Unit Modification Required Minimum Flow FCV 71-34 Install block valve to Valve Bonnet (All units) test bonnet.

Orifice Minimum flow Install block valve to orifice test orifice.

Auxilia Boiler

~Com onent Identification No./Unit Modification Re uired Auxiliary Boiler HCV 12-742 Install block valve to to RCIC Bonnet (All units) test bonnet.

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Core S ra

~Com anent Identification'o./Unit Modification Re unbred Suppression Chamber FCV 75-57 Add block valve to test.

Pool High Level Control (All units) bonnet or cut out.valve Valve Bonnet and cap.

Containment Air Dilution CAD Supply Valves FSV FSV 84-8A, 84-8C, FSV 84-8D'ddin FSV 84-8B block valves and test connec'tions to test valves correct direction.