ML19270G401

Responds to 790508 Request.Submits post-mod Test Plans for Auxiliary Feedwater Pump Dynamic Brake,Interim Anticipatory Reactor Trip Sys & Auxiliary Feedwater Flow Indicators

ML19270G401
Person / Time
Site:	Davis Besse
Issue date:	05/26/1979
From:	Roe L TOLEDO EDISON CO.
To:	Reid R Office of Nuclear Reactor Regulation
References
511, NUDOCS 7906060280
Download: ML19270G401 (4)

Text

. s TOLEDO

%o EDISON Docket No. 50-346 LOWELL E. ROE

%ce Pres 4 ens License No. NPF-3 [],'[,"g.L*',,~

Serial No. 511 May 26, 1979 Director of Nuclear Reactor Regulation Attention: Mr. Robert N. Reid, Chief Operating Reactors Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Reid:

This letter transmits information for the Davis-Besse Nuclear Power Station Unit 1 (DB-1) requested in our meeting with NRC staff members on May 8,1979.

Attachments A, B, and C provide the post modification test plans for auxiliary feedvater pump dynamic brake, interim anticapatory reactor trip system and auxiliary feedwater flow indicators respectively.

Very truly yours,.

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Of 94 fI l4,pQfW fl ? L LER:TJM cc:

J. Zwetzig Operating Reactors Branch No. 4 Division of Operating Reactors U.S. Nuclear Regulatory Commission j Washington, D. C. 20555 , 790C06cago Aocg ; $ THE TCLEDO ECISON CCMPANY ECISCN PLAZA 3CO MACISCN AVENUE ll l TCLECO, CH:0 43552

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3 x Docket No. 50-346 License No. NPF-3 Serial No. 511 May 26, 1979 . ATTACIMENT A Installation of Dynamic Braking of the Auxiliary Feedwater Pump Turbine Controls The functional testing of the dynamic braking of the auxiliary feedwater pump turbine controls is to be incorporated as a tempora.y modification to ST 5071.01, Auxiliary Feedwater System Monthly Test and will be run in conjunct Aon with the functional test of the auxiliary f eedwater flow indicators. The test will be con-ducted during Mode 3 with the steam generator partially drained. Auxilinry feed-water will be pumped from the condensate storage tanks through the auxiliary feeA-water nozzle of the OTSG by way of its respective aux.liary feedwater pump (AFP) . The auxiliary feedwater pump turbine (AFPT) will be supplied from main steam. The steam generator will be drained to below the AFPT level setpoint enabling the AFP to run in the auto essential mode and fill the steam generator to a level of 96 inches on the startup range indication. The steam generator drains will be opened with the OTSG steaming to the condenser to provide continuous flow. This will allow the system to control the amount of feedwater entering the OTSG by vary-ing the AFPT speed using the speed changer and permit acquisition of systen response characteristics. Additional testing with AFPT shutdown will be conducted to deter-mine the actions of the AFFT speed changer. An oscilloscope and a pulse generator will be used to drive the speed changer between the high and low stops. The length of the pulses will be varied to allow observat on of the speed changer response

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throughout a range of performance. 2274 354 9 O

r I i I r' , - Decket No. 50-346 License No, NPF-3 . Serial No. 511 May 26, 1979 .. -- - . - - - - . - - - -- - - - ---- -- - - - - - - - - - ATTAC1 BENT B Installation of Anticipatory Reactor Trip System The integrated testing of the installed control grade Anticipatory Reactor Trip

 . System (ARTS) will be completed under a tenporary procedure modification to ST 5030.02, Reactor Protection System (RPS) Monthly Functional Test.                             The test will be conducted in Mode 5, and will verify the tripping of the Control Rod Drive breakers frca simulated inputs of loss of feedwater flow and turbine trip.

The procedure will check the entire string response by insertion of test signals. A reverse pressure signal will be applied to the feedwater/ steam generator dif-ferential pressure transducer to verify proper response to a loss of feedwater. Proper response to a turbine trip will be verified by actuating the turbine

      " Master Trip Solenoid" by use of the control roem " Turbine Trip" switch. The procedure will also certify the test features of the Anticipatory Reactor Trip System and confirm all alarm functions. A check will be made to ensure that the installation has not affected the operation of the Steam and Feedwater Rupture Control System (SFRCS) in the area where an interface exists due to this modifica-tion, specifically the steam generator /feedwater differential pressure trip opera-tion.

I Additionally, ST 5030.12, Channel Functional Test of Reactor Trip Module Logic and Control Rod Drive Breakers, and ST 5030.13, Functional Test of the Manual Reactor Trip, will be performed to ensure that there was no degradation of the RPS due to the installation of the additional reactor trips. 2274 .555

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Docket NO, 50-346 License No, NPF-3 . Serial No, 511 ~ May 26, 1979. ATTACDfENT C Installation of Auxiliary Feedwater Flow Indication The functional testing of d:he installed auxiliary feedwater. flow indication is to be incorporated as a temporary procedure modification to ST 5071.01, Auxiliary Feed-water System Monthly Test and conducted in conjunction with the functional testing of the dynamic braking modification of auxiliary feedwater pump turbine controls. AFP operation will be initiated to verify indication of auxiliary f eedwater flow with an increase in OTSG level and allow a check between FI-4521 (4522) on panel C-5709 with local FI-4521A (4522A). A comparison of data taken on AFP discharge pressure, AFPT speed, and the pump characteristic curves will be conducted to verify results. e e e e e 6 2274 56 W h 9 9 e 4 e}}