ML19344E033

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Forwards Info Requested by ACRS Re Operable Sys During Special Test 7,simulated Loss of Ac Power.Sys Would Not Be Operable in Case of Loss of All Ac Power Condition
ML19344E033
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 08/22/1980
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 8008260538
Download: ML19344E033 (2)


Text

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g' TENNESSEE VALLEY AUTHORITY CH ATTANCOGA. TENNESSEE 37401 1800 Chestnut Street Tower II August 22, 1980 Director of Nuclear Reactor Regulation Attention:

Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Schwencer:

In the Matter of the Application of

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Docket No. 50-327 Tennessee Valley Authority

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Enclosed is the information requested by the ACRS with respect to the systems which remain operable during Special Test 7, Si=ulated Loss of All AC Power.

Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, ager Nuclear Regulat on and Safety Enclosure 3 o>l s

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ENCLOSURE SEQUOYAH NUCLEAR PLANT UNIT 1 ACRS QUESTION ON SPECIAL TEST 7 4

Question What systems remain operable during Special Test 7 - Simulated Loss of All AC Power?

Response

The following systems wh' ch are operable during Special Test 7 would not be operable in a loss of all AC power condition. This list is not all inclusive but does consider those major systems which could effect plant conditions.

1.

Component Cooling System supplying cooling water to the Reactor Coolant Pump (RCP) thermal barriers and normal auxiliary building loads.

2.

RCP seal injection l' low. from the Chemical and Volume Control System (CVCS). Normal charging is isolated.

3.

All containment ventilation systems including upper and lower con-tainment ecolers and control rod drive mechanism coolers along with 1

their Emergency Raw Cooling Water (ERCW) supply.

4.

Control Air System supply to all plant equipment except the Turbine Driven Auxiliary Feedwater Pump Slow control valves (which regulates flow to each steam generator) and the Secam Cencrator Power Operated Relief Valves. All other valves will be posiciancd to simulate a loss of all AC power condition.

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All auxiliary building ventilation which would supply areas where beat loads would not exist under loss of all AC power conditions (i.e., CVCS pump rooms). Areas which would carry a heac load in a loss of all AC pcwer condition will have their ventilation shut off during the test (i.e., Turbine Driven Auxiliary Feedpump room).

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