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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 , | |||
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 | Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 | ||
==Dear Mr. Schwencer:== | ==Dear Mr. Schwencer:== | ||
| Line 31: | Line 26: | ||
In the Matter of the Application of ) Docket No. 50-327 Tennessee Valley Authority ) | In the Matter of the Application of ) Docket No. 50-327 Tennessee Valley Authority ) | ||
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. | 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 | Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, ager Nuclear Regulat on and Safety Enclosure 3 o>l s | ||
L. M. Mills, ager Nuclear Regulat on and Safety Enclosure 3 o>l s | |||
/// 1 800sseo / n Eaual Oc::ortunity Errpioyer Q | /// 1 800sseo / n Eaual Oc::ortunity Errpioyer Q | ||
6 | 6 | ||
,y . | ,y . | ||
ENCLOSURE | ENCLOSURE | ||
, SEQUOYAH NUCLEAR PLANT UNIT 1 ACRS QUESTION ON SPECIAL TEST 7 4 | , 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 | |||
Question | |||
What systems remain operable during Special Test 7 - Simulated Loss of All | |||
. AC Power? | . AC Power? | ||
===Response=== | ===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. | 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. | : 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 | : 2. RCP seal injection l' low. from the Chemical and Volume Control System (CVCS). Normal charging is isolated. | ||
(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. | : 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 | : 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 | : 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. | ||
of all AC power condition. | |||
1 | 1 | ||
: l. S. All auxiliary building ventilation which would supply areas where beat | : l. S. 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 | ; 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). | ||
pcwer condition will have their ventilation shut off during the test (i.e., Turbine Driven Auxiliary Feedpump room). | |||
i | i | ||
. J | . J E | ||
l 1 | |||
1 | |||
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Revision as of 05:38, 31 January 2020
| ML19344E033 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| 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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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 ) Docket No. 50-327 Tennessee Valley Authority )
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
/// 1 800sseo / n Eaual Oc::ortunity Errpioyer Q
6
,y .
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.
1
- l. S. 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).
i
. J E
l 1
v . - ...sr. + y . - , e r .w-