ML19344B418

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Submits Info Re Differences Between Farley Nuclear Plant Test Procedures & Sequoyah Test Procedures for Natural Circulation W/Loss of Power Per 800714 Request
ML19344B418
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 10/13/1980
From: Clayton F
ALABAMA POWER CO.
To: Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 8010200590
Download: ML19344B418 (2)


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Director,' Nuclear lReactorRegulationi U. S. ; Nuclear Regulatory Commission-

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Attention:' Mr.-A.1Schwencer 1

q JOSEPH'M.- FARLEY NUCLEAR' PLANT - UNIT ~2 -

~SPECIAL LOW POWER TESTS Gentlemen:

Mr. 0.. G. Eisenhuhs' letter of July-14 1980, requested'that technical

- justification be provided for--any exceptions to the Sequoyah test program.

Information regarding the differences between Farley Nuclear Plant test i

procedures and Sequoyah test procedures for natural circulation with loss of power 1s)provided below'as requested in the above referenced letter and by members of your staff on October 9 1980.

The purpose of Sequoyah Test 2. Loss of Offsit'e Power,Lis' to demonstrate

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that decay heat can be removed via the steam' generators by maintaining steam generator levels with thel auxiliary feedwater system under simulated loss of offsite power conditions. 'The purpose of-Test 7, Loss of ~

Onsite/Offsite Power, is the'same as Test-2 except'that.a loss of all AC power will be simulated and steam generator levels will be maintained,.

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with the turbine driven auxiliary feedwater pump.

Perfoming these tests 4

as3roposed by APC0 would result:in improved safety and enhanced operator-a training. The;following is.a listing ofithe advantages of perfoming these 1.ests as-proposed.:

1. :If aaxiliary feedwater valves we're'1 eft open and'auidliary feedwater was' initiated as in:a loss of power event, the injection of'feedwater in. the'. steam generators would cause a rapid drop;in RCS~ temperature and ho--

. pressure. "This is an undesirable condition with a critical reactor

'and would not be of.any benefit in. accomplishing the goal Lof the test.

The auxiliary.feedwater control-valves will be~ shut just prior to s

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stopping (all. reactor coolant pumps and the running main feedwater pump.

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.Then the ' auxiliary feedwater: control: valves will-be throttled to main-.

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itainLsteam generator levels.-

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N 3 NSigni ficantl operatoriattentionTwill E necessary to maintain the w f

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W6 e operator? attention to:diese1) operation;and ailessEcontro11abley 4 q

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.4.1Farley:PreoperationaliTes*.548-6-002, P'lant Response?toKIntegrated., -^

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2 i ~ j$afeguards With Blacliout,> demonstrates"the ability of the-diesel to_

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a l bus undervoltage:and' safety; injection.o Repeating these tests;in the:

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inatural circulation procedurelis:redundantLand 41s not,necessary to -

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.5'. iFarleyINui: lear-Plant Test ProceduretS00-7-538, Loss:of 0ffsite. Power,

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e (demonstrates that.thelemergency: diesels willistart.and the emergency s ms Ebuses willtsupply power to safety?related equipment toLbring the plant ~

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to_~and maintain hot standby conditions subsequent to-loss of_ norma 11 station. power;at' equa1 to or greaterJthan; ten' percent generator; power.

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It is not{necessary.to. repeat:thisitest as'a: natural circulttion '

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PreoperationallTest5406-002alsoiemon'stratestheabilityofthe' i,

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auxiliary,feedwater? system toJperfors.in the as-designed manner.

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' Repeating-this test. insthe~natura1Jcirc11ation/ procedure would,

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objective?of the natural-circulation ~ test.

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i If'you have any;further questions, please advise.=

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