ML19270H904

Discusses Review of TVA Sequoyah ATWS Procedure & Reactor Sys Branch 791205 Comments.Concurs W/Reactor Sys Branch Comments & Supports Position That Separate Emergency Procedure Should Be Developed for ATWS

ML19270H904
Person / Time
Site:	Sequoyah
Issue date:	12/18/1979
From:	Buzy J Office of Nuclear Reactor Regulation
To:	Stahle C Office of Nuclear Reactor Regulation
Shared Package
ML18025B195	List: ML18025B194 ML19211C487 ML19211C498 ML19211C499 ML19211C500 ML19211C505 ML19211C524 ML19211C531 ML19211C534 ML19211C536 ML19211C552 ML19211C553 ML19211C555 ML19211C556 ML19211C802 ML19270H904 ML19290F424 ML19352A395 ML19352A415 ML19352A431 ML19352A502 ML19352A510 ML19352A511 ML19352A568 ML19352A577 ML19352A584 ML19352A586 ML19352A605 ML19352A675 ML19352A698 ML19352A716
References
FOIA-80-587, REF-GTECI-A-09, REF-GTECI-SY, TASK-A-09, TASK-A-9, TASK-OR NUDOCS 8001080039
Download: ML19270H904 (1)

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SUBJECT:

TVA ATWS PPOCEDURE 10R St.QU0YA,1' I

i Uc have reviewed the TVA Sequoyah ATWS procedure submitted on Octot.ec 17, o/9 i

and the conanents of the Reactors Systams Branch of Decen,ber 5,1979.

The prc-cedure submitted by TVA addresses ATWS in their Abnormal Operating Instruction A01-1, Reactor Trip Procedure.

301-1 contains symptoms and auto:r.atic action which occur following a norrul trip of the reactor.

The operator utilizes these conditiens to diagnose the vcnt and thereby classify the ca.org4ncy.

The sp stens and automatic 'rti;n for ATWS do not folled the non::al trip sequence and therefore conflict. ith l

the procedure in its pr stnt fonn. Although A0!-l requires the operaiois to be alert for AlWS, it d;cs not provide sufficient insight on rcactor ans pl.nt icsponse until the event is tei.:inolod. !'anual a. Lions outside the control icom may be rcquired to toi.ninate AlWS; therefore, the tin.e frame or period, the plant response and concurrent operator acticn iiuring this period, should be contained in the piocedure.

Ne believe that including ATWS in the present fcrm is contrary to Regulatory r.uide.. . "Quali ty Assus once Program Requirnments (D;'erational),"..hich includes a specific proceduce for anticipated tr r.;i nts. Also, ANS 3.2, ANSI f118.7-1976, " Quality Assurance for Opc-raticnal i'hr.c of !:uclear Po.ier Plants " addresses energency procedures in Section 5.3.9 and recomends separate procedures for reactor transients and e> cur; ons.

':e corcur tith the c" - nts of the Reactor Syst +, 'rench zd < 'spe<;rt the resi-tion that a separate ci.:ergency proccdure should be (*.. eloped for AfWS.

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