ML20009F276

Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for Ak Nuclear One Nuclear Power Plant

ML20009F276
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/31/1981
From:	Wade W EG&G, INC.
To:
Shared Package
ML20009F270	List: ML20009F276
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM SRO-237, NUDOCS 8107300234
Download: ML20009F276 (2)

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day 1981 San Ramon Operatione TECHNICAL EVALUATION OF THE RESPONSE TO POSITION No.5 O F ITEM H. E. 4.2 OF NUREG-0737 CONTAINMENT ISOLATION SETPOINT FOR THE ARKANSAS N.UCLEAR ONE NUCLEAR POWER PL' ANT UNITS 1 AND 2 l

(OCCKET Nos. 50-313 and 50-3SS)

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y W. O. Wade Accroved for Puolica ica 4 l b ~b

w. A. Auvalcaca Depart:1ent Manager This dec:a:1ent is UNC U SSIFIED Derivative CT assifier:

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- alcacias :.r oraceric.r.

Depar.:: rent Manager l

l work P erfer-ned *cr Lawrence t.ivermore National La=crat=rf un ser U.S. 0 ecar ment of E.me 2y Centrse.t ?,c. Of.ACOS-76 NVC 1983.

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INTR 000CTION AND 3ACKGROUND As. a consequence of tne incident at TMI-2, implementation of a j

numoer of new requirements has been recomended for operating reactors.

1 These new requirements are described in NUREe0660, *NRC Action F1an Devel-oped as a Resul: of tne TMI-2 Accident,* May 1980, and NUREG-0737, "Clari-fication of TML Action Plan Requirements," Novem er 1980.

Tae NRC staff nas also r equested licensees to suomit infor nation sufficient to permit an independent evaluation of tnetr response to :nese new requirements.

Tnis report provides an evaluation of the response to Action Plan Item II.E.4.2, position 5, by tne designated li ansee.

l DESIGN 3 ASIS OR REVIEW CRITERIA Position 5 requires nat tne containment pressure se: point :na:

l initiates containment isolation for non-essential system containment vessel penetrations be at, or reduced to, "...:na minimum corapatible wi:n normal operating condition,s."

i TECHNICAL EVALUATION Response evaluation is based upon :ne values provided for :ne following parameters:

(1)

The maximum coserved or exoec ed _ containment pressu. e during normal operation.

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(2)

The loop error and' coserved dri f in :ne cressure sensing instrumentatica providing :ne isolation signal (see note).

l (3)

The containment isolation pressure sa: point.

NOTE: Ine clarification document (NUREG-0737) provided only tne expectec margin for iristrument error and did not specify acceptabla values for instrument drift or atmospneric cnanges contributing to :ne total sensir.g loop e'eror.

Additional staff guidance establisied a l

limit-of 3.0 psi for an isolation setpoint margin over the normal containment pressure to account for :stal icop error.

In addition, for suba:mospneric contain-ments, a 3.0 psi sa: point margin over L:mospneric pressure is also considered acceptacle.

3 In considera: ton of :nese values, :ne isolation pressure sacacin:-

is to be as low as practical witnou increasing :ne procacili y of inaeve. -

tant actiyattarr of :ne isolatten signal.

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l CCNCLUSIONS Tne let:er of Maren 31, 1981, suomittec by Arcansas Power and Lign: Comoany, provided sufficient information to conclude :na: :ne con-tainment isolation pressure set;oin for Artansas Nuclear One, units 1 and 2, meets :na NURE3-C660/0737 requirements and is wi:nin :ne additional limiting guidelines ;rovided by :ne NRC staff.

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