ML19262K570

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Forwards Inel Repts EGG-EA-6473 & EGG-EA-6468 Re Unresolved Safety Issue A-47, Safety Implications of Control Sys. Comments on Technical Accuracy Requested by 840213
ML19262K570
Person / Time
Issue date: 01/12/1984
From: Szukiewicz A
Office of Nuclear Reactor Regulation
To: Stribling T
CAROLINA POWER & LIGHT CO.
Shared Package
ML19262K571 List:
References
REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR NUDOCS 8401190193
Download: ML19262K570 (2)


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Dear M.. $tribling:

Enclosed for your information and comment are two preliminary reports f ~r

!6aho 8;ational Engineering Laboratory (INEL).

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  • Report Conteming the Effects of Control Systevr' reilures cr m a-Generator 0=<7p n 2.*4 kes: tor Vess?1 Costant Systee Overco: lins !- t,

H a Typical net t apwse 3-Loop Flant

  • EGG-EA-6473, da t 'd Derort: r 1983.

(2) %stf=pc.a 3-ttep Other TreWenix Fath,re Pbce.ind Ef fecu t-

,, r and Re.lecto:t System JustiNcation P3 port? EGG-E3.-6462, dated % + +

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.s Tkse preiir.inary reports identify tie statws of the INEt. review of a vnr "

idestinghouse 3-loop plant design for resolution of USI ba7

  • Safety Isplie.ations of Centrol Systens." Thereporta(1/identifytheprc1%nar, criteria used to select cot.teD1 systeer; Whese 'tf oure could leed to potentially undesirabie treesfects or operating coditions, (2) provide the 4tlure se6e >nd effect analysis of the systems utfilzed fr. the 6esign arse (3) idertify systems erwl failmes scenarios that have been selected for edditfowl revics stilfritrg a plant siem1 ster to better assess the temsegwntes of their failure under segN$ntial or Cc2bir.ed f ailure redes.

3 The reports also identify systems that have been excluded from further retiew,

cad the h sis for th?fr rejection.

In order to accomplish our objectives and etnistre our i@act on the utilities to prwide ieforeation that was needed to conduct cur revin, th-Information sveilatele in-houw sad at our contractor facilitto was T

utilized. Engineering.hdgment based upon similarities in the design was

[a ewd tc supplement tk inforaaffon that was teeded, but not readily avaltab'e from the P,C lf t6es. Teer review and comment an the technical d

i T4 Mcuracy an4 the se of the control systems reviewed shd identified in I

T:TQese preliminary reports could significantly enhence our understanding of hhese systees and our conflGence in assuring a complete review of the dw 1

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- Mtant systers used during plant operation.

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