ML20027D266

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Informs of Review of Case Study of Abnormal Transient Operating Guidelines as Applied to Apr 1981 Overfill Event. Several B&W Plant Licensees Committed to or Considering Feedwater Sys Mod Which May Resolve Overfill Concern
ML20027D266
Person / Time
Site: Arkansas Nuclear 
Issue date: 10/07/1982
From: Harold Denton
Office of Nuclear Reactor Regulation
To: Michelson C
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML20027A873 List:
References
REF-GTECI-A-47, REF-GTECI-SY, TASK-1.D.1, TASK-A-47, TASK-OR, TASK-TM NUDOCS 8211030575
Download: ML20027D266 (1)


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MEORANDLfi FOR:

Carlyle Michelson, Birector

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Office for Anal is and Evaluation i

of Operationa Data i

Harold R. Denton, Director

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FROM:

l Office of Nuclear Reactor Regulation i

SUBJECT:

REVIEW 0F THE CASE STUDY OF THE ABNORMAL TR/ANSIENT OPERATING GUIDELINES (ATDG) AS APPLIED TO THiE APRIL 1981 OVERFILL EVENT AT ARXANSAS NUCLEAR ONE, LNI71 l

We have reviewed your August 30, 1982 case study on the above subject. We i

note that several of t,ur coments (Memorandum frorn D. G. Ejsenhut to C. Michelson, 7/30/82) on the draft of this report have been incorporated or acknowledged.

The two specific recommendations contained in the case study relate to i

1) focusing attention in the USI A-47 (Safety Implicstions off Control Systems) on equipment modifications to preclude overfill as u credible event and 2) considering the time available for operator actilons as part of the human factors control room reviews.

Our two on-going : program:s, USI A-47 and the Control Room Design Review (THI Action Plan ' Item I.D.1) vill indeed focus on these two areas.

In addition, several BW plant licensees have ecnmitted to or are considering feedwater system. modifications which r-ay resolve the OTSG over-fill concern. The status of BW plant overfill protection, v.s given in our cornents on the April 9,1982 draft of the case study, inidicates that actions by the licensees are under way which may resolve to c11tigata the overfill concern even before the implementation of any re quirements steming from USI A-47.

We will keep you infomed of our progress on USI A-47, the Corntml Room i

Design. Reviews, and any plant specific sodifications relating; to overfill protection.

a crital@ed BI E 6,Cse,

throld R. Denton, Director Q{fice of Nuclear Reactor Re;gulation R ll O30'f f

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