ML20093F319
| ML20093F319 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 10/10/1984 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20093F322 | List: |
| References | |
| SLNRC-84-121, TAC-57369, NUDOCS 8410150053 | |
| Download: ML20093F319 (3) | |
Text
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'A SNUPPS Standardized Nuclear Unit Power Mont System 5 Choke Cherry Road Nicholas A. Petrick v
land 20050 Executive Director
(
October 10, 1984 7
SLNRC 84-121 FILE:
0671.1 SUBJ: Task Analysis for SNUPPS DCRDR Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D.C.
-20555 Docket Nos:
50-482 and 50-483
Dear Mr. Denton:
Transmitted herewith is the procedure that will be used in performing the task analysis and verification for the SNUPPS Detailed Control Room Design Review (DCRDR).
This procedure reflects agreements reached during a September 24, 1984 meeting with the NRC, where the draf t version received a favorable reaction.
The major area of change that
.resulted from the September 24th meeting was an agreement that response time for systems or components will be analyzed as appropriate.
In addition, SNUPPS Staff clarified that the human f actors consultant will be involved in every task analyzed, as either the analysis originator or reviewer. Other minor changes were made to add clarity to the procedure for the procedure users.
The definition of scope for the task analysis is provided herein.
Necessary performance characteristics will be developed in the following way for each instrument and control required to perform the tasks identified in the Emergency Response Guidelines (ERGS).
An Action-Information Requirements Details (AIRD) form will be prepared for each Step, Caution Statement, and Note in Revision 1 of ERGS E-0, E-1, E-2, E-3, ECA-0.0, and all of the Function Restoration Guidelines.
This will result in the analysis of approximately 45 per cent of all steps in the total set of ERGS (335 out of 761). This sampling approach OOD 841C150053 841010 l' '
PDR ADOCK 05000482
\\
PDR I
s.
SLNRC 84-121 Page Two is justified because:
(1) in most cases the observation or control of a particular par ameter is referred to several times, by different ERGS, thus resulting in a 1arge amount of repetition, and (2) the sampling approach will result in consideration of most ( >90%) instru-mentation and control requirements.
To account for the remaining (<10%) instrumentation and control requirements, the following steps will be taken:
Upon completion of the Action-Information Requirements Summary (AIRS) forms (which will integrate the requirements developed on the AIRD forms), the inventory of parameters to be observed and/or controlled will be compared to the inventory of instrumentation and controls developed by Westinghouse in its SRTA (System Review and Task Analysis) of the basic version of the ERGS.
This identified inventory difference will be cross compared at the task level to Revision 1 of the ERGS, utilizing the task interchangeability data supplied in the SRTA.
As a result of this comparison, a supplemental analysis will be performed for (1) each plant parameter not already analyzed, (2) each type of task not already analyzed, and (3) each parameter value not enveloped by values already included in the analysis.
These supplemental analyses will be performed utilizing the AIRD form for the ERGS not previousy analyzed.
The results will then be transferred to the AIRS forms.
A final veri-fication utilizing the control room and/or simulator will be performed as discussed in the attached procedure.
A closing report is scheduled for submittal to the NRC during April 1985'.
Ver truly yours, 1
-C4(C Nicholas A. Petrick DJK/bds/13b25 Attachment cc:
D. F. Schnell UE G. L. Koester KGE J. M. Evans KCPL H. Bundy USNRC/WC W. L. Forney USNRC E. H. Johnson USNRC B. Little USNRC/ CAL J. H. Neisler USNRC/ CAL I
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