ML20046C743
| ML20046C743 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 07/08/1993 |
| From: | Kenyon T Office of Nuclear Reactor Regulation |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9308120036 | |
| Download: ML20046C743 (5) | |
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July 8,1993 Docket No.52-003 Mr. Nicholas J. Liparulo Nuclear Safety and Regulatory Activities Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230
Dear Mr. Liparulo:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE AP600 As a result of its review of the June 1992 application for design certifica-tion of the AP600, the staff has determined that it needs additional informa-tion in order to complete its review.
The additional information is needed in the area of human factors (Q620.75-Q620.90).* Enclosed are the staff's questions.
Please respond to this request within 90 days of the date of receipt of this letter.
You have requested that portions of the information submitted in the June 1992 application for design certification be exempt from mandatory public disclo-sure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submit-ted information is being withheld from public disclosure pending the staff's final detern ination. The staff concludes that this request for additional information does not contain those portions of the information for which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westing-house the opportunity to verify the staff's conclusions.
If, after that time, you do not regaest that all or portions of the information in the enclosures be withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the NRC's Public Document Room.
This request for additional information affects nine or fewer respondents, and therefore is not subject to review by the Office of Management and Budget under Public Law 96-511.
- The numbers in parentheses designate the tracking numbers assigned to the questions.
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Mr. Nicholas-J. Liparulo
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July 8, 1993-If you have any questions regarding this matter, you can contact me at (301).
504-1120.
Sincerely, (Original signed by)
Thomas J. Kenyon, Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
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LA:PDST:ADAR PM:PDJTgDAR PM:PDST:ADAR (A)SC:PDST:ADAR NAME:
PShea g y g TKe'pYonI~sg RHashlirg-TEssig/pb 07/h'/93 07/ g'/93 07/8/93 07/ % /93 DATE:
0FFICIAL RECORD COPY: HFRAI.TK
Mr. Nicholas J. Liparulo Westinghouse Electric Corporation Docket No.52-003 AP600 cc:
Mr. B. A.-McIntyre Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. John C. Butler Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. M. D. Beaumont Nuclear and Advanced Technology Division Westinghouse Electric Corporation One Montrose Metro 11921 Rockville Pike Suite 350 Rockville, Maryland 20852 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, D.C.
20585 Mr. S. M. Modro EG&G Idaho Inc.
Post Office Box 1625 Idaho Falls, Idaho 83415 Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.
Room 8002 Washington, D.C.
20503 Mr. Frank A. Ross U.S. Department of Energy, NE-42 Office of LWR Safety and Technology 19901 Germantown Road Germantown, Maryland 20874
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REQUEST FOR ADDITIONAL INFORMATION ON THE WESTINGHOUSE AP600 DESIGN HUMAN FACTORS ENGINEERING 620.75 Describe further the implementation guidance for the use of Task Analysis outputs by the designer and its use to " simplify the verification activities" (Section 18.8).
620.76 Have the guidance documents for display design, controls, etc., been developed yet and are they available for staff review (Section 18.8)?
620.77 The goal of validation is centered on the systematic evaluation of human factors (HF) concerns. While this is an excellent focus for verification and validation (V&V) tests, could the issue-driven validation fail to detect issues that are unexpected and unanticipated (in a manner analogous to the way that interfaces often provide poor information to operators for unplanned and unanticipated events)
(Section 18.8)?
620.78 The issues identified in the V&V plan are all of a general nature as would be expected, given the model-based approach used to facilitate issue identification.
However, are there any HF issues that relate uniquely to a passive plant in general, or to AP600 in particular?
Will any such issues be incorporated into the test program at a future date (Section 18.8)?
620.79 Is there a validation plan that is more detailed than the plan described in the SSAR7 One that addresses scenario design, participant sampling, participant familiarization, data collection, data analysis, etc.
If not, when will such detail be made available?
These methodological considerations are significant factors in the safety evaluation of the V&V plan (Section 18.8).
620.80 Is a specific Human Factors Engineering (HFE) Issue Tracking closure verification to be performed? What process assures that all HFE issues come to an acceptable HF resolution (Section 18.8)?
620.81 What analysis assures the availability of all task analysis-defined controls and displays at the M-MIS (the NUREG-0700-type of availability analysis)? What analyses will be performed to prevent unwanted functionality or extraneous information from getting into the controls and displays of the AP600 (Section 18.8)?
620.82 With respect to V&V scope, what is the status of local stations (other than the remote shutdown room)? Are human actions required at any local panels for the execution of abnormal or emergency procedures or for the performance of critical human actions as defined by the function-based task analyses or probabilistic risk analysis /h" man reliability analysis (PRA/HRA) (Section 18.8)?
620,83 The concept testing will lead to functional requirements to be used in a checklist fashion as part of issue vs.rification testing. What is 3
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. the relationship between these items and HFE guidelines? There seems to be some overlap, at least at the level of description provided in the SSAR; e.g., the results of issue 5 alarm analysis would seem to overlap, to some degree, in t.opic areas with industry work by MPR Associates for EPRI on alarm system guidance (Section 18.8).
620.84 What performance measures will be included in the final validation analysis? Why is situation analysis (SA) not identified, since it is measured in earlier issue analyses and is important to the cognitive approach being used in the design process?
Why is workload not included in any analyses? The V&V issues focus appropriately on task related performance measures and situation awareness. However, another issue frequently associated with advanced control complexes is that of information and cognitive overload. A design can result in adequate task performance and accurate situation awareness, yet accomplish these objectives at the cost of high workload.
Design testing and validation should be capable of identifying this situation so that designers can better support workload management.
(Also consider, for example, that if two design options are being compared and similar performance is observed on task and SA measures, work load differences may serve as the basis for selection.) (Section 18.8) 620.85 What modes of communication will be available between the main control area and personnel in the plant? Will only phones be available (Section 18.9)?
620.86 What factors would cause a display selection to be as long as 2 j
seconds (Section 18.9)?
620.87 Tables 18.9.8-1 through 18.9.8-37 provide high-level operator actions.
Where do these actions come from? What is the relationship of these actions to emergency response guidelines (ERGS) and emergency operating procedures (EOPs) (Section 18.9)?
620.88 What is the role of a combined operating license (COL) holder in the development of the emergency operations facility (E0F) and technical support center (TSC) (Section 18.9)?
620.89 What is the name of the low-pressure reference plant referred to in 18.9.8.1.1 (Section 18.9)?
620.90 Provide more detail concerning plant labeling (e.g. what is the process / method used for plant labeling? Is there a standard /guideli.ie for plant labeling? What conventions will be used for plant labeling?) (Section 18.13).
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