ML20044E371

Provides Summary of 930406 Telcon Conducted Among Representatives of Nrc,Bnl & ABB-CE.Summary of Topics Discussed Listed

ML20044E371
Person / Time
Site:	05200002
Issue date:	05/13/1993
From:	Mike Franovich Office of Nuclear Reactor Regulation
To:	Brinkman C ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
References
NUDOCS 9305240248
Download: ML20044E371 (7)

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WASHINGTON, D C. 20556-0001 gw j Ma) 13, 1993 Docket No.52-002 Mr. Charles B. Brinkman, Acting Director Nuclear Systems Licensing ABB-Combustion Engineering 1000 Prospect Hill Road Windsor, Connecticut 06095-0500

SUBJECT:

APRIL 6, 1993, CONFERENCE CALL ON THE HUMAN FACTORS PROGRAM PLAN AND OPERATING EXPERIENCE REVIEW OPEN ISSUES FOR THE ABB-COMBUSTION ENGINEERING (ABB-CE) SYSTEM 80+ DESIGN The purpose of this letter is to provide you with a summary of the April 6, 1993, telephonic conference conducted among representatives of the U.S.

Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL), and ABB-CE. The Human Factors Program Plan (HFPP) and Operating Experience Review (0ER) related to the human factors review of the Systen 90+ advanced control room design were the topics of discussion.

By letter dated April 16, 1993, the NRC transmitted to you the BNL reports evaluating the HFPP (Reference 1) and the OER (Reference 2).

The objective of the conference call was to develop a path to resolution of the HFPP and OER open issues identified in the BNL reports.

Enclosure I lists the partici-pants in the conference call. A summary of each of the topics discussed is provided below and, where appropriate, agreements between the NRC and ABB-CE are indicated.

Human Factors Proaram Plan In Reference 1, the following unresolved issues related to ABB-CE's HFPP (referenced herein as the Plan) (Reference 3) were identified:

(1) Several issues remain to be clarified concerning the scope, most notably the issue of procedure development:

(a) There are scope differences between the Plan and the design process requirements in Appendix A to the Plan.

(b) A formal procedure element is excluded from the Plan.

Resolution: With regard to (1)(a) above, ABB-CE agreed to resolve the incon-sistencies between the Plan and Appendix A.

The inconsistencies were as follows:

(1) the Appendix suggests that the technical support center (TSC) is subject to human factors engineering (HFE) guidance, however, the scope statement of the main document appears to indicate that the TSC will be subject to the full program; and (2) the operations support center (OSC) and emergency operations facility (EOF) are not addressed in the appendix and

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i Mr. Charles B. Brinkman May 13, 1993 r

should receive the same treatment as the TSC. The NRC agreed that this issue l

can be resolved by an acceptable resolution of the inconsistencies between the i

Plan and Appendix A.

With respect to (1)(b) above, ABB-CE reiterated their position that the HFPP 4

meets the intent of the NRC's HFE program review model. The ABB-CE approach is to validate the man-machine interface (MMI) without formal procedures (i.e., technical content complete without attention to format issues, a I

writer's guide, or verification and validation of the procedures). ABB-CE also indicated that a procedure development program including all of these elements will be conducted by a combined license applicant.

It was agreed i

that this is a programmatic issue which would not be resolved by providing more details describing the approach. The NRC technical staff a;,d management discussed this issue with ABB-CE during the senior management meeting held on April 22, 1993. The staff and ABB-CE are developing a path to resolution of this issue.

(2)

It was expected that the description of the document review process for i

HFE program products would be expanded in the current version of the i

Plan, but no such discussion was found.

l Resolution: ABB-CE agreed to describe how the interdisciplinary review of HFE l

and human system interface (HSI) documents is conducted, including how comments are addressed and how this is reported. -The NRC agreed that this issue can be resolved by an acceptable description of the formal document

-l review process.

(3) ABB-CE's Plan does not include a plant and emergency operating procedure development element.

l Resolution: The NRC and ABB-CE agreed that resolution of item (1)(b) above would also resolve this issue.

y Operatina Experience Review In Reference 2, the following unresolved issues related to ABB-CE's Operating Experience Review for System 80+ MMI design (referenced herein as the OER, NPX80-IC-RR790-01, docketed December 18, 1992) were identified:

(1) A few areas were identified where the scope of the OER was too limited (i.e., remote shutdown panels (RSPs), local control stations (LCSs), and review of System 80 experience).

Resolution: ABB-CE agreed to review some of the more recent documents on RSPs and LCSs (Enclosure 2) for the purpose of identifying and including in ABB-CE's HFE tracking system any issues not previously identified in the OER.

The NRC agreed that this issue can be resolved by an acceptable review of the subject documents. The NRC and ABB-CE agreed that the issue of scope regard-ing Sys;em 80 experience would be resolved under Issue 6 (discussed below).

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Mr. Charles B. Brinkman May 13, 1993 (2) The analysis results report was incomplete.

Resolution: The NRC and ABB-CE agreed that resolution of issue 1 above in j

this section would resolve this issue.

I (3) The OER analysis shall be reviewed by the HSI design team and shall be documented in an evaluation report.

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Resolution: The NRC and ABB-CE agreed that resolution of issue 2 above (under l

the HFPP section) regarding a description of how documents are reviewed by the i

HFE design team would resolve this issue.

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(4) The operating experience issues shall identify (a) human performance i

issues, problems and sources of human error, and (b) design elements l

which support and enhance human performance.

s Resolution: ABB-CE agreed to revise Appendix A, " Operating Experience Issues Identified for Review by the NRC," to its OER submittal and to submit the i

revision to the NRC staff for review and approval.

The proposed revision would include (a) a statement of the operating experience review issue from the NRC's HFE Program Review Model and (b) discussion of how each issue has been addressed, including additional details for certain issues (e.g., how GI-57 was incorporated into the System 80+ design).

i (5) ABB-CE is expected to respond to the " System 80 Operating Experience Issues Based upon Interviews with System 80 Operators" (BNL report dated March 29, 1993).

Resolution: ABB-CE agreed to develop an initial response to the above referenced operating experience issues by indicating those issues that are addressed in the System 80+ design versus those that should be tracked and resolved in the HFE Tracking System. The NRC agreed that this OER issue is resolved by the above initial response to the operating experience issues.

ABB-CE agreed to provide a final response to the operating experience issues relative to the above referenced document. The final response will indicate i

the design feature or document that resolves the issues for the System 80+

l design. This will be done after the staff completes the design features i

review and the evaluation of associated HSI design issues (scheduled April 19 thru 21, 1993).

(6) The list of references for the OER literature review was lacking in documents from the CE System 80 operating experience (i.e., Palo Verde licensee event reports [LERs]).

Resolution: ABB-CE acreed to review all of the Palo Verde LERs associated with the following cause codes:

(a) intrinsic human error, (b) task descrip-tion inadequacy, and (c) inadequate man-machine interface. ABB-CE agreed to incorporate any issues not currently addressed by System 80+ design resolu-tions into its HFE tracking system for resolution. The NRC staff also requests that ABB-CE categorize the LERs into the following categories:

3 (a) System 80+ design resolution provided, (b) incorporated into the ABB-CE l

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Mr. Charles B. Brinkman May 13, 1993 HFE tracking system, or (c) not applicable. No additional information other than the categorization will be required for categories (a) and (c).

The NRC i

agreed that this issue can be resolved by performing the above review of the Palo Verde LERs.

3 (7) Verify proper implementation of the ABB-CE HFE tracking system.

Resolution: ABB-CE agreed to provide to the NRC a copy of the computer files l

for the HFE tracking system, when available, and to incorporate any issues not i

previously identified into the HFE tracking system. Alternately, the NRC agreed that this issue can be resolved by an acceptable onsite (at the ABB-CE 2

facilities in Windsor, Connecticut) implementation audit of the ABB-CE HFE a

tracking system.

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References i

l (1) Draft Technical Evaluation Report entitled, " Review of the ABB-CE System 80+ Human Factors Program Plan (BNL Technical Report E2090-T2-1-3/93),"

dated March 22, 1993 (2)

Draft Technical Evaluation Report entitled, " Review of the ABB-CE System i

80+ Operating Experience Review (BNL Technical Report E2090-T2-5-3/93),"

l dated March 22, 1993

.l (3) HFPP for the System 80+ Standard Plant Design, NPX80-IC-DP790-01, docketed December 18, 1992.

i (4) Operating Experience Review for System 80+ MMI Design, NPX80-IC-RR790-01, l

docketed December 18, 1992.

i Sincerely, (Original signed by)

Michael X. Franovich, Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

Enclosures:

As stated 1

cc w/ enclosures:

See next page DISTRIBUTION:

Docket File PDST R/F DCrutchfield WRussell PDR PShea REckenrode, 10024 RBorchardt TEssig TWambach BBoger, 10H5 MXFranovich ACRS (11) w/o encl.

GWest, 10D2 GGalletti,10D24 SMagruder JMoore,15B18 GGrant, 17G21 GSuh (2), 12E4 0FC: LA:PDST:ADAR PM:PDSI: IR Sd D T:ADAR NAME:PShea,,,,(

MX F r an' '.' h:tz TEssig DATE:05/g /93V 05/g'/93 05/g /93 0FFICIAL RECORD COPY: HFPP.MXF

ABB-Combustion Engineering, Inc.

Docket No.52-002 f

cc: Mr. C. B. Brinkman, Acting Director i

Nuclear Systems Licensing ABB-Combustion Engineering, Inc.

j 1000 Prospect Hill Road Windsor, Connecticut 06095-0500 5

Mr. C. B. Brinkman, Manager Washington Nuclear Operations ABB-Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Stan Ritterbusch Nuclear Licensing ABB-Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0530 Mr. Sterling Franks U. S. Department of Energy NE-42 Washington, D.C.

205B5 Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.

Washington, D.C.

20503 Mr. Raymond Ng 1776 Eye Street, N.W.

Suite 300 Washington, D.C.

20006 Joseph R. Egan, Esquire Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.

Washington, D.C.

20037-1128 l

Mr. Regis A. Matzie, Vice President Nuclear Systems Development ABB-Combustion Engineering, Inc.

1000 Prospect Hill Road l

Post Office Box 500 Windsor, Connecticut 06095-0500 i

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Telephonic Conference Call April 6, 1993 Conference Call Participants t

Garmon West, Jr.

NRC i

Greg Galletti NRC l

John O'Hara BNL i

Jim Higgins BNL Daryl Harmon ABB-CE i

Bob Fuld ABB-CE Bob Rescorl ABB-CE Bob Bryan ABB-CE

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i Bibliography of Recent Documents on Local Control Stations NUREG/CR-3696, " Potential Human Factors Deficiencies in the Design of Local Control Stations and Operator Interfaces in Nuclear Power Plants," C. Heartly et al., Pacific Northwest Laboratory, Richland, WA, April 1984.

NUREG/CR-5572, "An Evaluation of the Effects of Local Control Station Design Configurations on Human Performance and Nuclear Power Plant Risk," Upton, New York: Brookhaven National Laboratory, September 1990.

Ruger, C. J.; Brown, W. S.; and Higgins, J. C. (1991).

" Human Factors Defi-ciencies at Local Control Stations," (BNL A-3972-4-91).

Upton, New York:

Brookhaven National Laboratory.

Task 2.3: Site Data Collection, BNL Report A-3972-23 (9192), September 30, 1992.

i INPO, " System and Component Labelling," INP0 88-009, Good Practice OP-208, September 1988.

Seminara, J.

L., " Effective Plant Labeling and Coding," EPRI NP-6209, Electric Power Research Institute, December 1988.

Persinko, D. and Ramey-Smith, A., "An Investigation of the Contributors to Wrong Unit or Wrong Train Events," NUREG-1192, U.S. Nuclear Regulatory Commission, April 1986.

NRC Information Notice No. 87-25:

"Potentially Significant Problems Resulting From Human Error Involving Wrong Unit, Wrong Train, or Wrong Component l

Events," U.S. Nuclear Regulatory Commission, June 11, 1987.

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