ML20065G869

Forwards Response to NRC 900727 Request for Addl Info on Ssar for Advanced Bwr.Response to Questions 620.3,620.7, 620.13,620.16,620.19,620.25 & 620.29 Contain Proprietary Info & Will Be Submitted Under Separate Cover

ML20065G869
Person / Time
Site:	05000605
Issue date:	10/09/1990
From:	Marriott P GENERAL ELECTRIC CO.
To:	Chris Miller NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
129-90, EEN-9058, NUDOCS 9010240040
Download: ML20065G869 (3)

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hiFN No.129 90 Docket No. STN 50-605 EEN 9058 i Document Control Desk ,

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Charles L hiiller, Director >

Standardization and Non Power Reactor Project Directorate o l

Subject:

Submittal of Responses to AdditionalInformation as Requested in NRC Letter from Dino C. Scaletti, Dated July 27,1990 -

Refererce: Submittal of Responses (Proprietary Information) to Additional  ;

Information as Requested in NRC Letter from Dino Scaletti, dated July 27,1990, hiFN No.130-90, dated October 9,1990

Dear hir,

hiiller:

Enclosed are thirty four (34) copies of the first submittal of Chapter 18 responses to the subject -

Request for Additional Information (RAI) on the Standard Safety Analysis Report (SSAR) for the Advanced Boiling Water Reactor (ABWR).

Response to Questions 620.3,620.7,620.13,620.16,620.19,620.25 & 620.29 contain information that is designated as General Electric Company proprietary information and is being submitted under separate cover.

Responses to the majority of the remaining questions will be provided at the end of October 1990.

It is intended that GE will amend the SSAR with these responses in a future amendment.

Sincerely, 1

P. Y tarriott, hinnager Regulatory and Analysis Services  ;

cc: F.A. Ross (DOE)

D.C. Scaletti (NRC)

D.R. Wilkins (GE) l' J.F. Quirk (GE) i p b -

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ABWR p . .a__g p...a QUESTION 620.1 Describe GE's human factors design team, the staff's human factors expertise, and its responsibilities for human factors on the ABWR design.

RESPONSE 620.1  :

The team is responsible for the compliance of the plant design with all regulatory requirements related to lluman Factors Engineering and the inclusion of good human factors engineering practice in all aspects of the plant design. The five members of the team have a total of 99 years of human factors engineering, managerial, quality ar,surance, plant operating and design experience on BWRs.

Descriptions of the individual members of the ABWR human factors team are follows.

Chairman: Twenty seven years of human factors engineering, licensing and Jesign experience at GE in nuclear energy. Responsible for the development of the man machine interface design for the ABWR and SBWR projects. Experience includes human factors engineering for the General Electric Emergency Response information System (SPDS) and GEPAC Plus and NUhtAC computer pioducts ' ,

Second Team hiember: Fifteen years experience at GE in nuclear energy. Developed lluman Factors

• Engineering Plan and documentation system for ABWR Project. Currently technical leader of an international study group working on design optimization for the SBWR Project.

Third Team hiember: Thirty one years experience at GE in nuclear energy. Experience includes the l cvaluation, development and implementation of quality assurance requirements and procedures for the ABWR certification program in the United States and the ABWR Project in Japan, the audit and review of GE quality and management activities both domestical and international and the review and development of both BWR and fast reactor fuel.

Fourth Team hiember: Twelve years experience at GE in nuclear energy. Experience includes instrumentation and control system design, human factrors engineering of nuclear power plant control rooms, containment transient analysis and program management. Conducted detailed control room design reviews for ,

several domestic and foreign operating and requisition nuclear plants. ,

Fifth Team hiember: Fourteen years experience at GE in nuclear energy. Responsible for preparation of Chapter 18, Human Factors Engineering", of the ABWR SSAR. Principal contributor to the development of plant automatic operation and control room design. Developed emergency operating procedures, system I operating procedures and integrated operating procedures for the ABWR.

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QUESTION 620.6 It appears that the workstation design may precede procedure design (which has historically been the case ,

in the nuclear industry). Yet, it seems that GE has the opportunity to follow the potentially va uable path of specifying what the operator has to accomplish in the control room to a great level of detail (via detailed task analyses and implementing procedures) and then design a workstation that will best support those operator tasks. Describe the temporal relationship between the future development of the operating procedures and the design of the workstation.

RESPONSE 620.6:

Early in the design of the ABWR, the need to specify the operator tasks and to develop operating procedures prior to the design of operator interfaces was recognized. Therefore, system level operating procedures were developed concurrent with the development of the ABWR system designs. These procedures consist of normal operating procedures for systems and for integrated plant startup and shutdown operations.

In addition, symptom-based emergency procedure guidelines were developed. These procedures were used as inputs for task analyses. Man machine interface requirements were then specified based upon these task analyses.

The symptom based emergency procedure guidelines developed for the U.S. ABWR are based on the U.S.

BWROG Emergency Procedure Guidelines, Revision 4 and are presented in Appendix 18A. These guidelines specify operator actions for accidents including postulated severe accidents. Section 18.5 specifies requirements for verification and validation of operator interfaces, taking into consideration normal plant operation and ,

emergency plant operation.

QUESTION 620.9 Describe the role of GE in the development of normal, abnormal and emergency operating procedures, including the generic technical basis document and writers guide, the development of procedures generation ,

documents, the verification and validation process, and the procedures maintenance program. Will GE develop sample procedures or offer a package of procedures to be modified based on site specific technical considerations?

RESPONSE 620.9:

GE has developed normal and emergency operating procedures as inputs for operator task analyses. In addition, GE has developed the ABWR Emergency Procedure Guidelines (EPGs), included in Appendix 18A.

Appendix 18D lists all the inputs used for calculation of operation limits and the outputs of those calculations.

The results of these calculations have been incorporated into the EPGs in Appendix 18A. The applicant :

referencing the ABWR design will be required to update some of the calculations based upon specific plant installation details and submit the procedure generation package as required by NUREG-0737 Supplement 1.

In essence, GE has developed the plant-specific technical guidelines normally required of an operating utility.The procedure verification, salidation, training, writer's guide, and maintenance programs will be the responsibility of the applicant referencing the ABWR design.

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