ML20107G268
| ML20107G268 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUREG-0800, NUREG-0800-18.0-R1, NUREG-800, NUREG-800-18.0-R1, SRP-18.00, TAC-51177, NUDOCS 8411070294 | |
| Download: ML20107G268 (5) | |
Text
NUREG-0000 (Fctm:rly NUREG-75/087)
/ kmRECog'% U.S. NUCLEAR REGULATORY COrdMISSION f4#,i STANDARD REVIEW PLAN
/
OFFICE OF NUCLEAR REACTOR REGULATION
,4. s Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants 18.0 Section No.
L Revision No. 1 Appendix No. ^
l Revision No.
NA NA Branch Tech. Position Revision No.
NA b
September 1984 Date issued l
FILING INSTRUCTIONS PAGES TO BE REMOVED NEW PAGES TO BE INSERTED PAGE NUMBER DATE PAGE NUMBER DATE l
Section 18.0 Section 18.0 1
18.0-1 Rev 0 July 1981 18.0-1 Rev 1 September 1984 To To 18.0-11 18.0-3 I
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8411070294 841031 PDR NUREG 0800 R PDR The U.S. Nuclear Regulatory Commission's Standard Review Plan, NUREG-0800, prepared by the Office of Nuclear Reactor Regulation, is available for sale by the National Technical Inforrnation Service, Springfield, VA 22161.
NUREG-0800 (Fcrm:rly NUREG-75/087) pa arc y
s U.S. NUCLEAR REGULATORY COMMISSION (M;' sj STANDARD REVIEW PLAN
/
OFFICE OF NUCLEAR REACTOR REGULATION ee...
18.0 HUMAN FACTORS ENGINEERING - INTRODUCTION The Human Factors Engineering Branch (HFEB) has primary responsibility for review of the human factors engineering design of the main control room and of control centers outside of the main control room.
Because of the close relation-ship of the human factors engineering aspects of plant staffing, shift composi-tion, procedures and operating instructions to control station design, the HFEB will coordinate its reviews closely with those Branches having primary responsi-bility for Chapter 13 of the Standard Review Plan.
Following the accident at Three Mile Island Unit 2, the NRC staff developed an Action Plan, NUREG-0660, to provide a comprehensive and integrated plan to improve the safety of power reactors.
Specific items from NUREG-0660 have been approved by the Commission for implementation at reactors and these were incor-porated in NUREG-0737, dated October 31, 1980.
Subsequently on December 17, 1982, the NRC staff issued Supplement 1 to NUREG-0737 which provided additional clari-fication on emergency response capabilities including the Detailed Control Room Design Review (DCRDR) and Safety Parameter Display System (SPDS).
Both the DCRDR and the SPDS address problems caused by the lack of emphasis on human factors engineering during the control room design process.
The DCRDR is performed by licensaes and applicants who have already designed their control room, to identify and correct human factors engineering design deficiencies.
The SPDS is also part of the control room upgrade and provides operating person-nel with a concentrated display of a minimum set of parameters which define the safety status of the plant.
Applicants who have not developed a control room design or are in the very early stages of a control room design should be utiliz-ing accepted human factors engineering principles during this process.
There-fore, it is not specifically required that they perform a DCRDR as defined in Supplement 1 to NUREG-0737, and the function of a separe.te SPDS may be integrated into the overall control room design.
Rev 1 - September 1984 USNRC STANDARD REVIEW PLAN star.dard review plans are prepared for tt e guidance of the office of Nuclear Reactor Regulation staff responsible for the review of applications to construct and operate nuclear power plants. These documents are made available to the public as part of the Commission's policy to inform the nuclear industry and the general pubt;c of regulatory procedures and policies. standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants.
Not all sections of the Standarri Format have a corresponding review plan.
Published standard review plans will be revised per;odically, as appropriate, to accommodate comments and to reflect new informa.
tion and experience.
Comments and suggestions for improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission.
office of Nuclear Reactor Regulation, Washington, D.C. 20555.
Th2 human factors engineering (HFE) chapter of the SRP has been formatted to prcvide reviewer guidance for (a) licensees and applicants with existing or alr:ady designed control rooms and (b) applicants just starting the control ro:m design process.
A s:ction of the SRP is currently being developed which will include the SPDS.
In cddition, other SRP sections and/or appendices to Chapter 18 are under devel-opm:nt which will establish positions on technical problems and questions of int:rpretation that have arisen during reviews of control station design.
Tablo 18.0-1 identifies topics which are potential candidates for inclusion as SRP sections or appendices.
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18.0-2 Rev 1 - September 1984
Table 18.0-1 Potential SRP Sections and/or Appendices to Chapter 18 1.
Environment Maintenance Acoustics Illumination 2.
Multiunit Control Rooms Degree of Similarity Mirror Imaging 3.
Control Room Workspace Communications Habitability / Access Emergency Equipment Storage 4.
Annunciators Types of Auditory Signals / Coding
" Blank" Tiles Periodic Testing
" Dark" Board Concept First Out Panels Alarm Tile, Matrix Color Coding Identification Prioritization Bulb Replacement Functional Grouping Alarm Tile, Contrast Tile Flash Rates Labeling / Engraving Controls and Locations Auditory Alarm Frequency and Normally "On" Tiles Intensity (Preferred)
Multi-Input Tiles Alarm Operation and Diagnostic Procedures "Out of Service" Alarm Tiles 5.
Panel Layout Consistency & Standardization Mirror-Imaging Clusters of Displays or Controls 6.
Visual Displays Color Coding (Lights, Indicators, CRT, C/D Relationship, Subsystem Delineation)
Display Character Size vs Viewing Distance (Visual Angle)
Flash Coding (Lights, CRT)
Lamp Test 7.
Controls Primary Control Location (Definition of Primary Controls)
Coding of Controls Accidental Activation Controls - Outside the Control Room 18.0-3 Rev 1 - September 1984