BS IEC 60965 pdf download – Nuclear power plants — Control rooms — Supplementary control points for reactor shutdown without access to the main control room
1 Scope
This International Standard establishes requirements for the supplementary control pointsprovided to enable the operating staff of nuclear power plants to shut down the reactor andmaintain the plant in a safe shut-down state in the event that control of the safety functionscan no longer be exercised from the main control room, due to unavailability of the maincontrol room or its facilities.
The standard also establishes requirements for the selection of functions,the design andorganisation of the human-machine interface,and the procedures which shall be usedsystematically to verify and validate the functional design of the supplementary control points.
lt is assumed that supplementary control points provided for shutdown operations fromoutside the main control room would be unattended during normal plant conditions other thanfor periodic testing.The requirements reflect the application of human engineering principlesas they apply to the human-machine interface during such periodic testing and duringabnormal plant conditions.
This standard does not cover special emergency response facilities (e.g. a technical supportcentre) or facilities provided for radioactive waste handling. Detailed equipment design is alsooutside the scope of the standard.
This standard follows the principles of IAEA Requirements NS-R-1 “Safety of Nuclear PowerPlants: Design” and lAEA Safety Guide NS-G-1.3“Instrumentation and Control Systemslmportant to Safety in Nuclear Power Plants”.
The purpose of this standard is to provide functional design requirements to be used in thedesign of the supplementary control points of a nuclear power plant to meet safetyrequirements.
This standard is intended for application to supplementary control points whose conceptualdesign is initiated after the publication of this standard. If it is desired to apply it to existingplants or designs,special care must be taken to ensure a consistent design basis. Thisrelates,for example, to factors such as the consistency between the supplementary controlpoints and the main control room, the ergonomic approach,the automation level and theinformation technology.
2Normative references
The following referenced documents are indispensable for the application of this document.For dated references,only the edition cited applies. For undated references, the latest editionof the referenced document (including any amendments) applies.
IEC 60709,Nuclear power plants – Instrumentation and control systems important to safety -Separation
IEC 60964,Nuclear power plants -Control rooms – Design
IEC 61226,Nuclear power plants – Instrumentation and control systems important for safety -Classification of insfrumentation and control functions
IEC 61513,Nuclear power plants – lnstrumentation and control for systems important tosafety – General requiremenfs for systems
IEC 61771,Nuclear power plants – Main control room – Verification and validation of design
IAEA NS-R-1:2000,Safety of nuclear power plants: Design
IAEA NS-G-1.3:2002,Instrumentation and Control Systems lmportant to Salety in NuclearPower Plants
3Terms and definitions
For the purposes of this document, the following terms and definitions apply. For other terms,refer to the general terminology defined in lEC 60964,IEC 61513 and in the IAEA NuSSprogramme, such as Safety Guide NS-G-1.3 or the safety glossary.
3.1
control room staff
a group of plant personnel stationed in the control room,which is responsible for achievingthe plant operational goals by controlling plant through the human-machine interface.Typically, the control room staff consists of supervisory operators, and operators who actuallymonitor plant and plant conditions and manipulate controls, but may also include those staftmembers and experts who are authorised to be present in the control room, e.g. during longlasting event sequences.
[IEC 60964,3.4]
3.2
local control points (or facilities)
points (or facilities) located outside the control room where local operators perform controlactivities
[IEC 60964,3.17]
3.3
local operators
the operating staff that perform tasks outside the control room[IEC 60964,3.18]
3.4
operating staff
plant personnel working on shift to operate the plant. The operating staff includes the controlroom staff, maintenance engineers,etc.
[IEC 60964,3.20]
3.5
supplementary control point
a location from which limited plant control and/or monitoring can be carried out to accomplishthe safety functions identified by the safety analysis as required in the event of a loss ofability to perform those functions from the main control room.The supplementary control pointmay be a special control room,but in many cases comprises a set of control panels anddisplays in switchgear rooms or similar areas.
BS IEC 60965 pdf download – Nuclear power plants — Control rooms — Supplementary control points for reactor shutdown without access to the main control room
