NUREG-0696

Functional Criteria for

Emergency Response Facilities

Final Report

Manuscript Completed: December 1980

Date Published: February 1981

Division of Emergency Preparedness Office of Inspection and Enforcement

U.S. Nuclear Regulatory Commission

Washington, D.C. 20555
ABSTRACT

This report describes the facilities and systems to be used by nuclear power

plant licensees to improve responses to emergency situations. The facilities

include the technical support center (TSC), onsite operational support center

(OSC), and nearsite emergency operations facility (EOF), as well as a brief

discussion of the emergency response function of the control room. The data

systems described are the safety parameter display system (SPDS) and nuclear

data link (NDL). Together, these facilities and systems make up the total

emergency response facilities (ERFs). Licensees should follow the guidance

provided both in this report and in NUREG-0654 (FEMA-REP-1), Revision 1 for

design and implementation-of the ERFs.

This document is being issued to establish criteria that the NRC staff intends

to use in evaluating whether an applicant/licensee meets the requirements of

10 CFR 50, Appendix E, Article IV.E.8 and Appendix A, GDC 19. It is not a

substitute for the regulations, and compliance is not a requirement. However,

the use of criteria different from those set forth herein will be accepted only

if the substitute criteria provide a basis for determining that the above-cited

regulatory requirements have been met.

iii
Contents

Page

ABSTRACT....................................iii

1. INTRODUCTION........................................................ 1

1.1 Background. 1

1.2 Control Room. 2

1.3 Emergency Response Facilities. 3

1.3.1 Technical Support Center. 3

1.3.2 Operational Support Center. 4

1.3.3 Emergency Operations Facility. 4

1.3.4 Safety Parameter Display System. 4

1.3.5 Nuclear Data Link. 4

1.4 Activation and Use. 5

1.5 Reliability. 5

2. TECHNICAL SUPPORT CENTER. 8

2.1 Function. 8

2.2 Location. 9

2.3 Staffing and Training. 9

2.4 Size .10

2.5 Structure .10

2.6 Habitability .11

2.7 Communications .11

2.8 Instrumentation, Data System Equipment, and Power Supplies .12

2.9 Technical Data and Data System ................................. 13

2.10 Records Availability and Management .15

3. OPERATIONAL SUPPORT CENTER .15

3.1 Functions .. 15

3.2 Habitability ............... 16

3.3 Communications .. 16

4. EMERGENCY OPERATIONS FACILITY ....................................... 16

4.1 *Functions ............................................ ;. 16

4.2 Location, Structure, and Habitability .. 17

4.3 Staffing and Training .......................................... 19

4.4 Size ................ 19

4.5 Radiological Monitoring ........................................ 20

4.6 Communications ............................ 20

v
Contents (continued)

Page

4. 7 Instrumentation, Data System Equipment, and Power Supplies ..... 21

4.8 Technical Data and Data System .22

4.9 Records Availability and Management .23

5. SAFETY PARAMETER DISPLAY SYSTEM .24

5.1 Function .24

5.2 Location....................................................... 25

5.3 Size .25

5.4 Staffing .25

5.5 Display Considerations .26

5.6 Design Criteria .26

6. NUCLEAR DATA LINK .27

6.1 Function .27

6.2 Description .28

6.3 NDL Interface .30

6.4 Environment .30

7. ACQUISITION AND CONTROL OF TECHNICAL DATA .31

7.1 Sources of Technical Data .31

7.2 Acquisition of Data .31

7.3 DAS Functional Limitations .31

7.4 DAS Design, Verification, and Configuration Control .31

7.5 DAS Reliability .34

8. EMERGENCY RESPONSE FACILITY INTEGRATION .34

9. VERIFICATION AND VALIDATION CRITERIA ................. ; .............. 35

10. BIBLIOGRAPHY........................................................ 36

FIGURES

Figure 1 NDL System Overview........................................... 29

Figure 2 Example of a Functional Block Diagram of Data Flow

Using Plant Process Computer .32

Figure 3 Example of a Functional Block Diagram of Data Flow

Without Using Plant Process Computer .33

vi
Contents (continued)

Page

TABLES

Table 1 Transfer of Emergency Response Functions from the

Control Room to the Technical Support Center and

the Emergency Operations Facility .............................. 6

Table 2 Relation of EOF Location to Habitability Requirements ........... 18

vii
FUNCTIONAL CRITERIA FOR EMERGENCY RESPONSE FACILITIES

1. INTRODUCTION

The facilities and systems described in this report are to be used by nuclear

power plant licensees to provide improved emergency response to accidents.

The facilities include the control room (CR), onsite technical support center

(TSC), onsite operational support center (OSC), and nearsite emergency operations facility (EOF). The systems include the safety parameter display system

(SPDS) and nuclear data link (NDL). Although the SPOS and the NDL are not

"facilities," for ease of description these systems and the facilities (TSC,

OSC, and EOF) will be referred to as the emergency response facilities (ERFs).

The TSC, EOF, and CR are required facilities specified by NRC regulations, 10

CFR 50, Appendix E, Article IV.E.8 and Appendix A, GDC 19. Although not specifi-.

cally required by the regulations, in order to perform NRC's statuatory responsibility to protect the public health and safety in the event of a radiological

incident at a nuclear power plant and as a result of lessons learned from the

Three Mile Island accident, the SPDS and the NDL system are included to provide

assurance that licensees and offsite authorities will have adequate information

to perform their tasks in an optimum manner. The OSC also is not specifically

required by the regulations, but is needed to ensure that an adequate facility

is provided for onsite emergency maintenance and for other support personnel to

gather as a ready resource to support actions initiated by the CR. Thus, the

SPDS, NDL, and OSC are integrally related to the emergency response facilities

required by the regulations, and are needed to ensure that their functions can

be effectively performed during an emergency. This document provides guidance

on the functional criteria for the ERFs and on the integrated support these

facilities will provide to the control room. Design and implementation of the

ERFs should also be integrated with the licensee's implementation of NUREG-0654

(FEMA-REP-1), Revision 1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power

Plants."'* The report also provides detailed criteria for emergency response

and certain emergency planning elements necessary for designing these facilities.

1.1 Background

The accident at Three Mile Island led to studies performed both within and

outside NRC that identified the need for extensive improvements in the response

of management to accidents at nuclear power plants. Some of the identified

improvements include:

* Establishing formal licensee, local, State, and Federal organizations

to better manage and effectively coordinate emergency response support;

* Developing integrated emergency response facilities and data systems

to aid in this management;

Providing for better information needed to assess conditions at a

plant and its environs prior to, during, and following an accident;

xFor complete information on material referenced in this report, refer to the

Bibliography (Section 10) at the end of the text.

1
Providing an improved capability by licensee and Federal organizations

to provide recommendations to State and local authorities on actions

protecting the public; and

Providing transmission of more accurate information to Federal, State,

and local emergency response organizations, and to the general public.

with respect to licensee activities'and responsibilities, NRC has determined

that the emergency response facilities and systems that will provide the necessary improvements are the TSC, OSC, EOF, SPDS and NDL. These facilities and

systems will operate as an .integrated system to support the control room in

the mitigation of the consequences of accidents and to enhance the licensee's

capability to respond to abnormal plant conditions. These facilities and

systems will help to provide a graduated response capability that is dependent

on the severity of an emergency. Severity conditions are classified into

emergency classes (in order of increasing severity) by NUREG-0654, Revision 1,

Appendix 1 as follows:

(1) Notification of Unusual Event

(2) Alert

(3) Site Area Emergency

(4). General Emergency

1.2 Control Room

The control room is the onsite location from which the nuclear power plant is

operated. It contains the instrumentation, controls, and displays for:

* Nuclear systems,

* Reactor coolant systems,

* Steam systems,

* Electrical systems,

* Safety systems (including engineered safety features), and

* Accident monitoring systems.

The control room is staffed by licensed reactor operators, the senior reactor

operators, and a senior reactor operator designated as the shift supervisor.

Safe operation of the reactor and plant manipulations remain under the control

of a licensed senior reactor operator, a reactor operator, or shift supervisor

at all times.

During abnormal operating conditions, the complexity of licensee responsibilities increases significantly. These responsibilities include actions taken

to:

* Diagnose the abnormal conditions;

* Perform corrective actions;

* Mitigate the abnormal conditions;

* Manage plant operations;

Manage emergency response;

* Inform Federal, State, and local officials;

* Recommend public protective measures to State and local officials;

* Restore the plant to a safe condition; and

* Recover from the abnormal conditions.

2
Initially, the control room personnel must assume all of these responsibilities.

1.3 Emergency Response Facilities

In helping personnel in the control room to mitigate the consequences of accidents

and respond to abnormal operating conditions, the emergency response facilities

(ERFs) shall function during emergencies to provide the following services:

* Help the reactor operators determine the plant safety status;

* Relieve the reactor operators of peripheral duties and communications

not directly related to reactor'system manipulations;

* Prevent congestion in the control room;

* Provide assistance to the operators by technical personnel who have

comprehensive plant data at their disposal;

* Provide a coordinated emergency response by both technical and

management personnel;

* Provide reliable communications between onsite and offsite emergency

response personnel;

* Provide a focal point for development of recommendations for offsite

actions; and

* Provide relevant plant data to the NRC .for its analysis of abnormal

plant operating conditions.'

Many of the ERF functions will be performed through the use of one or more

data systems that will gather, store, and process data for display in the control room, TSC, EOF, and NRC, Operations Center. A partially or fully integrated

ERF data system or separate data systems may be used to fulfill the ERF functions. A recent-generation plant process computer is one data system that

could be used to gather and process these data for display in the ERFs.

However, use of a process computer requires that it meet all of the criteria

prescribed later in this document. If it cannot meet these criteria,

independent data systems must be installed.

The personnel designated for duty in the ERFs shall be trained to follow

procedures specified in the licenseet's emergency plan to ensure timely '

emergency response.' Detailed management plans, facility staffing, and task

assignments of these emergency response personnel are site specific and shall

be part of the licensee's emergency plan developed from the guidance provided

by NUREG-0654, Revision 1.

1.3.1 Technical. Support Center

The technical support center (TSC) is an onsite facility 'located close to the

control room that shall provide plant management and technical support to the

reactor operating personnel located in the control room during emergency

3
conditions. It shall have technical data displays and plant records available

to assist in the detailed analysis and diagnosis of abnormal plant conditions

and any significant release of radioactivity to the environment. The TSC

shall be the primary communications center for the plant during an emergency.

A senior official, designated by the licensee, shall use the resources of the

TSC to assist the control room operators by handling the administrative items,

technical evaluations, and contact with offsite activities, relieving them of

these functions. The TSC facilities may also be used for performing normal

functions, such as shift technical supervisor and plant operations/maintenance

analysis functions, as well as for emergencies.

1.3.2 Operational Support Center

The operational support center (OSC) is an onsite assembly area separate from

the control room and the TSC where licensee operations support personnel shall

report in an emergency. There shall be direct communications between the OSC

and the control room and between the OSC and the TSC so that the personnel

reporting to the OSC can be assigned to duties in support of emergency

operations.

1.3.3 Emergency Operations Facility

The emergency operations facility (EOF) is a nearsite support facility for the

management of overall licensee emergency response (including coordination with

Federal, State, and local officials), coordination of radiological and environmental assessments,.and determination of recommended public protective actions.

The EOF shall have appropriate technical data displays and plant records to

assist in the diagnosis of plant conditions to evaluate the potential or actual

release of radioactive materials to the environment. A senior licensee official

in the EOF shall organize and manage licensee offsite resources to support the

TSC and the control room operators.

1.3.4 Safety Parameter Display System

The safety parameter display system (SPDS) provides a display of plant parameters

from which the safety status of operation may be assessed in the control room,

TSC, and EOF. The primary function of the SPDS is to help operating personnel

in the control room make quick assessments of plant safety status. Duplication

of the SPDS displays in the TSC and EOF will improve the exchange of information

between these facilities and the control room and assist corporate and plant

management in the decision-making process. The SPDS shall be operated during

normal operations and during all classes of emergencies. The SPDS should have

the flexibility to allow future modifications to be incorporated, such as the

capability to handle operator interaction and diagnostic analysis.

1.3.5 Nuclear Data Link

The nuclear data link (NDL), a data transmission system, will be designed to

send a set of variables from the plant to the NRC Operations Center. These

data will be used for analyses by the NRC headquarters technical support groups

and NRC Executive Team. The NDL will transmit information that will aid NRC

in its role of providing advice and support to the nuclear power plant licensee,

State and local authorities, and other Federal officials.

.4
1.4 Activation and Use

The activation and use of the ERFs shall be determined by the emergency class

and by the specific conditions surrounding an accident and shall be specified

in the licensee's emergency plan. As a minimum, within the unavailability

criteria, the following conditions shall apply:

(1) The SPDS shall be operational during all plant operating conditions,

including accidents.

(2) Activation of the onsite TSC and OSC is optional for a Notification of

Unusual Event emergency class, and is required for Alert and higher classes.

(3) Activation of the nearsite EOF is optional for Notification of Unusual

Event and Alert emergency classes, and is required for Site Area Emergency

and General Emergency classes.

(4) Data shall be available for transmittal through the NDL during all plant

operating conditions above cold shutdown.

Until the TSC, OSC, and EOF are activated, all functions of these facilities

shall be performed in the control room. When the TSC is functional, emergency

response functions, except direct supervision of reactor operations and manipulation of reactor system controls, shall shift to the TSC. Plant administration,

technical support functions, and contact with offsite activities to assist the

control room operators shall be performed in the TSC throughout the course of

an accident. The OSC shall provide a place for operations support personnel

to be in direct communication with the control room and other operations managers

for assignment to duties in support of emergency operations. When the EOF is

activated, the functions of providing overall emergency response management,

monitoring and assessing radiological effluent and the environs, making offsite

dose projections, providing recommendations to State and local officials, and

coordinating with Federal officials will shift to the EOF. See Table 1 for an

outline of the transfer of emergency response functions from the control room

to the TSC and EOF under the various emergency classes.

The level of staffing of the ERFs may vary according to the severity of the

emergency condition. The staffing criteria for each emergency class shall be

fully detailed in the licensee's emergency plan.

1.5 Reliability

The data systems, instrumentation, and facilities of the ERFs shall be designed

and constructed to provide a very high degree of reliability. The reliability

criteria for the ERF systems, instrumentation, and facilities shall be described

in terms of unavailability. This unavailability is specified in terms of an

operational unavailability goal of 0.01 that is applicable to all ERFs when

the reactor is above cold shutdown status. This operational unavailability

goal shall be defined in units of time as:

Downtime

Operational unavailability =

Operating time

. 5
Table 1. Transfer of Emergency Response

Functions from the Control Room to the

Technical Support Center and the Emergency Operations Facility

Emergency Class

Notification

of Unusual Site Area General

Emergency Response Functions Event Alert Emergency Emergency

Supervision of reactor

operations and manipulation

of controls

CR CR CR CR

Management of

plant operations

Technical support

to reactor operations

CR(TSC) TSC

TSC

TSC TSC1

CR(TSC) TSC TSC

Management of corporate

emergency response

resources

Radiological effluent and

environs monitoring,

assessment, and dose

projections

Inform Federal, State,

and local emergency response

organizations and make

recommendations for public

protective actions

CR(TSC,EOF)

CR(TSC,EOF)

CR(TSC,EOF)

TSC(EOF)

TSC(EOF)

TSC(EOF)

EOF EOF

EOF EOF

EOF EOF

Event monitoring by NRC

regional emergency

response team*

(CR) TSC(EOF) TSC&EOF TSC&EOF

Management of recovery

operations

Technical support of

recovery operations

CR(TSC,EOF)

CR(TSC,EOF)

TSC(EOF)

TSC

EOF EOF

TSC TSC

Note: (CR), (TSC), (EOF), or (TSC, EOF) indicates that activation of this facility

(or the performance of this function) is optional for the indicated emergency

class.

*One NRC individual also may be stationed in the control room.

6
where:

Downtime = any length of time the data systems, instrumentation, or

facilities are unavailable when the reactor is above cold

shutdown status because of the following:

inability to perform its intended function;

* impaired ability to perform its intended function due

to degraded circuits, equipment, power supplies, or

instrumentation (this shall not include truly

redundant equipment such as core thermocouples or

computer peripherals);

* unreliable performance due to the lack of adequate

sensor data; and

* scheduled outages to perform preventive maintenance

on instrumentation, equipment, power supplies, or

sensors. (The design of the systems and facilities

shall be to limit these scheduled outages to no more

than 16 hours per calendar quarter, and ERFs must be

capable of becoming fully operational within 30 minutes

during these outages.)

Operating time any length of time the reactor is above cold shutdown status.

In addition to the operational criterion during reactor operation, the SPDS

also has an unavailability goal while the reactor is in cold shutdown status.

For cold shutdown status including the refueling mode, the specified unavailability goal of the SPDS is 0.2. This SPDS cold shutdown unavailability shall

be defined in units of time as:

Downtime

SPDS cold shutdown unavailability =

Cold shutdown time

where:

Downtime = any length of time the SPDS data system, instrumentation,

and power supplies are unavailable when the reactor is in

cold shutdown status because of the following:

inability to perform its intended function;

* impaired ability to perform its intended function due

to degraded circuits, instrumentation, or power supplies;

* unreliable performance due to the lack of sensor data;

scheduled outages for preventive maintenance of

instrumentation, power supplies, or sensors. (The

7
SPDS must be able to be made available within 30

minutes during such outages.)

Cold shutdown time = any length of time the reactor is in a cold shutdown status

and refueling mode.

The TSC, EOF, and NDL have no cold shutdown unavailability goals while the

reactor is in cold shutdown status.

2. TECHNICAL SUPPORT CENTER

2.1 Function

The onsite technical support center (TSC) will provide the following functions:

* Provide plant management and technical support to plant operations

personnel during emergency conditions.

* Relieve the reactor operators of peripheral duties and communications

not directly related to reactor system manipulations.

* Prevent congestion in the control room.

Perform EOF functions for the Alert Emergency class and for the Site

Area Emergency class and General Emergency class until the EOF is

functional.

The TSC shall be the emergency operations work area for designated technical,

engineering, and senior licensee management personnel; any other licenseedesignated personnel required to provide the needed technical support; and a

small staff of NRC personnel. The primary role of NRC in the TSC will be to

observe plant operation and provide advisory support to plant management. A

senior licensee official shall use the resources of the TSC to provide guidance

and technical assistance to the operating supervisor in the control room.

However, all manipulations shall be performed by the control room licensed

operators.

The TSC shall have facilities to support the plant management and technical

personnel who will be assigned there during an emergency and will be the primary onsite communications center for the plant during the emergency. TSC

personnel shall use the TSC data system to analyze the plant steady-state and

dynamic behavior prior to and throughout the course of an accident. The results

of this analysis will be used to provide guidance to the control room operating

personnel in the management of abnormal conditions and in accident mitigation.

TSC personnel will also use the environmental and radiological information available from the TSC data system to perform the necessary functions of the EOF

when this facility is not operational. The TSC also may be used to provide

technical support during recovery operations following an emergency.

The TSC facilities may be used by designated operating personnel for normal

daily operations as well as for training and emergency drills. Use of the TSC

facility during normal operation shall be limited to activities that will not

degrade TSC preparedness to react to abnormal conditions or reduce TSC systems

8
reliability. The shift technical advisor (STA) may use the TSC facilities in

performing his duties during normal operating conditions in addition to using

them during emergencies.

Lilcensees who cannot meet the criteria for location, size, and habitability

for the TSC must submit to NRC a request for an exception. This request must

include justification for the exception and an alternate proposal. NRC will

review requests for exceptions on a case-by-case basis.

2.2 Location

The onsite TSC is to provide facilities near the control room for detailed

analyses of plant conditions during abnormal conditions or emergencies by

trained and competent technical staff. During recent events at nuclear power

-plants, telephone communications between the facilities were ineffective in

providing all of the necessary management interaction and technical information

exchange. This demonstrates the need for face-to-face communications between

TSC and control room personnel. To accomplish this, the TSC shall be as close

as possible to the control room, preferably located within the same building.

The walking time from the TSC to the control room shall not exceed 2 minutes.

This close location will facilitate face-to-face interaction between control

room personnel and the senior plant manager working in the TSC. This proximity

also will provide access to information in the control room that is not available

in the TSC data system.

Provisions shall be made for the safe and timely movement of personnel between

the TSC and the control room under emergency conditions. These provisions shall

include consideration of the effects of direct radiation and airborne radioactivity from inplant sources on personnel traveling between the two facilities.

Anticontamination clothing, respiratory protection, and other protective gear

may be used to help protect personnel in transit. The 2-minute travel time

between the TSC and the control room does not include time required to put on

any necessary radiological protective gear, but it does include the time required

to clear any security checkpoints. There should be no major security barriers

between these two facilities other than access control stations fol- the TSC

and control room.

2.3 Staffing and Training

Upon activation of.the TSC, designated personnel shall report directly to the

TSC and achieve full functional operation within 30 minutes. Activation of

the TSC shall ensure that only designated operating personnel are in the control

room during the emergency and that needed technical support will be provided

without obstructing actual plant manipulations or overcrowding the control room.

The licensee-designated TSC staff shall consist of sufficient technical, engineering, and senior designated licensee officials to provide the needed support to the

control room during emergency conditions. Consultants also may be designated

by the licensee to augment utility resources in the TSC. A senior designated

licensee official shall coordinate activities in the TSC and interface with

the control room, the OSC, and the EOF.

The level of staffing of the TSC may vary according to the severity of the

emergency condition. The staffing for each emergency class shall be fully

detailed in the licensee's emergency plan.

9
For the TSC to function effectively, TSC staff personnel must be aware of

their responsibilities during an accident. The licensee shall, therefore,

develop training programs for these personnel. In addition, to maintain

proficiency, the TSC staff shall participate in TSC activation drills that

shall be conducted periodically in accordance with the licensee's emergency

plan. Operating procedures and staff training in the use of data systems and

instrumentation shall contain guidance on the limitations of instrument

readings including whether the information can be relied upon following such

events as accidents resulting from earthquakes or the release of radiation.

2.4 Size

The TSC may be housed in a complex of directly adjacent areas. It shall be

large enough to provide:

* Working space, without crowding, for the personnel assigned to the

TSC at the maximum level of occupancy (minimum size of working space

provided shall be approximately 75 sq ft/person);

* Space for the TSC data system equipment needed to acquire, process,

and display data used in the TSC;

* Sufficient space to perform repair, maintenance, and service of

equipment, displays, and instrumentation;

* Space for data transmission equipment needed to transmit data

originating in the TSC to other locations;

* Space for personnel access to functional displays of TSC data;

* Space for unhindered access to communications equipment by all TSC

personnel who need communications capabilities to perform their

functions;

* Space for storage of and/or access to plant records and historical

data; and

* A separate room adequate for at least three persons to be used for

private NRC consultations.

The TSC working space shall be sized for a minimum of 25 persons, including 20

persons designated by the licensee and five NRC personnel. This minimum size

shall be increased if the maximum staffing level specified by the licensee's

emergency plan exceeds 20 persons.

2.5 Structure

The TSC complex must be able to withstand the most adverse conditions reasonably

expected during the design life of the plant including adequate capabilities

for (1) earthquakes, (2) high winds (other than tornadoes), and (3) floods.

The TSC need not meet seismic Category I criteria or be qualified as an engineered safety feature (ESF). Normally, a well-engineered structure will provide
an adequate capability to withstand earthquakes. Winds and floods with a

100-year-recurrence frequency are acceptable as a design basis. Existing

buildings may be used to house the TSC complex if they satisfy the above minimum

criteria.

2.6 Habitability

Since the TSC is to provide direct management and technical support to the

control room during an accident, it shall have the same radiological habitability

as the control room under accident conditions. TSC personnel shall be protected

from radiological hazards, including direct radiation and airborne radioactivity

from inplant sources under accident conditions, to the same degree as control

room personnel. Applicable criteria are specified in General Design Criterion

19; Standard Review Plan 6.4; and NUREG-0737, "Clarification of TMI Action Plan

Requirements," Item II.B.2.

The TSC ventilation system shall function in a manner comparable to the control room ventilation system. The TSC ventilation system need not be seismic

Category I qualified, redundant, instrumented in the control room, or automatically activated to fulfill its role. A TSC ventilation system that includes

high-efficiency particulate air (HEPA) and charcoal filters is needed, as a

minimum. Sufficient potassium iodide shall be provided for use by TSC and

control room personnel. The capacity of the installed TSC ventilation filter

system shall be independent of these thyroid-blocking provisions.

To ensure adequate radiological protection of TSC personnel, radiation monitoring systems shall'be provided in the TSC. These monitoring systems may be

composed of installed monitors or portable monitoring equipment dedicated to

the TSC. These systems shall continuously indicate radiation dose rates and

airborne radioactivity concentrations inside the TSC while it is in use during

an emergency. These monitoring systems shall include local alarms with trip

levels set to provide early warning to TSC personnel of adverse conditions that

may affect the habitability of the TSC. Detectors shall be able to distinguish

the presence or absence of radioiodines at concentrations as low as 10-7

microcuries/cc.

Equipment *that protects personnel shall be provided in the TSC for the staff

who must travel between the TSC and the control room or the EOF under adverse

radiological conditions. Protective equipment also shall be provided to allow

TSC personnel to continue to function during the presence of low-level airborne

radioactivity or radioactive surface contamination. Anticontamination clothing

and respiratory protective gear are examples of equipment that shall be provided.

This equipment shall be properly maintained to assure availability during an

emergency.

If the TSC becomes uninhabitable, the TSC plant management function shall be

transferred to the control room.

2.7 Communications

The TSC will be the primary onsite communications center for the nuclear power

plant during an emergency. It shall have reliable voice communications to the

control room, the OSC, the EOF, and the NRC. The primary function of this voice

11
communication system will be plant management communications *and the immediate

exchange of information on plant status and operations. Provisions for communications with State and local operations centers also shall be provided in

the TSC to provide early notification and recommendations to offsite authorities prior to activation of the EOF.

The TSC voice communications facilities shall include means for reliable primary

and backup communication. The TSC voice communications may include private

telephones, commercial telephones, radio networks, and intercommunication systems

as appropriate to accomplish the TSC functions during emergency operating conditions. Existing licensee communications systems may be used if the systems

can be demonstrated to be reliable under emergency conditions and if they are

adequate to meet the added TSC requirements. The licensee shall provide a means

for TSC telephone access to commercial telephone common-carrier services that

bypasses any onsite or local offsite telephone switching facilities that may

be susceptible to loss of power during emergencies. The licensee shall ensure

that spare commercial telephone lines to the plant are available for use by

the TSC during emergencies.

The TSC voice communications equipment shall include:

* Hotline telephone (located in the NRC consultation room) on the NRC

emergency notification system (ENS) to the NRC Operations Center;

Dedicated telephone (located in the NRC consultation room) on the

NRC health physics network (HPN);

* Dedicated telephones for management communications with direct access

to the control room, the OSC, and the EOF;

* Dial telephones that provide access to onsite and offsite locations;

Intercommunications systems between work areas of the TSC, if needed

for the TSC functional performance or if the TSC is comprised of

separate functional areas; and

* Communications to licensee mobile monitoring teams and to State and

local operations centers prior to EOF activation.

The TSC communication system shall also include designated telephones (in

addition to the ENS and HPN telephones) for use by NRC personnel. The licensee

shall provideat least two dial telephone lines for such NRC use when the TSC

is activated. The licensee shall also furnish the onsite access facilities

and cables to the NRC for the ENS and HPN telephones.

Facsimile transmission capability between the TSC, the EOF, and the NRC Operations Center shall also be provided.

2.8 Instrumentation, Data System Equipment, and Power Supplies

Equipment shall be provided to gather, store, and display data needed in the

TSC to analyze plant conditions. The data system equipment shall perform these

12
functions independent of actions in the control room and without degrading or

interfering with control room and plant functions. TSC instrumentation data

system equipment and power supplies need not meet safety-grade or Class lE

requirements. When signals to the TSC are received from sensors providing

signals to safety system equipment or displays, suitable isolation shall be

provided in accordance with GDC 24 to ensure that the TSC systems will not

degrade performance of the safety system equipment or displays.

The TSC electrical equipment load shall not degrade the capability or reliability

of any safety-related power source. Circuit transients or power-supply failures

and fluctuations shall not cause a.loss of any stored data vital to the TSC

functions. Sufficient alternate or backup power sources shall be provided to

maintain continuity of TSC functions and to immediately resume data acquisition,

storage, and display of TSC data if loss of the primary TSC power sources occurs.

The total TSC data system reliability shall be designed to achieve an operational unavailability goal of 0.01 during all plant operating conditions above

cold shutdown as described in Section 1.5.

The plant data processor (plant process computer) may provide, if stringent

conditions are met, the TSC data system functions or may have data for the TSC

system transmitted through it. In either case, the performance of the plant

data processor and its related .instrumentation and equipment shall be included

when determining the TSC data system unavailability. In addition, the computa-.

tional capacity and data throughput of the plant processor must be sufficient

to accommodate the combined computational and input-output loads of the .TSC

system and the other functions being performed by the plant processor. TSC

data processed through the plant data processor shall be continuously available

to the TSC with the same reliability and accuracy required of a data system

designed to operate independently from the plant data processor. Use of the

plant data processor shall not degrade the integrity of data supplied to the

TSC or the security of the software used to process TSC data.

The SPDS display equipment used in the TSC need not be seismically qualified;

it need only meet the TSC data system equipment reliability and performance

criteria. The design of the TSC data system equipment shall incorporate human

factors engineering with consideration for both operating and maintenance

personnel.

2.9 Technical Data and Data System

The TSC technical data system shall receive, store, process, and display information acquired from different areas of the plant as needed to perform the TSC

function. The data available for display in the TSC must enable the plant

management, engineering, and technical personnel assigned there to aid the

control room operators in handling emergency conditions. The data system shall

provide access to accurate and reliable information sufficient to determine:

* Plant steady-state operating conditions prior to the accident,

Transient conditions producing the initiating event, and

13
Plant systems dynamic behavior throughout the course of the

accident.

The TSC data system may be used for:

* Reviewing the accident sequence,

* Determining appropriate mitigating actions,

* Evaluating the extent of any damage, and

* Determining plant status during recovery operations.

The data set available to the TSC data system must be complete enough to permit

accurate assessment of the accident without interference from the control room

emergency operation. As a minimum, the set of Type A, B, C, D, and E variables

specified in Regulatory Guide 1.97, Revision 2, "Instrumentation for Light-WaterCooled Nuclear Power Plants to Assess Plant and Environs Conditions During and

Following an Accident," shall be available for display and printout in the TSC.

In addition, all sensor data and calculated variables not specified in Reg.

Guide 1.97 but included in the data sets for the SPDS, for the EOF, or for

transmission to offsite locations shall be available for display. The accuracy

of the data displayed shall not be significantly less than the accuracy of

comparable data displayed in the control room. The time resolution of data

acquisition shall be sufficient to provide data without loss of information

during transient conditions. The time resolution for each sensor signal will

depend on the potential transient behavior of the variable being measured.

The TSC data displays of Reg. Guide 1.97 variables shall meet the criteria for

TSC data but need not meet the Reg. Guide 1.97 design and qualification criteria

for display of those variables in the control room.

Data storage and recall capability shall be provided for the TSC data set. At

least 2 hours of pre-event data and 12 hours of post-event data shall be recorded.

The 'sample frequency shall be chosen to be consistent with the use of the data.

Capacity to record at least two weeks of additional post-event data with reducedtime resolution shall be provided. Archival data storage and the capability

to transfer data between active memory and archival data storage Without

interrupting TSC data acquisition and displays shall be provided for all TSC

data.

A sufficient number of data display and printout devices shall be provided in

the TSC to allow all TSC personnel to perform their assigned tasks with unhindered access to data. The TSC displays shall include, but not be limited to,

alphanumeric and/or graphical representations of:

* Plant systems variables,

* In-plant radiological variables,

* Meteorological information, and

* Offsite radiological information.

Trend information display and time-history display capability is needed in the

TSC to give the TSC personnel a dynamic view of the plant status during abnormal

14 .
operating conditions. The TSC displays shall be designed so that callup, manipulation, and presentation of data can be easily performed. The TSC data display

formats shall present information so that it can be easily understood by the

TSC personnel performing analyses.

The SPDS shall also be displayed in the TSC. This duplication will improve the

exchange of information between the control room and the TSC. If the SPDS

system in the control room is composed of multiple display units, multiple

displays must also be provided in the TSC.

2.10 Records Availability and Management

The TSC shall have a complete and up-to-date repository of plant records and

procedures at the disposal of TSC personnel to aid in their technical analysis

and evaluation of emergency conditions. In particular, up-to-date as-built

drawings of the plant systems are needed to diagnose sensor data, evaluate data

inconsistencies, and identify and counteract faulty plant system elements.

The TSC personnel shall have ready access to up-to-date records, operational

specifications, and procedures that include but are not limited to:

* Plant technical specifications,

* Plant operating procedures,

* Emergency operating procedures,

* Final Safety Analysis Report,

Plant operating records,

* Plant operations reactor safety committee records and reports,

* Records needed to perform the functions of the EOF when it is not

operational,

and up-to-date, as-built drawings, schematics, and diagrams showing:

* Conditions of plant structures and systems down to the component level,

and

* In-plant locations of these systems.

All of the above records shall be available in the TSC in current form when

this facility is fully implemented. These records will be updated as necessary

to ensure currency and completeness. The method of storage and presentation

of the TSC records shall ensure ease of access under emergency conditions.

3. OPERATIONAL SUPPORT CENTER

3.1 Functions

The operational support center (OSC) is an onsite area separate from the control room and the TSC where licensee operations support personnel will assemble

in an emergency. The OSC shall:

Provide a location where plant logistic support can be coordinated

during an emergency, and

15
Restrict control room access to those support personnel specifically

requested by the shift supervisor.

When the OSC is activated, it shall be supervised by licensee operations management personnel designated in the licensee's emergency plan to perform these

functions.

3.2 Habitability

No specific habitability criteria are established for the OSC. If the OSC

habitability is not comparable to that of the control room, the licensee's emergency plan shall include procedures for evacuation of OSC personnel in the event

of a large radioactive release. These procedures also shall include provisions

for the performance of the OSC functions by essential support personnel from

other onsite locations.

3.3 Communications

The OSC shall have direct communications with the control room and with the

TSC so that the personnel reporting to the OSC can be assigned to duties in

support of emergency operations. The OSC communications system shall consist

of one dedicated telephone extension to the control room, one dedicated telephone extension to the TSC, and one dial telephone capable of reaching onsite

and offsite locations, as a minimum. Direct voice intercommunications and/or

reliable direct radio communications may be used to supplement these telephone

communication links.

4. EMERGENCY OPERATIONS FACILITY

4.1 Functions

The emergency operations facility (EOF) is a licensee controlled and operated

offsite support center. The EOF will have facilities for:

* Management of overall licensee emergency response,

* Coordination of radiological and environmental assessment,

Determination of recommended public protective actions, and

* Coordination of emergency response activities with Federal, State,

and local agencies.

When the EOF is activated, it shall be staffed by licensee, Federal, State,

local and other emergency personnel designated by the emergency plan to perform

these functions. It shall be the location where the licensee provides overall

management of licensee resources in response to an emergency having actual or

potential environmental consequences. A designated senior licensee official

will manage licensee activities in the EOF to support the designated official

in the TSC and the senior reactor operator designated the shift supervisor in

the control room.

Facilities shall be provided in the EOF for the acquisition, display, and evaluation of all radiological, meteorological, and plant system data pertinent to

determine offsite protective measures. These facilities will be used to evaluate

the magnitude and effects of actual or potential radioactive releases from the

16
plant and to determine offsite dose projections. Facilities used in performing

essential EOF functions must be located within the EOF complex. However, supplemental calculations and analytical support of EOF evaluations may be provided

from facilities outside the EOF. The licensee also may use the EOF as the postaccident recovery management center.

The licensee shall use the EOF to coordinate its emergency response activities

with those of local, State, and Federal agencies, including the NRC. Licensee

personnel in the EOF will use the evaluations of offsite effects to make protective action recommendations for the public to State and local emergency

response agencies.

State and local agencies will be responsible for implementing emergency response

actions involving the general public. The State and local agencies may operate

from the EOF or from their own control centers at other locations, dependent

upon the site-specific provisions of the emergency plan at each plant. Collocation of offsite authorities at the EOF for the purpose of offsite dose

estimation is encouraged.

At the licensee's option, the EOF may be a location for information dissemination to the public via the news media by designated spokespersons in accordance

with the licensee's emergency plan. Provisions to allow periodic briefings of

a press pool at the EOF should also be made. Actual use of this provision would

depend on specific accident conditions and the emergency plan of the licensee.

The licensee shall provide normal industrial security for the EOF complex during

normal operating conditions. This protection is required to ensure EOF activation readiness for an emergency by the exclusion of unauthorized persons.

After the EOF is activated, security protection shall be upgraded to restrict

access to those personnel assigned to this facility. Any location provided in

the EOF for news media briefings shall be outside of the controlled access area.

To maintain a proper level of readiness, the EOF shall be activated periodically

for training and for emergency preparedness exercises as specified in the

licensee's emergency plan. The EOF facility may be used by designated

licensee personnel for normal daily operations as well as for training and

exercises. Use of the EOF during normal operations shall be limited to

activities that will not degrade EOF activation, operations,-or reliability.

4.2 Location, Structure, and Habitability

The location of the EOF, and whether a backup facility is required, should

consider the following factors:

Whether the location provides optimum functional and availability

characteristics for carrying out the licensee functions specified

for the EOF (i.e., overall strategic direction of licensee onsite

and support operations, determination of public protective actions

to be recommended by the licensee to offsite officials, and coordination of the licensee with Federal, State, and local organizations).

Whether the EOF functions would be interrupted during radiation

releases for which it was necessary to recommend protective actions

for-the public to offsite officials.

17
It is strongly recommended that the EOF location be coordinated with State and

local authorities to improve the relationship between the licensee and offsite

organizations.

The habitability criteria for the EOF determined by its location are given in

Table 2 below.

Table 2. Relation of EOF Location to Habitability Criteria

EOF Criteria

Item Distance within Distance at or beyond

Needed 10 mi of the TSC 10 mi of the TSC'

Structure Well engineered for Well engineered for

design life of plant2 design life of plant2

Protection factors > 5 None

Ventilation Isolation with HEPA4 None

protection filters (no charcoal)

Backup EOF5 Located within 10 None

to 20 mi of the TSC

ISpecific Commission approval is required for EOF locations beyond 20 miles

of the TSC. For these cases, provisions must include arrangements to locate

the NRC staff closer to the reactor.

2 As an example of "well engineered," refer to the Uniform Building Code. In

addition, it must be able to withstand adverse conditions of high winds (other

than tornadoes) and floods. Winds and floods with a 100-yr recurrence

frequency are acceptable for a design basis.

3 Protection factor is defined in terms of the attenuation of 0.7 MeV gamma

radiation. As a minimum, the protection factor only applies to those areas

of the EOF in which dose assessments, communications, and decisionmaking

take place.

4 Ventilation system shall function in a manner comparable to the control

room and TSC systems; but need not be seismic Category I qualified, redundant,

instrumented, or automatically activated.

5 Need not be a separate, dedicated facility, but, when activated, shall provide

continuity of dose prediction and decisionmaking functions by arranging for

portable backup equipment. No special provisions for protection factors

or ventilation protection are needed.

Licensees who cannot meet the requirements of size and habitability for the

EOF must submit to NRC a request for an exception. This request must include

justification for the exception and an alternate proposal. NRC will review

requests for exceptions on a case-by-case basis.

18
4.3 Staffing and Training

The EOF shall be staffed to provide the overall management of licensee resources

and the continuous evaluation and coordination of licensee activities during

and after an accident. Upon EOF activation, designated personnel shall report

directly to the EOF to achieve full functional operation within 1 hour. *A senior

management person designated by the licensee shall be in charge of all licensee

activities in the EOF. The EOF staff will'include personnel to manage the

licensee onsite and offsite radiological monitoring, to perform radiological

evaluations, and to interface with offsite officials. The EOF staff assignments

shall be part of the licensee's emergency plan. The specific-number and type

of personnel assigned to the EOF may vary according to the emergency class.

The staffing for each emergency class shall be fully detailed in the licensee's

emergency plan. Operating procedures and staff training in the use of data

systems and instrumentation shall contain guidance on the limitations of instrumentation including whether the information can be relied upon following serious

accidents.

In order to function effectively, the EOF staff personnel must be aware of their

responsibilities during an accident. To maintain proficiency, the EOF staff

shall participate in EOF activation drills, which shall be conducted periodically

in accordance with the licensee's emergency plan. These drills shall include

operation of all facilities that will be used to perform the EOF functions,

including any support facilities located outside the EOF.

4.4 Size

The EOF building or building complex shall be large enough to provide the

following:

* Working space for the personnel assigned to the EOF as specified in

the licensee's emergency plan, including State and local, agency personnel, at the maximum level of occupancy without crowding (minimum

size of working space provided shall be approximately 75 sq ft/person);

Space for EOF data system equipment needed to transmit data to other

locations;

* Sufficient space to perform repair, maintenance, and service of equipment, displays, and instrumentation;

* Space for ready access to communications equipment by all EOF personnel

who need communications capabilities to perform their functions;

* Space for ready access to functional displays of EOF data;

* Space for storage of plant records and historical data or space for

means to readily acquire and display those records; and

* Separate office space to accommodate at least five NRC personnel during

periods that the EOF is activated for emergencies.

19
The EOF working space shall be sized for at least 35 persons, including 25

persons designated by the licensee, 9 persons from NRC, and 1 person from FEMA.

This minimum size shall be increased if the maximum staffing levels specified

in the licensee's emergency plan, including representatives from State and local

agencies, exceed 25 persons.

4.5 Radiological Monitoring

To ensure adequate radiological protection of EOF personnel, radiation monitoring systems shall be provided in the EOF; These monitoring systems may be

composed of installed monitors or dedicated, portable monitoring equipment.

These systems shall continuously indicate radiation dose rates and airborne

radioactivity concentrations inside the EOF while it is in use during an

emergency. These monitoring systems shall include local alarms with trip levels

set to provide early warning to EOF personnel of adverse conditions that may

affect the habitability of the EOF. Detectors to distinguish the presence or

absence of radioiodines at concentrations as low as 10-7 microcuries/cc shall

be provided.

4.6 Communications

The EOF shall have reliable voice communications facilities to the TSC, the

control room, NRC, and State and local emergency operations centers. The normal

communication path between the EOF and the control room will be through the

TSC. The primary functions of the EOF voice communications facilities will

be:

EOF management communications with the designated senior licensee

manager in charge of the TSC,

* Communications to manage licensee emergency response resources,

* Communications to coordinate radiological monitoring,

* Communications to coordinate offsite emergency response activities,

and

* Communications to disseminate information and recommended protective

actions to responsible government agencies.

The EOF voice communications facilities shall include reliable primary and backup means of communication. Voice communications may include private telephones,

commercial telephones, radio networks, and intercommunications systems as appropriate to accomplish the EOF functions during emergency conditions. Existing

licensee communications systems may be used if the systems can be demonstrated

to be reliable under emergency conditions and if they are adequate to meet the

added EOF criteria. The licensee shall provide a means for EOF telephone access

to commercial telephone common-carrier services that bypasses any local telephone

switching facilities that may be susceptible to loss of power during emergencies.

The licensee shall ensure that spare commercial telephone lines to the plant

are available for use by the EOF during emergencies.

The EOF voice communications equipment shall include:

20
* Hotline telephone (located in the NRC office space) on the NRC emergency notification system (ENS) to the NRC Operations Center;

Dedicated telephone (located in the NRC office space) on the NRC health

physics network (HPN);

* Dedicated telephones for management communications with direct access

to the TSC and the control room;

* Dial telephones reserved for EOF use to provide access to onsite and

offsite locations;

* Intercommunications systems between work areas of the EOF, if needed,

for EOF functional performance or if the EOF is comprised of separate

functional areas or separate buildings;

* Radio communications to licensee mobile monitoring teams;

* Communications to State and local operations centers; and

* Communications to facilities outside the EOF used to provide supplemental support for EOF evaluations.

The EOF communication system shall also include designated telephones (in addition to the ENS and HPN telephones) for use by NRC personnel. The licensee

shall provide at least three dial telephone lines for such NRC use while the

EOF is activated. The licensee shall also furnish the access facilities and

cables to the NRC for the ENS and HPN telephones.

Facsimile transmission capability between the EOF, the TSC, and the NRC Operations Center shall be provided..

4.7 Instrumentation, Data System Equipment, and Power Supplies

Equipment shall be provided to gather, store, and display data needed in the

EOF to analyze and exchange information on plant conditions with the designated

senior licensee manager in charge of the TSC. The EOF data system equipment

shall perform these functions independently from actions in the control room

and without degrading or interfering with control room and plant functions.

EOF instrumentation, data system equipment, and power supplies need not meet

safety grade or Class 1E criteria. When signals to the EOF are received from

sensors providing signals to safety system equipment or displays, suitable

isolation in accordance with GUC 22, 23, and 24 shall be provided to ensure

that the EOF systems cannot degrade performance of the safety system equipment

of displays.

The EOF electrical equipment load shall not degrade the capability or reliability

of any safety-related power source. Circuit transients or power supply failures

and fluctuations shall not cause a loss of any stored data vital to the EOF

functions.

The total EOF data system shall be designed to achieve an operational unavailability goal of 0.01 during all plant operating conditions above cold shutdown

as described in Section 1.5.

21
The plant data processor (plant process computer) may provide, if stringent

conditions are met, the EOF data system functions or may have data for the EOF

system transmitted through it. In either case, the performance of the plant

data processor and its related instrumentation and equipment shall be included

when determining the EOF data system unavailability. In addition, the computational capacity and data throughput of the plant processor must be sufficient

to accommodate the combined computational and input-output loads of the EOF

system and the other functions being performed by the plant processor. EOF

data processed through the plant data processor shall be continuously available

to the EOF with the same reliability and accuracy required of a data system

designed to operate independent of the plant data processor. Use of the plant

data processor shall not degrade the integrity of data supplied to the EOF or

the security of the software used to process EOF data.

The SPDS display equipment used in the EOF need not be seismically qualified

and shall meet only the EOF data system equipment reliability and performance

criteria. This display is necessary for licensee corporate management and the

NRC Regional Director to communicate.more easily with the TSC or the control

room and to have a better understanding of the plant status. The design of

the EOF data -system equipment shall incorporate human-factors engineering with

consideration for both operating and maintenance personnel.

4.8 Technical Data and Data System

The EOF technical data system will receive, store, process and display information sufficient to perform assessments of the actual and potential onsite and

offsite environmental consequences of an emergency condition. Data providing

information on the general condition of the plant also shall be available for

display in the EOF for utility resource management.

The EOF data set shall include radiological, meteorological, and other environmental data as needed to:

* Assess environmental conditions,

* Coordinate radiological monitoring activities, and

* Recommend implementation of offsite emergency plans.

As a minimum EOF data set, sensor data of the Type A, B, C, D, and E variables

specified in Reg. Guide 1.97, Revision 2, and of those meteorological variables

specified in proposed Revision 1 to Regulatory Guide 1.23, "Meteorological

Measurements Programs in Support of Nuclear Power Plants," and in NUREG-0654,

Revision 1, Appendix 2, shall be available for display in the EOF. All data

that are available for display in the TSC, including data transmitted from the

plant to NRC, shall be part of the EOF data set.

The accuracy of data in the EOF must be consistent with the data accuracy needed

to perform the EOF functions. The accuracy of data displays in the EOF shall

be equivalent to that for the data displayed in the TSC. The time resolution

of data requisition shall be sufficient to provide data without loss of information during transient conditions. The time resolution required for each

sensor signal shall depend on the potential transient behavior of the variable

being measured. The EOF data displays of Reg. Guide 1.97 variables shall meet

the criteria for EOF data but need not meet the design and qualification

criteria in Reg. Guide 1.97 for display of those variables in the control room.

22
Data storage capability shall be provided for the EOF data set. At least 2 hours

of pre-event data and 12 hours of post-event data shall be recorded. The sample

frequency shall be chosen to be consistent with the use of the data. Capacity

to record at least two weeks of additional post-event data with reduced time

resolution shall be provided. Archival data storage and the capability to

transfer data between active memory and archival data storage without interrupting EOF data acquisition and displays shall be provided for all EOF data.

A sufficient number of data display devices shall be provided in the EOF to

allow all EOF personnel to perform their assigned tasks with unhindered access

to alphanumeric and/or graphical representations of:

* Plant systems variables,

In-plant radiological variables,

* Meteorological information, and

* Offsite radiological information.

Trend-information display and time-history display capability is required in

the EOF to give EOF personnel a dynamic view of plant systems, radiological

status, and environmental status during an emergency. The EOF displays shall be

designed so that callup, manipulation, and presentation of data can be easily

performed. The displays shall be partitioned to facilitate the retrieval of

information by the different functional groups in the EOF. This may be accomplished with either separate display units or by logically separated information display pages available on a callup basis at each data display unit. The

EOF data display formats shall present information so that it can be easily

understood by the EOF personnel operating the system. If display capabilities

for news media briefings are provided in the EOF, these displays shall be

separated physically from the EOF functional displays. Human-factors

engineering shall be incorported in the design of the EOF.

The SPDS shall also be displayed in the EOF. This duplication will provide

licensee management and NRC representatives information about the current

reactor systems status and will facilitate communications among the control

room, TSC, and EOF. If the SPDS system in the control room is composed of

multiple display units, multiple displays must'also be provided in the EOF.

4.9 Records Availability and Management

The EOF shall have ready access to up-to-date plant records, procedures, and

emergency plans needed to exercise overall management of licensee emergency

response resources. The EOF records shall include, but shall not be limited

to:

Plant technical specifications,

* Plant operating procedures,

Emergency operating procedures,

Final Safety Analysis Report,

* Up-to-date records related to licensee, State, and local emergency

response plans,

* Offsite population distribution data,

* Evacuation plans,

* Environs radiological monitoring records, and

Licensee employee radiation exposure histories.

23
and up-to-date'drawings, schematics and diagrams showing:

* Conditions of plant structures and systems down to the component level

and

* In-plant locations of these systems.

These records shall either be stored and maintained in the EOF (such as hard

copy or microfiche) or shall be readily available via transmittal to the EOF

from another records storage'location. The method of storage and presentation

of the EOF records shall ensure ease of access under emergency conditions.

The records available to the EOF shall be completely updated as necessary to

ensure currency and completeness.

5. SAFETY PARAMETER DISPLAY SYSTEM

5.1 Function

The purpose of the safety parameter display system (SPDS) is to assist control

room personnel in evaluating the safety status of the plant. The SPDS is to

provide a continuous indication of plant parameters or derived variables representative of the safety status of the plant. The primary function of the SPDS

is to aid the operator in the rapid detection of abnormal operating conditions.

The functional criteria for the SPDS presented in this section are applicable

for use only in the control room.

It is recognized that, upon the detection of an abnormal' plant status, it may

be desirable to provide additional information to analyze and diagnose the cause

of the abnormality, execute corrective actions, and monitor plant response as

secondary SPDS functions.

As an operator aid, the SPDS serves to concentrate a minimum set of plant parameters from which the plant safety status can be assessed. The grouping of parameters is based on the function of enhancing 'the operator's capability to assess

plant status in a timely manner without surveying the entire control room.

However, the assessment based on SPDS is likely to be followed by confirmatory

surveys of many non-SPDS control room indicators.

Human-factors engineering shall be incorporated in the various aspects of the

SPDS design to enhance the functional effectiveness of control room personnel.

The design of the primary or principal display format shall be as simple as

possible, consistent with the required function, and shall include pattern and

coding techniques to assist the operator's memory recall for the detection and

recognition of unsafe operating conditions. The human-factored concentration

of these signals shall aid the operator in functionally comparing signals in

the assessment of safety status.

All data for display shall be validated where practicable on a realtime basis

as part of the display to control room personnel. For example, redundant sensor

data may be compared, the range of a parameter may be compared to predetermined

limits, or other quantitive methods may be used to compare values. When an

unsuccessful validation of data occ'urs, the SPDS shall contain means of identifying the impacted parameter(s). Operating procedures and operator training

in the use of the SPDS shall contain information and provide guidance for the

24
resolution of unsuccessful data validation. The objective is to ensure that

the SPDS presents the most current and accurate status of the plant possible

and is not compromised by unidentified faulty processing or failed sensors.

The SPDS shall be in operation during normal and abnormal operating conditions.

The SPDS shall be capable of displaying pertinent information during steadystate and transient conditions. The SPDS shall be capable of presenting the

magnitudes and the trends of parameters or derived variables as necessary to

allow rapid assessment of the current plant status by control room personnel.

The parameter trending display shall contain recent and current magnitudes of

the parameter as a function of time. The derivation and presentation of parameter trending during upset conditions is a task that may be automated, thus

freeing the operator to interpret the trends rather than generate them. Display

of time derivatives of the parameters in lieu of trends to both optimize operatorprocess communication and conserve space may be acceptable.

The SPDS may be a source of information to other systems, and the functional

criteria of these systems shall state the required interfaces with the SPDS.

Any interface between the SPDS and a safety system shall be isolated in

accordance with the safety system criteria to preserve channel independence

and ensure the integrity of the safety system in the case of SPDS malfunction.

Design provisions shall be included in the interfaces between the SPDS and

nonsafety systems to ensure the integrity of the SPDS upon failure of

nonsafety equipment.

A qualification program shall be established to demonstrate SPDS conformance

to the functional criteria of this document.

5.2 Location

The SPDS shall be located in the control room with additional SPDS displays

provided in the TSC and the EOF. The SPDS may be physically separated from

the normal control board; however, it shall be readily accessible and visible

to the shift supervisor, control room senior reactor operator, shift technical

advisor, and at least one reactor operator from the normal operating area. If

the SPDS is part of the control board, it shall be easily recognizable and

readable.

5.3 Size

The SPDS shall be of such size as to be compatible with the existing space in

the control area. The SPDS display shall be readable from the emergency operating

station of the control room senior reactor operator. It shall not interfere

with normal movement or with full visual access to other control room operating

systems and displays.

5.4 Staffing

The SPDS shall be of such design that no operating personnel in addition to

the normal control room operating staff are required for its operation.

25
5.5 Display Considerations

The display shall *be responsive'to transient and accident sequences and shall

be sufficient to indicate the status of the plant. For each mode of plant

operation, a single primary display format designed according to acceptable

human-factors principles (a limited number of parameters or derived variables

and their trends in an organized display that can be readily interpreted by an

operator) shall be displayed, from which plant safety status can be inferred.

It is recognized that it may be desirable to have the capability to recall

additional data on secondary formats or displays.

The primary display may be individual plant parameters or may be composed of a

number of parameters or derived variables giving an overall system status.

The basis for the selection of the minimum set of parameters in the primary

display shall be documented as part of the design.

The important plant functions related to the primary display while the plant

is generating power shall include; but not be limited to:

Reactivity control

* Reactor core cooling and heat removal from primary system

* Reactor coolant system integrity

* Radioactivity control

* Containment integrity

The SPDS may consist of several display formats as appropriate to monitor and

present the various parameters or derived variables. For each plant operating

mode, these formats may either be automatically displayed or manually selected

by the operator to keep control room operating personnel informed. Flexibility

to allow for interaction by the operator is desirable in the display designs.

Also, where feasible, the SPDS should include some audible notification to alert

personnel of an unsafe operating condition.

The SPDS need not be limited to the previously stated functions. It may include

other functions that aid operating personnel in evaluating plant status. It is

desirable that the SPDS be sufficiently flexible to allow for future incorporation

of advanced diagnostic concepts and evaluation techniques and systems.

5.6 Design Criteria

.The total SPDS need not be Class 1E or meet the single-failure criterion. The

sensors and signal conditioners (such as preamplifiers, isolation devices, etc.)

shall be designed and qualified to meet Class 1E standards for those SPDS parameters that are also used by safety systems. Furthermore, sensors and signal

conditioners for those parameters of the SPDS identical to the parameters specified

within Reg. Guide 1.97 shall be designed and qualified to the criteria stated

in Reg. Guide 1.97. For SPDS application, it is also acceptable to have Class IE

qualified devices from the sensor to a post-accident-accessible location, such

as outside containment, and then non-lE devices from containment to the display

(or processor) on the presumption that these components can be repaired or

replaced in an accident envi onment. The processing and display devices of

the SPDS shall be of proven high quality and reliability.

26
The function of the SPDS is to aid the operator in the interpretation of tran- sients and accidents. This function shall be provided during and following all events expected to occur during the life of the plant, including earthquakes. To achieve this function, the display system shall not only take adequate'account of'human factors--the man-machine interface--but shall also be sufficiently durable to function during and after earthquakes. Because of current technology, it may not be possible to satisfy these criteria within one SPDS system.

From an operational viewpoint, it is preferred that only one display system be used for evaluating the safety status of the plant. One display system simpli- fies the man-machine interface and thus minimizes operator errors. However, in recognition of the restraints imposed by. current technology, an alternative is to design the overall SPDS function with a primary and a backup display system: (1) the primary SPDS display would have high performance and flexibility and be human factored but need not be seismically qualified; and (2) the backup display system would be operable during and following earthquakes, such as the normal control room displays needed to comply with Reg. Guide 1.97. The display system (or systems) provided for the SPDS function shall be capable of function- ing during and following all design basis events for the plant.

In all cases, both the primary SPDS display and the backup SPDS seismically qualified portion of the display shall be sufficiently human factored in its design to allow the control room operations staff to perform the safety status

assessment task in a timely manner. Dependence on poorly human-engineered Class 1E seismically qualified instruments that are scattered over the control board, rather than concentrated for rapid safety status assessment, is not acceptable for this -function. An acceptable approach would be to concentrate the seismically qualified display into one segment of the control board.

The dynamic loading limitations of the SPDS design shall be defined and incor- porated into the training program. The control room operations staff shall be provided with sufficient information and criteria to allow for performance of

an operability evaluation of SPDS if an earthquake should occur.

The SPDS as used in the control room shall be designed to an operational unavail- ability goal of 0.01, as defined in Section 1.5 of this document. The cold shutdown unavailability goal for the SPDS during the cold shutdown and refueling modes for the reactor shall be 0.2, as defined in Section 1.5.

Technical specifications shall be established to be consistent with the unavail- ability design goal of the SPDS and.with the compensatory measures provided during periods when the SPDS is inoperable. Operation of the plant with the

SPDS out of service is allowed provided that the control board is sufficiently human factored to allow the operations staff to perform the safety status

assessment task in a timely manner. Dependence on poorly human-engineered instruments that are scattered over the control board rather than concentrated for rapid safety status assessment is not acceptable for this function.

6. NUCLEAR DATA LINK

6.1 Function

When a significant incident occurs'at a nuclear power plant, the NRC will activate the Executive Team (ET) at the NRC Operations Center to oversee the agency

27
response. The ET for reactor events consists of the Director of the NRC response

(Chairman or designated alternate), the Executive Director for Operations, the

Director of the Office of Inspection and Enforcement, and the Director of the

Office of Nuclear Reactor Regulation. When the ET is activated, the Regional

Director and Regional support staff leave immediately for the affected site,

and a headquarters technical support group is called in to provide assistance

to the ET and to NRC site personnel.

The primary role of each of these components of the NRC Incident Response Program is to monitor the event, independently evaluate the situation, provide

advice and assistance to the licensee and offsite authorities, and inform

officials and the general public about the radiological conditions on site and

around the facility and the physical condition of facility.

Until the Regional Director (or other designated senior NRC official) arrives

at the site, the NRC Operations Center must carry out the roles described above.

When the Regional Director or other designated senior NRC official arrives at

the site, it is contemplated that responsibility for managing the NRC operations

in and around the plant will be transferred to that individual at the site

(i.e., NRC Director of Site Operations).

After the responsibility for managing the NRC site operations has been transferred to the Director of Site Operations, the headquarters technical support

groups will provide direct support to him by continuing to evaluate information provided by site personnel. In addition, certain key decisions, particularly those relating to recommendations for actions affecting the general public

and those involving changes in the NRC's role in responding to the accident,

may remain with the Director of the NRC response. The NRC role will not extend

to any manipulation of nuclear power plant controls nor will it normally include

directing licensee actions. However, in extreme cases, NRC may direct that

certain operations be performed by the licensee at the nuclear plant. In such

an unlikely situation, it is expected that any direction from NRC would be

provided to licensee management from the Director of Site Operations after his

arrival onsite or from the Director of NRC response (Chairman or designated

alternate) prior to that time. (A more detailed description of the manner in

which NRC will respond to significant incidents can be found in NUREG-0728,

"Report to Congress: NRC Incident Response Plan," and in NUREG-0730, "Report

to Congress on the Acquisition of Reactor Data for the NRC Operations Center".)

To fulfill these functions of providing support, NRC must have reliable and

-timely data from the nuclear power plant. This will be obtained through a

nuclear data link (NDL), a data transmission system designed to send a

specified set of variables from the plant to the NRC Operations Center.

6.2 Description

The nuclear data link (NDL) processes and transmits certain reactor process

variables, and radiological and site meteorological data from each operating

nuclear power plant to the NRC Operations Center. The NDL system is comprised

of a data acquisition system, an NDL terminal (both of which are located on

site), and an Operations Center system at NRC headquarters. Figure'l shows a

block diagram of how the NDL could be connected to the emergency response data

acquisition system and is explained in the following paragraphs.

28
ONSITE OFFSITE

COMMUNICATIONS

LINK

REACTOR SITE

ISOLATED

i, - INPUTS

to FROM PLANT

SENSORS

DATA

ACQUISITION

SYSTEM

NDL

TERMINAL

OPERATIONS

CENTER

COMPUTER

NRC OPERATIONS CENTER

Figure 1. NDL System Overview
The data acquisition system (DAS) acquires data for the variables listed in

Reg. Guide 1.97, Rev. 2, and Reg. Guide 1.23 and also may include other sitespecific variables for transmission to the TSC, EOF, and SPDS.as determined by

the licensee. The DAS also has Reg. Guide 1.97 data available to be transmitted

to the NRC Operations Center over the NDL and to vendors and State or local

authorities over other data links. Reg. Guide 1.97 information currently lists

approximately 60 variables, depending on whether a PWR or BWR facility is being

considered. The OAS performs multiplexing of incoming signals and conversion

of raw data into engineering units. The data are scaled and time tagged appropriately and converted into a standardized, digital format for transmission.

Sensor sampling by the DAS and data transmission to the NDL terminal must occur

at intervals of not greater than one minute. The analog-to-digital conversion

performed on the input data transmitted shall have 12-bit resolution. Each

reading shall be time tagged.

A data-access approach discussed in Appendix E of NUREG/CR-1451 may be used

for transients. With that approach, the peak value and time integral of the

transient are captured, digitized, formatted, and transmitted at one-minute

intervals.

An NDL terminal at the plant may accept data from the DAS and transmit it to

the NRC Operations Center. The terminal would handle the communications protocol

as well as error detection and correction. The NDL terminal hardware and software would be a standardized unit specified by the NRC. Specification for this

unit would be developed as a part of the NDL system design.

The Operations Center system makes.data obtained from the licensee facility

available for viewing in the NRC Operations Center. Facilities for retention

of data will exist at the NRC Operations Center. The Operations Center subsystem, as presently envisioned, will include a general-purpose computer that

is capable of receiving data from any plant. Video data terminals, printers,

magnetic memory storage, and miscellaneous Peripherals will comprise the balance of the equipment at the NRC Operations Center. The peripherals provide

the man-machine interface to access and display numerical and graphical representations of parametric data and provide data storage capabilities. The computer may be used to maintain a file of current data from each reactor site.

When an incident occurs, long-term data retrieval and storage begins in the

NRC Operations Center. Stored data from at least a 2-week period shall be

available for recall and display, as well as for analysis and verification by

NRC personnel.

6.3 NDL Interface

The interface between the data acquisition system and the NDL will require the

use of a common communications protocol, to be defined later.

6.4 Environment

The DAS and the NDL interface shall meet the same environmental specifications

that apply to the onsite technical support center. Power supply for the

acquisition system and formatting equipment shall be high-reliability non-Class

1E power that is backed by battery power to eliminate momentary interruptions.

30
The licensee is responsible for the correction of any failure that results in

degraded plant data being delivered to the NDL communications link at the specified intervals.

7. ACQUISITION AND CONTROL OF TECHNICAL DATA

7.1 Sources of Technical Data

Parameters specified in Reg. Guide 1.97, Rev. 2, and Reg. Guide 1.23 shall be

provided to the data acquisition system (DAS). Isolation devices are needed

for all signal interfaces with safety systems to prevent interference, degradation, or.damage to any element of the safety system as specified in General

Design Criterion 24, "Separation of Protection and Control Systems," and IEEE

Standard 279-1971, Section 4.7, "Control and Protection System Interaction."

The signals may be provided at a control room interface or input connection to

the process control computer. These inputs shall not be processed by a softwareprogrammable device, or any device controlled indirectly by software, before

entering the DAS except for data received in accordance with Reg. Guide 1.23.

7.2 Acquisition of Data

Examples of data acquisition and distribution systems are shown in Figures 2

and 3 of this document. The configuration in Figure 3 is the anticipated data

acquisition system that will be implemented. If the conditions of Section 2.8

are met, the.configuration shown in Figure 2 could be acceptable. All inputs

that interface with safety system signals must be isolated by an isolation

device prior to connection to the DAS.

7.3 DAS Functional Limitations

The DAS must not be subject to external demands for processing or services that

could degrade the needed reliability under accident conditions and must not be

interrupted, delayed, or in any way impeded or degraded in its function by any

such external demands or software installation or changes in any plant equipment. The only exception is the system's internal calibration and selfdiagnostic routines.. Output data from the DAS must be consistent with readings

observed by the operators in the control room. To achieve this objective,

verification and validation tests shall be performed to assure correlation of

data obtained from each source.

7.4 DAS Design, Verification, and Configuration Control

Because the data acquisition system may be the basic source of data for all of

the emergency facilities, its hardware and software configurations and changes

shall be verified for reliability. Tests to demonstrate'and evaluate the

integrity of software and the integrated system are needed. These tests should

be performed with the system operating continuously on live input signals in

addition to satisfactory performance of static and dynamic test cases.

31
AM)

OPERATIONS I LO

FACILITY ~ Il N IY ~ CI;

____ ____ ____ j N C ~VENDORS EOPFPRAIN STATE AGENCIES

UrUNCTIONAL DISPLAYS' CENTER |.OCAL L AGENCIES | Fgrni P s Comptioer.1

Figure 2. Example of a Functional Block Diagram of Data Flow Using Plant Process Computer.
. 1!

U)

Figure 3. Example of Functional Block Diagram Flow Without Using Plant Process Computer.
The following are the primary criteria for qualification of changes in the DAS:

(1) The original development and subsequent changes are to be performed in

accordance with documented quality assurance procedures that are to be

available for review by the NRC staff.

(2) The original software and subsequent modifications are to be subjected to

static and dynamic test programs to verify performance. Once the system

becomes operational, all subsequent software changes and modifications

must undergo static and dynamic tests to verify performance. After the

performance has been verified, the software may be transferred to the DAS

in accordance with an approved DAS update procedure.

These types of criteria were used to ensure software reliability in Position

19 of NUREG-0308, "Safety Evaluation Report Related to Operation of Arkansas

Nuclear One, Unit 2," Rev. 1 and supplements.

The criteria for qualification of the DAS describe the changes on DAS operation

and its effect on compatibility with the NDL. Records shall be kept of the

date a particular change was implemented.

7.5 DAS Reliability

The data acquisition system shall provide data access for the SPDS, TSC, and

EOF, as well as the NDL. Therefore, high DAS reliability is paramount to achieve

accurate and dependable.information on a continued basis. A moderate amount

of excess capacity and the capability to expand modularly should be included

to allow modest increases in parameter monitoring without serious impact on

the system.

8. EMERGENCY RESPONSE FACILITY INTEGRATION

During emergency conditions, it is essential that there be a continuous high

level of interaction and communications among key personnel in the control room,

emergency response facilities, and NRC to ensure that all emergency actions

are fully understood and coordinated.

The foregoing emergency response facilities (ERFs) are developed to function

as an integrated system. The licensee's ERFs shall be designed to provide

coordinated support to the control room during emergency operating conditions.

These facilities shall be integrated into the licensee's emergency plan at each

site to facilitate coordination with State and local emergency response facilities.

The systems design of the ERFs shall ensure that the following functional criteria

f each-facility are satisfied:

* The operation of any system or subsystem within the licensee's ERFs

shall not degrade the performance or reliability of any reactor safety

or control system or of any safety-related displays in the control

room.

* Actions in the control room and operation of control room systems

shall not degrade or interfere with the functional operation of ERF

systems.

34
Normal operation of any system or subsystem in the ERFs shall not

degrade or interfere with the functional operation of other systems

in those facilities.

The DAS hardware and software shall be protected against unauthorized

manipulation of or interference with input signals, data processing,

data storage, and data output.

The ERF data system may be a fully or partially integrated data-processing system serving all emergency response facilities and systems. Alternatively, the ERF

data system may be comprised of multiple data-processing units serving individual

parts of the ERFs or providing separate functions.

Regulatory-Guide 1.97, Revision 2, establishes criteria for accident-monitoring

instrumentation to be displayed in the control room. The minimum data set that

shall be available for display and use in the TSC and EOF shall include the

following:

Type A, B, C, D, and E variables specified in Reg. Guide 1.97;

Meteorological variables specified in Reg. Guide 1.23 and NUREG-0654,

Revision 1, Appendix 2; and

Variables displayed by the SPDS.

The acquisition and transmission of data of Reg. Guide 1.97 variables to the

TSC and EOF need not meet the Reg. Guide 1.97 design and qualification criteria

for display of that data-in the control room.

Signals for ERF systems may be received from sensors providing signals to safet3

related systems. Suitable isolation devices must be used to ensure that the

ERF systems cannot degrade performance of the reactor safety systems. The ERF

data systems need not be safety-grade systems beyond the device providing

isolation from safety-related systems.

9. VERIFICATION AND VALIDATION CRITERIA

The design, development, qualification, and installation of the SPDS, TSC, EOF,

and NDL facilities and systems shall be independently verified and validated

by qualified personnel other than the original designers and developers. The

independent verification and validation of these facilities are needed to provide assurance that highly reliable and available systems will be implemented

for all plant facilities. The licensee's quality assurance organization may

be used for the verification and validation program if it meets the independence

criteria and is technically capable of performing these functions.

Because the SPDS, TSC, and EOF are important elements in the capability of a

nuclear power plant to respond to an emergency, limiting conditions for operation in the plant technical specifications shall be established to specify

35
compensating actions to be taken by the licensee when the SPDS, TSC, and EOF

are not operational. Reportable outage periods under the technical specification shall include a report on compensatory measures, such as additional staffing, taken during the time the SPDS, TSC, EOF, or NDL is not operational.

The plant technical specifications shall include surveillance requirements to

determine the operability of the ERFs. The SPDS, TSC, OSC, EOF, and NDL facilities shall be designed to provide for periodic testing to diagnose and recognize

component degradation and systems malfunction.

10. BIBLIOGRAPHY

1. Letter from H. R. Denton, NRC, to All Operating Nuclear Power Plants,

Subject: Discussions of Lessons Learned Short-Term Requirements, dated

October 30, 1979.*

2. Letter from D. G. Eisenhut, NRC, to All Operating Nuclear Power Plants,

Subject: NRC Nuclear Data Link (NDL), dated March 12, 1980.*

3. Letter from D. G. Eisenhut, NRC, to All Power Reactor Licensees, Subject:

Clarification of NRC Site Requirements for Emergency Response Facilities

at Each Site, dated April 25, 1980.*

4. U.S. Nuclear Regulatory Commission, "Safety Evaluation Report Related to

Operation of Arkansas Nuclear One, Unit 2," USNRC Report NUREG-0308,

November 1977, Supplement 1, March 1978. (Available from NTIS only.)

5. U.S. Nuclear Regulatory Commission, "TMI-2 Lessons Learned Task Force

Status Report and Short-Term Recommendations," USNRC Report NUREG-0578,

July. 1979.**

6. U.S. Nuclear Regulatory Commission, "TMI-2 Lessons Learned Task Force

Final Report," USNRC Report NUREG-0585, August 1979.**

7. U.S. Nuclear Regulatory Commission, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of

Nulcear Power Plants," USNRC Report NUREG-0654, Rev. 1, November 1980.***

8. U.S. Nuclear Regulatory Commission, "NRC Action Plan Developed as a Result

of the TMI-2 Accident," USNRC Report NUREG-0660, Vols. 1 and 2, May 1980.***

9. U.S. Nuclear Regulatory Commission, "Report to Congress: NRC Incident

Response Plan," USNRC Report NUREG-0728, September 1980.**

10. U.S. Nuclear Regulatory Commission, "Report to Congress on the Acquisition

of Reactor Data for the NRC Operations Center," USNRC Report NUREG-0730,

September 1980.**

36
11. U.S. Nuclear Regulatory Commission, "Clarification of TMI Action Plan

Requirements," USNRC Report NUREG-0737, November 1980.***

12. U.S. Nuclear Regulatory Commission, "Standard Review Plan

of Safety Analysis Reports for Nuclear Power Plants - LWR

Report NUREG-75/087 Section 6.4, "Habitability Systems," (Available from NTIS only.)

for the Review

Edition," USNRC

Rev. 1.

13. U.S. Nuclear Regulatory Commission, "Conceptual and Programmatic Framework

for the Proposed Nuclear Data Link," prepared by Sandia National Laboratories,

USNRC Report NUREG/CR-1451, April 1980.**

14. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.23, "Meteorological

Measurement Programs in Support of Nuclear Power Plants," proposed Revision 1.t

15. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.97, "Instrumentation

for Light-Water-Cooled-Nuclear Power Plants to Assess Plant and Environs

Conditions During and Following an Accident," Revision 2.t

16. 10 CFR Part 50, General Design Criterion 19, "Control Room."*

17. 10 CFR Part 50, General

and Control Systems."*

Design Criterion 24, "Separation of Protection

*Available in the NRC Public Document Room for inspection and copying for a fee.

**Available for purchase from the NRC/GPO Sales Program, U.S. Nuclear Regulatory

Commission, Washington, DC 20555, and the National Technical Information Service,

Springfield, VA 22161.

***Available free upon written request to the Division of Technical Information and

Document Control, U.S. Nuclear Regulatory Commission, Washington, DC 20555.

tAvailable from the NRC/GPO Sales Program, U.S. Nuclear Regulatory Commission,

Washington, DC 20555, Attention: Regulatory Guide Account.

37
NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER (Assignedby DDC

(7-77)

BIBLIOGRAPHIC DATA SHEET NUREG-0696

4. TITLE AND SUBTITLE (4dd Volume No., if appropria te) 2. (Leave blank)

Functional Criteria for Emergency Response Facilities

3. RECIPIENT'S ACCESSION NO.

7. AUTHOR(S) 5. DATE REPORT COMPLETED

Safety Data Integration Group MONTH |YEAR

Finhrl |ry 1iQAl

9. PERFORMING ORGANIZATION NAME AND MAILING ADDRESS (Include Zip Code) * DATE REPORT ISSUED

MONTH IYEAR

Safety Data Integration Group MONTH Ml

U.S. Nuclear Regulatory Febraryiss

Washingotn, D. C. 20555 6 ~aebak

8. (Leave blank)

12. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS (Include Zip Code) 10. PROJECT/TASK/WORK UNIT NO.

Office of Inspection and Enforcement

U. S. Nuclear Regulatory Commission 11. CONTRACT NO.

Washington, D. C. 20555

13. TYPE OF REPORT PERIOD COVERED (Inclusive dates)

Technical Report

15. SUPPLEMENTARY NOTES 114. (Leave blank)

16. ABSTRACT emOO words or less)

This report -describes the facilities and systems to be used by nuclear power plant

licensees to improve responses to emergency situations. The facilities include the

Technical Support Center (TSC), Onsite Operational Support Center (OSC), and

Nearsite Emergency Operations Facility (EOF), as well as a brief discussion of the

emergency response function of the control room. The data systems described are the

Safety Parameter Display System (SPDS) and Nuclear Data Link (NDL). Together, these

facilities and systems make up the total Emergency Response Facilities (ERFs).

Licensees should follow the guidance provided both in this report and in NUREG-0654

(FEMA-REP-1), Revision 1, for design and implementation of the ERFs.

17. KEY WORDS AND DOCUMENT ANALYSIS 17a. DESCRIPTORS

17b. IDENTIFIERS/OPEN-ENDED TERMS

18. AVAILABILITY STATEMENT 19. SECURITY CLASS (This report) 21. NO. OF PAGES

Unclassified

..20SECURITY page k 2LABS 2. 2Th PRICE Unlimited ncassi le S

N RC FORM 335 (7-77)