ML20032C865
| ML20032C865 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/06/1981 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0696, RTR-NUREG-0737, RTR-NUREG-696, RTR-NUREG-737, TASK-3.A.1.2, TASK-TM JPN-81-89, NUDOCS 8111110824 | |
| Download: ML20032C865 (33) | |
Text
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e POWER AUTHORITY OF THE STATE OF NEW YORK 10 CoLUMeus CIRCLc NEW YORK. N. Y.1o019 (212) 397 6200 G E O RG,E,,T 5,E,R R Y p
Cwit P rR u s t E t s JOHN BOSTO JOHN S DYSON C w ais u a no pngsi noCEDURES JOSEPH R. SCHMIEDER v Cs Csease aN
- "J;n:7...,
RICH ARD M. P LY N *d g n g n,g g,
Mo ERri M w.ONai November 6, 1981 EoWC<'*$ive<c PREDEmicic R, cL A R ec JPN-81-89 c e'r7/a ''''
THOM AS R FREY l'.'.'U.1 "'.".' 6 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Darrell G.
Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
.-\\f* l.I'V ',
Subject:
James A.
FitzPatrick Nuclear Power Plant
, g/
Docket No. 50-333 4
//
Conceptual Design for James A. FitzPatrick i
Emergency Response Facilities
' JPj
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References:
- 1. Letter from Darrell G. Eisenhut (NRC) b.
N to All Operating Nuclear Power Plants, 7
y dated February 18, 1981 k
j
- 2. Letter from William J. Dircks (NRC)
- Q ag l
to Mr. Stephen H. Howell (AIF),
dated August 10, 1981
Dear Sir:
l In response to your letter dated February 18, 1981 l
(Reference 1), the Power Authority submits the attached document entitled, " Conceptual Deisgn for James A. FitzPatrick Emergency Response Facilities."
The facility described in this report was designed to
- ~
meet the intent of NUREG-0696, " Functional Criteria for Emergency l
Response Facilities," and NUREG-0737 Item III.A.1.2, " Upgrade l
of Emergency Support Facilities," to improve the ability of the James A.
FitzPatrick Plant to respond in emergency situations.
It 4
should be noted that this report does not specifically address l
either the SPDS or NDL as clarified by Reference 2.
The Authority is in the process of developing a functional specification for the upgrading of the technical data system to incorporate the requirements of NUREG-0696 in the Control Room (CR), Technical Support Center (TSC) and the Emergency Operations Facility (EOF).
8111110824 811106 64 PDR ADOCK 03000333 j j h F
PDR l
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. A formal implementation schedule detailing planned modifications will be provided to you as soon as a functional specification is completed.
We expect this schedule to be available in the first quarter of 1982.
Should you or your staff have any questions, please contact us.
Very truly yours,
.%w
=
Senior Vice President Nuclear Generation attachments cc:
Mr.
J.
Linville Resident Inspector U.
S.
Nuclear Regulatory Commission P.
O.
Box 136 Lycoming, New York 13093 Mr. Ron Barton United Engineers & Constructors, Inc.
30 S.
17th Street Philadelphia, Pa.
19101
c ATTACHMENT I CONCEPTUAL DESIGN FOR JAMES A.
FITZPATRICK EMERGENCY RESPONSE FACILITIES Power Authority of the State of New York James A. FitzPatrick Paclear Power Plant Docket No. 50-333
__ _j
TABLE OF CONTENTS I.
INTRODUCTION II.
TECHNICAL SUPPORT CENTER (TSC)
A.
LOCATION / SIZE B.
STRUCTURE i
C.
HABITABILITY D.
COMMUNICATIONS j
E.
STAFFING AND TRAINING i
F.
TECHNICAL DATA SYSTEM G.
POWER SUPPLIES H.
RECORDS AVAILABILITY / MANAGEMENT III.
OPERATIONAL SUPPORT CENTER (OSC)
A.
LOCATION / SIZE B.
STAFFING C.
COMMUNICATIONS IV.
EMERGENCY OPERATIONS FACILITY (EOF)
A.
LOCATION B.
HABITABILITY C.
DATA SYSTEM D.
SIZE E.
TRAINING F.
RECORDS AVAILABILITY / MANAGEMENT G.
COMMUNICATIONS
-i-
, TABLE OF CONTENTS (continued)
V.
EMERGENCY RESPONSE DATA SYSTEM (ERDS)
A.
CONTROL ROOM INFORMATION SYSTEM (CRIS)
B.
TECHNICAL SUPPORT CENTER INFORMATION SYSTEM (TSCIS)
C.
EMERGENCY OPERATIONS FACILITY INFORMATION SYSTEM (EOFIS) uI.
PROJECTED IMPLEMENTATION SCHEDULE VII.
RE FE REh2S LIST OF FIGURES FIGURE 1.
ADMINISTRATION BUILDING el. 286'-0" (TSC)
FIGURE 2.
ADMINISTRATION BUILDING el. 300'-0" (CR)
FIGURE 3.
INTAKE / OUTLET VENTILATION DUCTS - ADMINISTRATION BUILDING FIGURE 4.
CONCEPTUAL EMERGENCY RESPONSE DATA SYSTEM (E RDS)
I
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i l
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I.
INTRODUCTION This document describes the Authority's conceptual Design of the Emergency Response Facilities (ERF) provided to respond to a potential emergency at James A.
FitzPatrick Nuclear Power Plant.
The conceptual design provided herein addresses the guidelines in NUREG-0696.
This conceptual design has been prepared based on current technology.
It should be noted that many efforts to optimize the design for the ERF's are currently being undertaken by the industry.
It is the Authority's intent to keep abreast of these trends in technology and factor new developments into the FitzPatrick design as applicable.
For example:
Human Factor Evaluations of various display concepts are presently being conducted by the BWR Owners' Group.
The Authority will utilize the results of these evaluations in implementing the best design applicable to the JAF Facility.
Accordingly, the design approach described in this document may be subject to change.
It is the intent of the Authority to upgrade the interim facilities to the requirements of NUREG-0696.
Accordingly, the Emergency Response Facilities currently in operation have been included in this document along with a description of the proposed design to comply with the above mentioned criteria.
This document will describe both the items that have been implemented and the actions required.
The FitzPatrick design will utilize a separate processing system to provide the ability to gather, store, and display data required for the Technical Support Center (TSC), Control Room (CR), and the Emergency Operations Facility (EOF).
In conjunction with meeting the requirements of NUREG-0696, the processing system will be designed to allow the option of phasing out the present process computer and incorporating the process computers functions into the new system.
Based upon this approach, the schedule for full implementation of NUREG-0696 may require an extension. __
m II.
TECHNICAL SUPPORT CENTER (TSC)
The Technical Support Center (TSC) has been established on the second floor of the Administration Building (E L. 286'-0") as shown in Figure 1.
The requirements of NUREG-0696 for the TSC have been implemented with the exception of a ventilation system that includes high-efficiency particulate air and charcoal filters.
The ventilation system upgrade will be 4
campleted by October 1982.
The following is a detailed description of the TSC, and the equipment provided therein:
A.
Location / Size The area designated as the Technical Support Center (TSC) is detailed in Figure 1.
The space provided for the TSC consists of the lunch area, assembly area and adjacent hallways.
Sufficient floor space (Approx. 1962 sq. ft.) is available in this area for the required personnel (Approx. 20) and equipment necessary to perform the required TSC functions.
The following equipment designations are included for the TSC work sreas:
1.
Data System Equipment 2.
Communications Equipment 3.
Document Storage 4.
Private NRC Consultation Rooms The location of the Technical Support Center (TSC) is within 100 feet of the JAF Control Room (Figure 2.) and can easily be reached by personnel within two minutes.
There are no major security barriers between these two facilities other than one access control station.
Radiological, structural and biological requirements important to long-range human occupancy have been included in the design of the TSC facility. - -
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B.
Structure The Technical Support Center (TSC) is located in the Administration Building which houses the offices and work areas of the plant operating personnel.
This building is situated between the 3eactor Building and the Turbine Building.
Included in the Administration Building structure is the Main Control Room for plant operation.
The Contaol Room (including external access) is a seismic Class I structure while the Administration Building housing the ":phnical Support Center (TSC) is a seismic Class II structure.
The portion of the seismic Class II structure housing the Control Room is designed to meet the TSC and seismic Class I structural requirements. An analysis was performed which ensures that any deflection, translation, or other movement of that part of the structure would not adversely affect the fenction of the seismic Class I Control Room.
The design tur the seismic Class I structure is based on dynamic analysis using acceleration response spectrum curves which were normalized to ground motion of 0.089 for the Operating i
Basis Earthquake (OBE), and 0.159. for the Design Basis Earthquake (DBE) as defin?d in the JAF FSAR Sections 12.4.6.1 & 12.4.6.2.
The structural loading conditions are the same as presented in FSAR Section 12.4-1 & 12.4-2 including foundation bearing loads, dead loads, wind I
loads and tornado loads.
As far as potential TSC flooding is concerned, the yard grade surrounding the plant, el. 271.5' is well above the maximum possible flood level developed for the site.
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C.
Habitability A Radiation Study and Ventilation Study were completed at FitzPatrick which documentated that the Technical Support Center (TSC) will be habitable according to all applicable criteria presented in NUREG-0696.
The detailed results of the studies are as following:
Radiation Study -
As a result of the shielding review, no modifications were required to maintain the habitability of the TSC.
The TSC will have a safe and low radiation level at all times.
The TSC is provided with dedicated portable area monitors and particulate detectors with both indication and alarm functions.
Ventilation System Study -
The Technical Support Center (TSC) will be provided with High Efficiency Particulate Air (HEPA) filters and charcoal absorbers to insure TSC habitability by maintaining air quality and limiting particulate effluent mitigation.
The Administration Building air intakes utilize dual intakes with inlets located as shown on Figure 3.
Separated by a distance of approximately 65 feet, the dual inlets provide excellent deterrence to contamination from radioactive emission.
The TSC Ventilation system filter train will insure minimal airborne radiation levels through the following operations; In the event of a radioactive release, a filter train consisting of a heater, prefilter, HEPA and charcoal filters and a 3000 scfm fan, will be manually activated by a selector switch.
This fan circulates the air within the Administration Building pressure boundary. _ _,
while a fan on the HEPA filter gyntcm will Edd filtered cir to give a positivo precoure differential of 1/8" water gauge within the boundaries of the 1st, 2nd and 3rd floors of the Administration Building including the TSC, relative to the surrounding areas.
(See Figures 1. & 2.)
To maintain the prescribed areas at this design pressure, the exhaust and return system in the Administration Building will be manually shut off when the filter system goes into operation.
In addition to built-in Heating, Ventilation and Air Conditioning (HVAC) modifications, provisions have been made for self-contained breathing apparatus availability to personnel in and traveling between the Control Room and Technical Support Center (TSC).
The availability of these items are as follows:
A total of seven (7) self-contained breathing apparatus will be located within the JAFNPP Control Room to assure immediate availability to the emergency crew.
A minimum of twenty (20) additional self-contained breathing apparatus and forty (40) spare bottles are maintained at various other locations and would be accessible by the TSC personnel. - -
FIGURE 3 ADMINISTRATION BUILDING HVAC INTAKE / OUTLET DUCTS LOCATION a.
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D.
Communications The Technical Support Center Communications Equipment will include:
A page/ party system and a sound-powered telephone system to allow point-to-point and multi-point conversations between the TSC, Control Room and other areas in the plant.
A dial telephone system to onsite and offsite locations for point-to-point and multi-point conversations.
A dedicated communication link from the TSC to the:
1.
Authority Headquarters 2.
NRC 3.
Control Room
- 4.
- 5.
- j I
6.
Local County Emergency Operations Center
- 7.
County Warning Point
- 8.
State Warning Point
- 9.
NYS Office of Disaster Preparedness
- 10.
NYS Department of Health
- 11.
NMPNS Control Room
- 12.
NMPNS Technical Support Center *
1.
Control Room l
2.
TSC 3.
Radiological survey teams 4.
County Sheriff's office 1
Facsimile transmission capability b2 tween the TSC, EOF, and State of New York Bureau of Radiological Health.
E.
Staffing and Training As specified in the James A. FitzPatrick Emergency Plan, the TSC will be staffed by members of the plant technical services organization, General Electric technical personnel and other contract and Headquarters office technical personnel as required.
This staff will be directed by the Emergency Director who will normally be the Resident Manager.
Other senior members of the TSC staff will act as the Technical Support Center Leader if the Emergency Director is not available.
The specific general functions of the FitzPatrick TSC staff include:
1.
Provide guidance to Control Room operating personnel.
2.
Provide plant systems support for management personnel in the EOF during recovery operations.
3.
Communicate with other emergency response centers.
4.
Provide direction to emergency coordinators.
5.
Make recommendations to EOF and offsite agencies regarding protective actions.
6.
Function as the primary information source to the EOF and the NRC for plant operations.
7.
Analysis and resolution of thermodynamic and thermal hydraulic problems 8.
Analysis of problems involving mechanical, electrical, instrument or control systems and development of solutions.
9.
Design and coordination of short-term modifications.
10.
Development of guidance regarding plant conditions for emergency directvr and operations functions. -
11.
Assistance in formulating procedures End instructions as needed for emergency operations.
12.
Resolution of questions concerning operating license requirements with NRC Representatives.
As soon as practical after declaring an emergency condition, the Emergency Director shall attempt to determine what staffing arrangements are necessary to maintain an ongoing emergency organization.
The Emergency Director or his designee will then develop a schedule for emergency response facility staffing in the TSC.
The level of staffing of the emergency response facilities may be varied by the Emergency Director as necessary to optimize assessment, mitigation or recovery operations.
The Emergency Director has the authority to limit or restrict access to the control room and/or TSC as necessary to assure that the intended functions of these facilities are not impaired.
Emergency Directors and Emergency Coordinators receive initial and annual training in the overall Emergency Plan and Implementing Procedures in detail adequate to ensure complete understanding of individual roles in the integrated response to emergencies.
They will partic pate in annual drills and exercises.
They will be cross-trained in specific functional responsibilities.
Emergency coordination personnel will be trained in the following topics:
1.
Emergency Plan implementation 2.
Classification of emergency conditions 3.
Notifications 4.
Personnel accountability _ _ _
5.
Rostricted area evccuation 6.-
Site evacuation 7.
Emergency Response Facilities F.
Technical Data System Until the implementation of the Emergency Response Data System is completed, as described in Section V, the TSC will have access to the Process Computer Data via the following equipment:
1.
Duplication of Control Room alarm and/or demand video monitors.
2.
Hard copy, high speed, printout of any of special pre-formatted emergency logs upon demand.
3.
Optional video display of emergency logs.
4.
Continuous trend recording of any two process computer analog inputs.
G.
Power Supplies The Technical Support Center (TSC) will meet its power requirements through the existing power control station in the Administration Building.
If this source is found to be inadequate, an additional motor control center will be installed and dedicated to the TSC function.
H.
Records Availability / Management The Technical Support Center will have a complete and up-to-date set of plant records, and procedures in the form of microfiche, aperture cards or hard copy records.
Necessary reproduction and display equipment will be available in the TSC to provide hard copy of any existing records to personnel in the Technical Support Center. _
Existing document control proctduros will be codified to esdure that updated copies of records and procedures are stored in the document area of the Technical Support Center.
The following documentation items will be available in the TSC:
1.
Emergency Plan and Implementing Procedure 2.
Copies of the Technical Specifications and their Basis, Operating Procedures, Special Procedures and Emergency Operating Procedures.
3.
Final Safety Analysis Report (FSAR) 4.
Documentation from the Automated Records Management System (ARMS) 5.
Plant Operations Review Committee Meeting Minutes 6.
Drawings, schematics and diagrams showing the condition of plant structure and systems 7.
Off-site dose estimate calculator l
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III.
OPERATIONAL SUPPORT CENTER The Operational Support Center has been established in the Control Room viewing area and meets the requirements of NUREG-069 6 :
A.
Location / Size The Operational Support Center location in the viewing gallery of the Control Room shares the Control Room Heating, Ventilation and Air Conditioning (HVAC)
Facilities.
Sufficient space is available for shift personnel to assemble and be assigned or assume duties in support of emergency operations.
Communications equipment necessary to control activities is also available.
This facility will be activated for Alert, Site Area Emergency, or General Emergency situations.
Access is thereby limited to the Control Room to those support personnel specifically required by the Shift Supervisor.
B.
Staffing I
As soon as practical after declaring an emergency condition, the Emergency Director Will determine what staffing arrangements are necessary to maintain an ongoing emergency organization.
The Emergency Director or his designee will then develop a schedule for emergency response facility staffini, in the OSC and TSC. -
C.
Communications Operational Support Center (OSC) communications facilities will be established to meet the requirements of NUREG-0696 Section 3.3 which includes:
1.
One dial telephone for onsite and offsite locations.
2.
Direct verbal intercommunications and radio communications to supplement the above. - -. - - -. -...... _. _... _. _ -..., - - _ -, _ - _ _ _ _
v IV.
EMERGENCY OPERATIONS FACILITY The Emergency Operations Facility (EOF) is comprised of the following two existing facilities:
1.
Near Site EOF.
2.
A.
Location 1.
Near-Site Emergency Operations Facility (EOF) a.
The EOF is located in the Energy Information Center.
(The EOF is located outside of the JAFNPP security fence and is within 20 minutes ground travel time from the TSC.)
b.
The purpose of the EOF is to provide a facility for the acordination of long-term emergency responta 2nd recovery activities.
2.
Alternate Emergency Operations Facility ( AEOF) a.
The AEOF is located at Niagara Mohawk Power Corporation's Service Center on West First Street in Oswego, New York.
(This facility is located approximately 10 miles from the site and 180' from the prevailing downwind direction.)
b.
The purpose of the NEOF is to provide a backup for continuing the functions of the near-site EOF in the event the near-site EOF is deemed inappropriate for use.
Equipment and personnel will be transferred c.
from the EOF to the AEOF in the event it is activated.
EOF /AEOF Operations 1
Upon declaring Site Emergency or General Emergency condition, the EOF or ABOF will be activated within one hour and fully operational within sixteen hours.
The Emergency Director will direct the activation of the 1
EOF /AEOF.
If it is determined by the Emergency Director that use of the EOF is inappropriate, based on radiological considerations, he will order the AEOF to be activated.
If such a decision is made, personnel will be sent to the EOF to remove necessary equipment and transfer it to the AE OF.
B.
Habitability The EOF is located in the Nine Mile Point Energy f
Information Center.
Special provisions for protection factors or ventilation protection will not be provided for this nearsite EOF.
However, a backup AEOF will be provided at a distance of approximately 10 miles from the I
Nine Mile Point site.
This backup site will be provided with the same accident monitoring capabilities as the nearsite EOF and will be activated in the event the nearsite facility is uninhabitable.
The Authority believes this arrangement meets the intent of NUREG-0696.
The EOF will be equipped with an area radiation monitor and a continuous air monitor to continuously indicate radiation dose rates and airborne radioactivity concentrations inside the EOF.. _, _
C.
Data System Until the implementation of the Emergency Response Data System (E RDS) is completed as described in Section V, the EOF will consist of a Meteorological Measuring System; this system will include wind speed, wind direction from temperature sensors installed on an isolated tower at elevations of approximately 30 feet and 200 feet above plant grade.
The data collected by these sensors will be telemetered to the JAFNPP control room and continuously recorded on strip charts.
This data will also be available to the EOF /AEOF.
D.
Size The classroom and adjacent areas including conference rooms, offices, lavatories and part of the lobby in the Energy Information Center contains 13,000 sq. ft. of floor space.
This space is designated as available for EOF use on a required basis.
Private NRC offices will be fashioned from these areas.
E.
Training Emergency managers will receive initial training in methods of assessments, corrective actions, protective actions, location & function of facilities, scope responsibilities and functions of the Emergency Plan and Implementing Procedures.
Managers will also receive annual training in review of the plan, specifically for changes and improvements of methodology.
Managers will participate in drills and exercises.
Training in the plan and procedures will be in detail adequate to ensure complete underst pnding of the individuals' roles in the integrated response to emergencies.
Managers will be cross-trained in specific functional responsibilities. m
- - - - _ ~
F.
Rtcords Availability M2ntgament Stored in the EOF will be a set of up-to-date records including:
l 1.
Technical specifications j
2.
Operating procedures
}
3.
Emergency operating procedures 4.
Final Safety Analysis Report 5.
Up-to-date records related to licensee, State and Local Emergency Plans l
6.
Off-site population distribution data 7.
Evacuation plans j
8.
Drawings, schematics and diagrams showing the condition of plant systems down to the component level and the inplant location of these systems will l
be added later other records will be obtained from the TSC by facsimile transmittal.
Document control procedures will be j
f modified to assure that current and complete copies of all of the stated records and procedures will be stored in the EOF.
Transfer of db above to the AEOF will be completed in the event that the EOF becomes non-operational.
1 G.
Communications Communications equipment within the EOF will include:
Dial telephone to on-site and off-site locations.
a.
b.
Dedicated communication links to:
1.
Authority Headquarters 2.
NRC 3.
Control Room
- I
4.
Tschnical Support Canter
- 5.*
Emergency Operations Pacility*
6.
Local County Emergency Operations Center
- 7.
County Warning Point *'
~
8.
State WarningsPoint*
9.
NYS Office of Disaster Preparedness
- t 10.
NYS Department of Health
- 1 11.
NMPNS Control Room
- 12.
NMPNS Technical Supporb Center *
Communications equipment within-the_AEOF will include:
Dial telephone to on$ site and off-site lbc'ations, a.
I
'J' b.
Dedicatr$ communication links to:
1.
NRC 2.
Control Room /TSC 3.
New York State Warning. Point and Oswego County Office of Disaster Preparedness
, 1 Emergency Portable Radio l
c.
s.._,
d.
An NRC ENS hotline from 'the AEOF vill be installed later.
NOTE:
Equipment for th'e AEOF will be transpor$ed f rom the EOF as necessary 4
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EMERGENCY RESPONSE DATA SkSTEM (ERDS)
V.
Ineorder to reet the requi.e.ements of NUREG-0696 for data
' collection, storage and display, t$c installation of a new
' data system will be comp 16ted..Th'is Emergency Response Data cf
_ _ _ Sistem (ERDS) will-su'pply 'infornation to the Control Room
? ' '(CR), Technical Support Center (TSC)1 and the Emergency l
Operations Facility (EOF).
/ 'J
' 'E The required inputs included in this ERDS system will include 4
the, parameters discussed in Regulatory Guide 1.97 Rev. 2 and
-Ehose defined by the BWR Owners Group Conceptual Design to Displays of information will meet the intentf of NUREG-0696.
beisupplied'to the Control Room, Technical Support Center and
~
o the Em&rgen'cy Operations Facility.
The flexability of this new data system will enable the Authority to eventually phase out the present process computer and incorporate its functions.into the Emergency Response Data System (ERDS). (Figure 4.)~
The ERDS consists of the following:
Q A.
Control Room Inforn.ation System (CRIS)
B,.
Technical Support Center Information System (TSCIS)
Emergency Operations Facility Information System (EOFIS)
C.
s.
t j'
t S.-
FIGURE 4 CONCEPTUAL EMERGENCY RESPONSE DATA SYSTEM (ERDS) m m,,
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Tho ERDS functions of ecch systsm cre:
A.
Control Room Information System (CRIS)
The Control Room information requirements for emergency response are defined as a minimum by the Emergency Procedure Guidelines (EPG).
These requirements will be provided by the existing control room instrumentation and by future modifications to that instrumentation.
Further additional information not required but useful in carrying out t*ne actions of the EPGs will be provided by the CRIS System.
Tne CRIS consists of the existing Control Room instrumentation together with any Control Room additions or modifications subsequently implemented.
The function of the CRIS encompasses that intended by the Safety Parameter Display System (SPDS) described in NUREG-0696.
The CRIS will have the following operational / hardware features:
a.
Complete hardware redundancy as required.
b.
For each plant operating mode, a single primary display format designed according to acceptable human engineering principles (a limited number of parameters or derived variables and their trends in an organized display that can be readily interpreted by an operator) will be routinely displayed from which plant safety status can be determined.
The operator of the display will have the ability to c.
call a secondary display containing additional data.,
d.
The censors and cignal conditionare providing input to'the CRIS from safety systems will ba designed and qualified to Class lE Standards.
Reg. Guide 1.97 Rev. 2 variables used in the CRIS will have 1.97 qua.ified sensors and signals conditioners.
l e.
Sufficient signals will be input to the CRIS to provide indication of the operating condition of the followino systems as a minimum:
1.
Reactivity Control 2.
Reactor Core Cooling and heat removal from the primary system 3.
Reactor Coolant System Integrity 4.
Containment Radioactivity 5.
Containment Integrity B.
Technical Support Center Information System (TSCIS)
Plant data required to analyze plant operating conditions prior to, during, and after an accident will be supplied by the TSCIS to personnel in the Technical Support Center (TSC).
The TSCIS will have the following hardware features:
The sensors and signal conditioners providing input a.
to the TSCIS will be comparable in accuracy and reliability to corresponding sensors and conditioners providing input to already existing control room displays.
b.
Where the TSCIS interfaces with class lE systems, appropriate isolation in accordance with GDC 24 and IEEE Standard 279-1971, Section 4.7 will be provided so as not to degrade the capability or reliability of any class lE Oystem.. -
c.
The TSCIS will, es e ninimum, monitor all variables definsd on Type A, B, C, D and E variabloc in NRC
~
Regulatory Guide 1.97, Rev.
2.
The TSCIS will monitor the same set of points as the CRIS, EOFIS and the plant computer.
d.
Complete hardware redundancy as required.
The TSCIS will have the following operational features:
Using the display concept developed by the BWR a.
Owners Group, the TSCIS will be capable of displaying the current and trend value of required variables using appropriate human engineering principles in display design.
The current value of all variables will also be available at all times.
b.
The system will collect and store the value of variables with the time resolution of data acquisition in a circular buffer containing the last two (2) hours of plant information.
Capacity to record at Jeast two (2) weeks of additional post event data with reduced time resolution will 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 will be provided for all TSC data.
This information will be available for replay in any of the formats specified.
The system will have the ability to replay the information at increased cpeed at the operators request.
Upon the request of the terminal display operator the system will store all information for future retrieval.
The TSCIS will be capable of interfacing with remote c.
terminals and computers using standard industrial interfaces.
C.
Emergancy Operations Facility Information System (EOFIS)
The basis for the data to be displayed by the EOFIS will be the plant-unique JAF Emergency Plan.
It is anticipated, that the largest portion of the information presented in this center will relate to dose assessment and notification of civil authorities.
Displays will be limited to those necessary to aid in the performance of these tasks.
EOFIS Variable Set The set of variables which will be available in the EOFIS to assist EOF personnel in performing their function is:
1.
Containment radiation 2.
Refueling floor area radiation 3.
Airborne radioactivity released from plant planned release points 4.
Liquid radioactivicy released to the environment 5.
Off-site radiation and radioactivity as indicated by survey teams 6.
Wind direction 7.
Wind speed 8.
Atmospheric temperature 9.
Meteorological / Radiological Data Set
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VI.
PROJEC'IED IMPLEMENTATION SCHEDULE The Emergency Response Facilities (ERF) detailed in this conceptual design is proposed by the Authority to meet the intent of NUREG-0696, " Functional Criteria for Emergency Response Facilities," and to improve the FitzPatrick Plant's ability to respond in emergency situations.
A detailed final implementation schedule will be issued after completion of the functional specification to upgrade the existing technical data system by incorporating the requirements of NUREC-0696, and Reg. Guide 1.97, Rev. 2.
In accordance with the requirements of NUREG-0696, the current interim TSC, OSC and EOF will remain fully operational until the scheduled stagina in parallel with the existing process computer system is completed... - - - -
VII. REFERENCES 1.
NUREG-0578, TMI-2 Lessons Learned Task Force; Status Report and Short term Recommendations.
2.
NUREG-0585, TMI-2 Lessons Learned Task Force Final Report, 10/79.
3.
NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
Rev. 1 4.
NUREG-0696, Functional Criteria for Emergency Response Facilities.
5.
NUNEG-0737, Clarification of TMI Action Plan Requirements 6.
REGULATORY GUIDE 1.23, " Meteorological Programs in Support of Nuclear Power Plants," Proposed Revision 1.
7.
REGULATORY GUIDE 1.97, " Instruments for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident,"
l Revision 2.
8.
EMERGENCY PROCEDURE GUIDELINES, BWR 1 through 6; Revision 1.
9.
IP3, Conceptual Eris Design - Passman.
10.
JAFNPP EMERGENCY PLAN; Revision 0, 1981.
11.
BWR OWNERS GROUP, Conceptual Design Eris; July 8, 1981.
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