ML20041E784
| ML20041E784 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 02/19/1982 |
| From: | Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20041E783 | List: |
| References | |
| RTR-NUREG-0696, RTR-NUREG-696 NUDOCS 8203120113 | |
| Download: ML20041E784 (46) | |
Text
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James W Cook Vice President - Projects, Engineenng and Construction General omces: 1945 West Parnell Road, Jockeon, MI 492o1 * (517) 788-o453 I
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'N'.nWA'nm:'CJ Harold R Denton, Director Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission p C'U ["
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MIDLAND PROJECT MIDLAND DOCKET NOS 50-329, 50-330 RESPONSE TO NRC QUESTIONS 432.43.2 AND 432.43.7 FILE B13.3 SERIAL 15538
REFERENCE:
NRC (E G ADENSAM) LETTER DATED OCTOBER 27, 1981 ENCLOSURE: SUPPLEMENTAL INFORMATION FOR THE EVALUATION OF EMERGENCY RESPONSE FACILITIES (8 COPIES)
The enclosure provides the response to NRC Questions 432.43.2 and 432.43.7 as requested by the reference.
It describes the conceptual design for the Midland Plant Emergency Response Facilities and demonstrates that these facilities satisfactorily address the guidelines of NUREG-0696.
The NRC Staff should recognize that the information provided in the enclosure represents the state of the design as it exists today and that modifications may occur during the evolution of the emergency planning process (ie, work staffing assignments, room arrangements, communications equipment placement, etc). Appropriate parts of the requested information in the reference are being incorporated into a revision to the Midland Site Emergency Plan which is to be issued by the end of February 1982. That information is referenced appropriately in the enclosure.
Consumers Power Company is pursuing an alternative to the one hour minimum EOF staffing time guideline of NUREG-0654 which should be acceptable to the NRC Staff. That alternative consists of staffing an interim EOF located approximately 120 miles from the plant site at the corporate headquarters in Jackson, Michigan. The proposal for this alternative is described in Consumers Power Company (B D Johnson) letter to the NRC dated February 5, 1982, Docket 50-255, License DPR-20 (Palisades). Based upon NRC l
acceptance of the Palisades proposal, similar information will be provided on the Midland docket.
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i TABLE OF CONTENTS P,agg 1.0 PURPOSE 1-1 2.0 TECHNICAL SUPPORT CENTER 2-1 2.1 INTEGRATION WITH OVERALL PLANNING 2-1 2.2 LOCATION 2-1 2.3 SIZE 2-1 2.4 STRUCTURE 2-2 2.5 HABITABILITY 2-3 2.6 STAFFING 2-4 2.7 COMMUNICATIONS 2-4 2.8 INSTRUMENTATION, DATA SYSTEM EQUIPMENT AND POWER SUPPLIES 2-5 2.9 TECHNICAL DATA AND DATA SYSTEM 2-5 2.10 RECORDS AVAILABILITY AND MANAGEMENT 2-5 3.0 CONTROL ROOM 3-1 3.1 INTEGRATION WITH OVERALL PLANNING 3-1 3.2 STAFFING 3-1 3.3 COMMUNICATIONS 3-1 3.4 ERF PHASE 3-1 4.0 OPERATIONAL SUPPORT CENTER 4-1 4.1 INTEGRATION WITH OVERALL PLANNING 4-1 4.2 HABITABILITY 4-1 4.3 COMMUNICATIONS 4-1 4.4 STAFFING 4-1 4.5 SIZE 4-1 5.0 EMERGENCY OPERATIONS FACILITIES 5-1 5.1 INTEGRATION WITH OVERALL EMERGENCY PLANNING 5-1 5.2 LOCATION, STRUCTURE AND HABITABILITY 5-1 5.3 STAFFING 5-1 5.4 SIZE 5-2 5.5 RADIOLOGICAL MONITORING 5-3 5.6 COMMUNICATIONS 5-3 5.7 INSTRUMENTATION, DATA SYSTEM EQUIPMENT AND POWER SUPPLIES 5-4 5.8 TECHNICAL DATA AND DATA SYSTEM 5-4 5.9 RECORDS AVAILABILITY AND MANAGEMENT 5-4 rp0182-0373a168
11 P.352 6.0 DATA ACQUISITION SYSTEM 6-1 6.1 DAS FUNCTIONAL DESCRIPTION 6-1 6.2 DAS FACILITIES 6-1 6.3 DAS EQUIPMENT SPECIFICATIONS 6-2 6.4 SENSOR DATA TO BE ACQUIRED 6-3 6.5 DATA TO BE PROVIDED FOR DOSE ASSESSMENT 6-4 7.0 DATA DISPLAY SYSTEMS 7-1 7.1 FUNCTIONAL DISPLAY DEVICES 7-1 7.2 SPDS 7-3 8.0 DATA COMMUNICATIONS 8-1
8.1 DESCRIPTION
8-1 8.2 GENERAL 8-1 8.3 ADDED QUESTIONS FOR DATA LINKS USING EIA STANDARD INTERFACES 8-1 8.4 ADDED QUESTIONS FOR VOICE-FREQUENCY LINKS 8-1 9.0 SYSTEM SUPPORT REQUIREMENTS 9-1 9.1 DOCUMENTATION 9-1 9.2 TRAINING 9-1 9.3 QUALITY ASSURANCE 9-1 9.4 RELIABILITY 9-2 9.5 MAINTENANCE 9-2 10.0 JOINT PUBLIC INFORMATION CENTER 10-1 10.1 INTEGRATION WITH OVERALL PLANNING 10-1 10.2 LOCATION, STRUCTURE AND HABITABILITY 10-1 10.3 STAFFING 10-1 10.4 SIZE AND COMMUNICATIONS 10-1 10.5 RECORDS AVAILABILITY 10-2 rp0182-0373a168
1-1 1.0 PURPOSE The purpose of this report is to provide additional information requested by the NRC on October 27, 1981 (Questions 432.43.2 and 432.43.7) on the Emergency Response Facilities (ERF) to serve Consumers Power Company (CP Co) Midland Nuclear Power Plant. This report responds to these questions and supplements the Midland Site Emergency Plan (SEP) by providing design information on the functioning of the ERFs, including the Joint Public Information Center (JPIC).
The references made in this enclosure to the SEP are effective for Revision 42 and thereafter, i
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2-1 2.0 TECHNICAL SUPPORT CENTER 2.1 INTEGRATION WITH OVERALL PLAhWING Information concerning the integration of the Technical Support Center (TSC) with the overall emergency plan is included in SEP Subsection 7.1.1.
2.2 LOCATION The TSC is located in the protected area within the Plant security perimeter (see SEP Figure 2-2).
All Plant data that is stored in the Plant computer will be available in the TSC data system. Any control room information not available in the Plant computer can be obtained from the control room by the dedicated communications system.
However, to prcvide face-to-face interaction between the TSC personnel and the control room personnel, the TSC is located in close proximity to the control room.
j The primary route from the TSC to the control room is to leave the TSC via the southwest exit, head south to the west entrance to the turbine building, pass through a security checkpoint (automatic card reader), proceed to the center stairwell, walk up 2 flights of stairs (from Elevation 634' to 659'), pass through another security checkpoint and enter the control room. This distance can be walked in approximately two minutes without personnel exposure exceeding the criteria of General Design Criteria (GDC) 19 (ie, 5 rem whole body averaged over 30 days). For a more detailed description of the study performed to calculate operator dose received while traveling to and from the TSC from the Control Room, see the response to Item II.B.2 in the Responses to Post TMI-2 Issues and Events FSAR volume.
When personnel travel between the TSC and the control room, a radiological survey of the area will be performed between the two facilities.
If, during an accident, it is determined that the primary route to the control room is impeded by high radiation fields, an alternate route will be chosen that will adhere with ALARA concepts.
Anticontamination clothing, respiratory protection and other protective gear may be used to protect personnel in transit. See SEP Subsections 6.4.2.1 and 6.4.2.2 for additional information on respiratory protective devices and protective clothing.
2.3 SIZE The TSC has been designed to provide flexibility in the assignment of work stations and ready access to various communications equipment provided in the TSC. See Figure 2-1 for a general layout of TSC and its functional working groups.
The TSC will be carpeted and have acoustical ceiling tile to minimize mechan-ical noise. Separate offices for the TSC Manager and Site Emergency Director, rp0182-0373bl68
2-2 separate rooms for conferences, Document Control, computer equipment and com-munications systems will minimize conversational noise.
The 4,278 square foot floor area provided in the TSC allows ample working space for the personnel assigned to the TSC. To allow further interaction among the TSC personnel, personnel performing related tasks are grouped adjacent to one another by work function. The Chem /HP personnel will have I
work stations designed for the designated task near each other and the techni-1 l
cal personnel will have work stations designed for their tasks near each other. This grouping will facilitate the flow of information between persons and groups. Figure 2-1 shows a tentative layout of personnel work stations and items of equipment at each work station.
Equipment is currently planned for each working group that will provide the group with data necessary to perform its assigned function. One CRT will be driven by the Radiological Monitoring System computer and four CRTs by the TSC computer.
In order to determine the extent of both in-plant radiation levels and tracking Plant radioactive effluents following an accident, the Chem /HP group will be provided with the following major pieces of equipment:
HP radio control console to monitor radio transmissions from the radiation monitoring teams; two CRTs, one to display data for dose assessment and the other to display data from the Radiological Monitoring System; and ' programmable calculator as backup to the dose assessment CRT.
In order to determine the i
status of Plant systems, the technical group will be provided with three CRTs (one is a backup) to display data from the Safety Parameter Display System and the Data Acquisition System. The CRi displays and keyboards will be similar to those provided in the control room.
The TSC will have a room dedicated for the TSC computer. The TSC computer will have data links to the main Plcnt computer, meteorological tower data acquisition systems and the digital Radiation Monitoring System computer. The computer equipment racks will be placed in the computer room such that sufficient space will be provided according to vendor recommendations for access to the back of the equipment for repairs.
Sufficient table space will be available in the work area such that maps, diagrams and drawings can be reviewed by the work groups. Maps of the area will be pinned to tack boards located in the work area and conference room.
Up-to-date Plant diagrams and drawings will be maintained by Document Control in the records room.
The TSC will have a separate work space designated for five NRC personnel.
Three of the five NRC personnel will have their work stations in a separate room in the TSC with sufficient privacy for meetings and telephone conver-sations. See Figure 2-1 for the location of the NRC work space.
2.4 STRUCTURE Since the TSC is designed to be operable during a 100-year flood and to be
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able to withstand a 100-year windstorm, the TSC will be able to withstand reasonably expected adverse conditions. The TSC will be accessible during l
these floods or storms.
Should a sustained 40 mile per hour wind from the l
rp0182-0373bl68
2-3
's northwest occur during a probable maximum flood, it may be necessary to protect the TSC entrances from flooding by sandbagging.
See FSAR Subsec-tion 2.4.3.6.
2.5 HABITABILITY The TSC will have similar radiological habitability as the control room. The radiation doses received in the TSC during an accident will be below the criteria of GDC 19 (ie, 5 rem whole body averaged over 30 days).
The TSC ventilation system will be functionally comparable to the control room ventilation system for protection against cirborne radioactivity. An area radiation monitor will be installed in close proximity to the normal air intake to the TSC. At an airborne activity level within the intake duct that results in a dose rate of 2.5 mrem per hour, an alarm will actuate to alert the TSC personnel to manually energize the filtration system, which includes the automatic closing of normal air intake damper and the opening of the emergency air intake. Air entering the emergency intake will flow through the filtration system before being circulated into the TSC.
The TSC filtration system consists of an electric heating coil, a moderate efficiency prefilter, a high efficiency particulate air (HEPA) filter, a four-inch deep rechargeable i
carbon adsorbers, a downstream HEPA filter and an internally mounted fan / motor assembly. The filtration system will have a minimum efficiency of 99.97% on 0.3pm DOP (dioctyl phthalate) particles as determined by Military Standard 282.
The Radiation Monitoring System (RMS) for the TSC consists of an area radiation monitor located by the normal air intake duct of the TSC and a portable airborne radioactivity monitor located within the working area of the TSC, which is capable of plug-in into the plant RMS.
The area radiation monitor will be a gamma-sensitive (GM tube) detector.
See FSAR Subsection 12.3.4.1 for a further discussion of area radiation monitors.
The portable airborne radiation monitor will monitor noble gases by using beta-sensitive scintillation detectors, and will monitor halogen (iodine) and radioactive particulates by using charcoal adsorbers, particulate filters and gamma scintillation detectors. The airborne radioactivity monitor will alarm at a radiation level of 1.0E-07 microcuries/cm', which will alert the TSC personnel to take protective action.
Protective action may include donning protective clothing and respiratory protective devices.
See FSAR Subsection 12.3.4.2 for a further discussion of portable airborne radioactivity monitors.
Supplies of respiratory protective devices, protective clothing and radio-protective drugs will be available to all TSC personnel. For additional in-formation on respiratory protective devices, protective clothing and radioprotective drugs, see SEP Subsections 6.4.2.1, 6.4.2.2 and 6.4.2.3, respectively.
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2.6 STAFFING 4
The TSC will be staffed by people with sufficient technical expertise to per-form the functions of the TSC (see Figure 2-2).
The tasks that may need to be performed in the event of an emergency are discussed in SEP Subsection 5.1.2.
The responsibilities of various Management and technical personnel are discussed in SEP Subsection 5.1.1.
The training of ti.4 Plant personnel in emergency preparedness is discussed in SEP Section 8.1.
l All functional equipment in the TSC will be activated within 30 minutes. The human error factor will be minimized by utilizing as many means as possible, including CRTs, recorders and programmable calculators, plant procedures, documentation and operating manuals available in the TSC, and periodic j
training exercises.
2.7 COMMUNICATIONS I
The communications systems that will be used by the emergency organizations l
will consist of reliable primary and backup systems (see SEP Section 7.5).
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The communications systems for the emergency response facilities are shown in j
Figure 2-3.
Ten dedicated emergency hot line services will be available for use by the TSC personnel during emergency conditions. These dedicated telephones will be switchboard independent and will bypass any onsite or local offsite switching facilities. The following dedicated telephones will be available in the TSC:
Emergency Notification System (ENS) to the NRC Operations Center; NRC Health Physics Network (HPN); dedicated direct access-to the control room and j
Emergency Operations Facility (EOF); and hot lines to Corposate Headquarters, State Police in Bay City, Midland County Dispatcher, Dow Cheenical and Dow j
Corning. OSC communications is via the onsite telephone system.
2 The ENS and HPN telephones will be located in the NRC Office of the TSC (see
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Figure 2-1).
'IVo additional dial telephone lines and a speaker telephone will be provided as backup to the ENS and HPN for use by NRC personnel.
The Police Radio Link and dial telephones will provide backup communications i
with the State Police in Bay City, Midland County Dispatcher, Dow Chemical and
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Dow Corning. The Health Physics base will provide radio communications with l
mobile monitoring teams and a backup communications link to the EOF.
Communications between HP Control Points and the Radiological Assessment-Coordinator may be provided by telephone or radio. The security repeater will provide communications with the security force. The Plant repeater will provide radio communications with emergency teams.
Provisions for 24-hour per day manning of the state / local communication links that initiate emergency response actions are provided, since the Michigan State Emergency Operations Center is located at the Bay City State Police Post l
and Midland County Emergency Operations Center is located at the Midland l
County Building Annex with communications via the sheriff's office central dispatch.
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2-5 In order to provide unhindered access to communications equipment by all TSC personnel, a separate telephone will be provided at each work station for communications with onsite and offsite locations. These telephones will light up when ringing to easily identify a ringing telephone. Multiline speaker telephones for communications within the TSC, and with onsite and offsite locations and the dedicated telephones will be provided in the TSC Manager's Office, the SED's Office and the conference room. The communications room in l
the TSC will be provided with a multiline, autodial telephone, the radio l
control console, and facsimile transmission equipment.
Facsimile transmission capabilities will be provided between the TSC, EOF and NRC Operations Center. The facsimile equipment will be standard equipment compatible with telephone transmissions.
2.8 INSTRUMENTATION, DATA SYSTEM EQUIPMENT AND POWER SUPPLIES Instrumentation, data system equipment and power supply methodologies are discussed in Sections 6, 7 and 8 of this report.
2.9 TECHNICAL DATA AND DATA SYSTEM Technical data and data system methodologies are discussed in Sections 6, 7 and 8 of this report.
2.10 RECORDS AVAILABILITY AND MANAGEMENT The TSC personnel will have ready access to up-to-date records, operational specifications and procedures. These will include:
a.
Plant meteorological data; b.
SPDS; c.
Plant operating procedures; d.
Emergency operating procedures; e.
FSAR; f.
SEP; g.
SEP Implementing Procedures; h.
Plant Technical Specifications; 1.
Plant operating records;
- j. Drawings of record, schematics and diagrams showing Plant structures and systems down to the component level, as well as in plant locations of these systems; k.
Current Federal, State and local emergency response plans; 1.
Offsite population distribution data; m.
Plant employee quarterly radiation exposure histories; and i
n.
Working copies of procedures, log sheets and other job performance aids.
Document Control distribution and maintenance procedures have been established to update these records as necessary to ensure that they are current and complete.
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2-6 A variety of methods of storage and presentation will ensure availability and ease of access to the various records maintained in the TSC. Document storage will be by any of the following methods:
a.
Hardcopy on bookshelves; b.
TSC computer with access by CRTs; c.
Microfilm in storage cabinets; d.
Aperture cards in storage cabinets; or Automated document control system with video display capability in the e.
TSC.
Document Control personnel will be assigned to the TSC to assist other TSC personnel in retrieval of documents. The Document Control personnel will be assisted in document / record retrieval by a CRT display since all indices are maintained on computer. A backup, master index of documents will be stored on microform. Micrographic reader / printers will be located in the records room in order to review the various microforms and obtain hardcopy for further study.
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1 3.0 CONTROL ROOM 3.1 INTEGRATION WITH OVERALL PLANNING i
The control room is the onsite location from which the Midland Nuclear Power Plant will be operated.
It will contain the instrumentation, controls and displays for: nuclear systems, reactor coolant systems, steam systems, electrical systems, safety systems and accident monitoring systems. During the course of an emergency situation, the control room personnel will perform the following functions:
a.
Monitor Plant parameters; b.
Analyze abnormal conditions; take corrective actions; i
c.
Classify emergencies; i
d.
Make initial notification to Plant Supervisor, Shift Supervisor and Shift Engineer and o,ffsite agencies; e.
Establish communications with Plant emergency response teams; f.
Establish communications with emergency response facilities; and g.
Manage Plant operations.
3.2 STAFFING The staffing of the control room during normal operations is described in SEP Subsection 5.1.1.
The control room emergency organization is shown in Fig-ure 3-1.
3.3 COMMUNICATIONS The following onsite and offsite communications links for continuous informa-tion exchange will be available: commercial telephones, dedicated telephones, radio and Plant public address systems (see SEP Section 7.5).
The emergency response facilities' communications systems are shown in Figure 2-3.
The Plant public address system is described in FSAR Subsection 9.5.2.2.2.
The Plant Supervisor, Shift Supervisor and Shift Engineer or their designates will be notified of an abnormal condition. The Control Room Operators and Shift Supervisor will be in the control room at all times and will be imme-
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diately aware of any abnormal conditions.
The SEP Implementing Procedures on communications will require that, after the TSC is activated, the control room staff verify the TSC communications links to ensure that they have been established and are functional.
3.4 ERF PRASE i
1 Once the TSC is activated, the control room personnel will relinquish to the TSC the management of Plant operations not directly related to reactor system manipulation and reactor safety.
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FIGURE 3-1 CONTROL ROOM EMERGENCY ORGANIZATION I
4-1 4.0 OPERATIONAL SUPPORT CENTER 4.1 INTEGRATION WITH OVERALL PLANNING Information concerning the integration of the Operational Support Center (OSC) with the overall emergency plan is included in SEP Subsection 7.1.3.
The primary Health Physics control point will be located at the access control area in the auxiliary building and is accessible to OSC personnel. Ar alternate Health Physics control point will be located in the drsimetry processing area at the change house.
4.2 HABITABILITY The OSC functions as a personnel staging area to provide logistics support during an accident. To satisfy this function, the location in the machine shop anc lunchroom area of the administration and service building was chosen for its utility and accessibility. Emergency supplies available in the OSC are discussed in SEP Subsection 7.1.3.
In the event that Health Physics determines, based on portable radiation monitoring surveys, that the radiological conditions in the OSC prohibit continuous manning, the OSC personnel will be evacuated to a backup OSC. The OSC evacuation and reassembly will be included in SEP Implementing Procedures.
Following reassembly, the backup OSC will function as the personnel staging area.
4.3 COMMUNICATIONS The primary OSC communication link with the control room and TSC will be via plant telephone system as described in see Figure 2-3 and SEP Section 7.5.
Direct voice radio communications by walkie-talkie will be used to supplement telechene links. Regular telephone service will be available in the OSC for communications with other onsite and offsite locations.
Regular telephone service will be available at the backup OSC for communi-cations with the control room and TSC. The Plant radio system is the backup.
4.4 STAFFING Information concerning the staffing of the OSC is included in SEP Subsec-tion 7.1.3.
4.5 SIZE The machine shop and lunchroom area of the administration and service building will be large enough to accommodate the people _ assigned to the OSC.
rp0182-0373bl68
5-1 5.0 EMERGENCY OPERATIONS FACILITIES 5.1 INTEGRATION WITH OVERALL EMERGENCY PLANNING Information concerning the integration of the EOF with the overall emergency l
plan is included in SEP Subsections 5.1.3 and 7.2.
The EOF will be used as the Long-Term Recovery Organization. The functions assigned to the Long-Term Recovery Organization are included in SEP Subsection 5.1.4.
5.2 LOCATION, STRUCTURE AND HABITABILITY The EOF for the Midland Plant will be located in the Bay City Service Center in Bay City, Michigan approximately 18 miles east of the Plant (see Figure 5-1).
The EOF will be readily accessib)e by road to Federal, State and local government officials, as well as CP Co personnel. The transportation network in the vicinity of the EOF is also shown in Figure 5-1.
The Bay City Service Center is a single-story, brick building. The EOF portion of the Service Center has no windows. This building will be able to withstand reasonably expected adverse conditions and remain operational.
The radiation doses expected when the EOF is being utilized during a design basis accident (DBA) or other specified accidents would be normal background radiation since the EOF is more than ten miles from the Plant. For this reason, no ventilation protection will be provided.
Supply of protective clothing and respiratory equipment will be readily available for personnel who may require access to the Plant or may enter the airborne plume.
In the event that Health Physics determines that the radiological conditions at the Plant or of the airborne plume conflict with ALARA concepts, the protective clothing and respiratory equipment will be donned prior to entering the Plant or any contaminated area.
5.3 STAFFING The EOF will be staffed by enough people with sufficient technical expertise to perform the functions of the EOF (see Figure 5-2).
SEP Subsection 5.1.3 discusses the tasks that may need to be performed in the event of an emergency and the responsibilities of various Mansgement and technical personnel. The training of CP Co personnel in emergency preparedness is discussed in SEP Section 8.1.
All functional equipment in the EOF will be capable of being activated within 60 minutes. The human error factor will be minimized by utilizing as many means as possible including CRTs, recorders and programmable calculators.
Plant procedures, documentation and operating manuals available in the EOF, and periodic training exercises.
rp0182-0373bl68
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5-2 i
5.4 SIZE The EOF will be large enough to provide adequate working space for the personnel assigned to the EOF including Federal, State and local agency personnel. See Figure 5-3 for a general layout of the EOF.
l i
i A movabic curtain will be provided to minimize traffic through the work area.
?
Rooms will be provided for private conferences to minimize conversational noise.
The 4513 square foot floor area provided in the EOF allows ample working space for a minimum of 40 personnel. To permit interaction among the EOF staff,
- l personnel performing related tasks will be grouped together by work function.
Figure 5-3 shows a tentative layout of personnel work stations and items of equipment at each work station. As shown on this figure, the Health Physics 1
personnel will have work stations near each other and the engineering personnel will have work stations near each other. This arrangement will facilitate the flow of information among members of the work group.
Since the l l[
Health Physics and engineering work groups will be located in the same work area, the flow of information between the work groups will be readily j
available.
Equipment is currently planned for each work group that will provide each l
group with data necessary to perform its assigned function.
Four CRTs will be j
driven by the EOF computer. The Health Physics group will be provided with 1
the following major pieces of equipment in order to track radiological
}
effluents following an accident: Health Physics base station co monitor radio transmissions from the radiation monitoring teams; a CRT to display selected 4
radiological and dose assessment data; and a programmable calculator as backup to the CRT. The engineering group, in order to assist in determining status of Plant systems, will be provided with two CRTs (one is a backup) to display appropriate data from the SPDS and Data Acquisition System (DAS). Reactor Physics will be provided with one CRT in order to assist in determining the j
status of the reactor. The CRT displays and keyboards will be similar to 1
those provided in the control room.
i The EOF will have a room dedicated for the EOF computer which will have data 3
links to the TSC computer. The computer equipment racks will be placed in the room such that sufficient space will be provided according to vendor recommendations for access to the back of the equipment for repairs. The Bay i
)i City Service Center has a maintenance shop that will be available for minor equipment repair.
Sufficient table space will be available in the work area for review of maps, diagrams and drawings by the work groups. Maps of the EPZ area will be located throughout the EOF. Up-to-date Plant diagrams and drawings will be maintained by Document Control in the records storage room.
The EOF will have a separate work space designated for nine NRC personnel.
Five of the nine NRC personnel will have work stations in a separate room adjacent to the EOF. This converted classroom will provide sufficient privacy j
rp0182-0373bl68
5-3 l
for meetings and telephone conversations.
(A speaker telephone will be provided in this room.)
Additional rooms will be available for private conversations for dissemination i
of confidential information.
Also, as shown in Figure 5-3, work areas have been assigned in the EOF for liaison personnel from offsite organizations.
5.5 RADIOLOGICAL MONITORING
]
Since the EOF is located beyond ten miles of the Plant, dedicated radiation i
monitors will not be assigned to the EOF.
5.6 COMMUNICATIONS a
The communications systems that will be used by the emergency organizations
- will consist of reliable primary and backup systems (see SEP Section 7.5).
The communications systems for the emergency response facilities are shown in j
Figure 2-3.
i Ten dedicated emergency hot line services will be available for use by the EOF j
personnel. These dedicated telephones will be switchboard independent and j
will bypass any local telephone switching facilities. The following dedicated telephones will be available in the EOF: ENS to the NRC Operations Center; NRC HPN; dedicated direct access to the control room and the TSC; and hot lines to Corporate Headquarters, State Police in Bay City, Midland County Dispatcher, Dow Chemical and Dow Corning. A radio control circuit will be available from the EOF to the Health Physics base at the Plant.
The ENS and HPN telephones will be located in the NRC Office space of the EOF (see Figure 5-3).
TWo additional dial telephone lines will be provided as backup to the ENS and HPN for use by NRC persor.nel at the EOF.
The police radio link and dial telephones will provide backup communications l
with the State Police in Bay City, Midland County Dispatcher, Dow Chemical and i
Dow Corning. The Health Physics base will provide radio communications with mobile monitoring teams and backup communication links to the TSC.
1 I
In order to provide unhindered access to communications equipment, each EOF work group supervisor will be provided with a separate telephone for communications within the EOF and to facilities outside the EOF. The 4
telephones will '11ght up when ringing to easily identify a ringing telephone.
Facsimile transmission capability will be provided between the EOF, TSC JPIC, and NRC Operations Center. The facsimile equipment will be standard equipment compatible with telephone transmissions.
l 5.7 INSTRUMENTATION, DATA SYSTEM EQUIPMENT AND POWER SUPPLIES Instrumentation, data system equipment and power supply methodologies are discussed in Sections 6, 7 and 8 of this report.
l
.rp0182-0373bl68
5-4 5.8 TECHNICAL DATA AND DATA SYSTEM Technical data and data system methodologies are discussed in Sections 6, 7 and 8 of this report.
5.9 RECORDS AVAILABILITY AND MANAGEMENT The EOF personnel will have ready access to up-to-date records, operational specifications and procedures. These will include:
a.
Plant meteorological data; b.
SPDS; c.
Plant operating procedures; d.
Emergency operating procedures; e.
FSAR; f.
SEP; g.
SEP Implementing Procedures; h.
Plant Technical Specifications;
- i. Drawings of record, schematics and diagrams, showing Plant structures and systems down tu the component level, and in plant locations of these j
systems;
- j. Current Federal, State and local emergency response plans;
}i k.
Offsite population distribution data; l
1.
Plant employee quarterly radiation exposure histories; and Checklists, guides, work sheets and other job performance aids.
m.
These records will be stored and maintained in the EOF. Document Control distribution and maintenance procedures have been established to update these records as necessary to ensure that they are current and complete.
A variety of methods of storage and presentation will ensure availability and ease of access for the various records maintained in the EOF. Document j
storage will be by any of the following methods:
- t a.
Hardcopy on bookshelves; b.
Plant computer with access with CRTs; c.
Microfilm in storage cabinets; or d.
Aperture cards in storage cabinets.
Document Control personnel will be assigned to the EOF to assist other EOF l
personnel in retrieval of documents. The Document Control personnel will be assisted in a document / record retrieval by a CRT display since all indices are maintained on computer. A backup, master index of documents will be stored on microform. Micrographic reader / printers and microfiche reader / printer will be located in the EOF in order to review the various microforms and obtain hardcopy for further study.
i rp0182-0373bl68
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FIGE 5-1 MIIIAT AEA FACILITY LOCATICNS
EOF COORDINATOR i
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6-1 6.0 DATA ACQUISITION SYSTEM 6.1 DAS FUNCTIONAL DESCRIPTION A functional block diagram of the Midland computer system and ERF's DAS is presented in Figure 6-1.
This diagram shows the major items of data processing and display equipment, their locations and the principal paths of information flow. The functional interconnection to ERFs and other Plant facilities is also indicated.
The Midland computer system and DAS are a highly integrated multiprocessor system with redundant and interconnected components. The major subsystems of this facility are: the front-end preprocessors, the main Plant computers, the radiation monitoring computer, the TSC computer, the EOF computer, and the functional displays and peripherals associated with each computer.
Each unit of the Midland Plant has its own main computer and front-end preprocessor with an additional computer for backup of either main computer.
The front-end preprocessors are dedicated computers for scanning, processing and alarm detection of Plant process variables. Each front-end preprocessor serves as a backup for the other unit and automatically switches when a failure is detected.
Each main Plant computer will perform the following basic functions: monitor alarms, log Plant data, execute NSSS core calculations, execute BOP perform-ance calculations, provide automatic turbine start-up and monitoring, provide Plant operating data, perform control rod drop tests, monitor input status, provide safety parameter displays and provide Plant data to the TSC and EOF computers.
Switchover to the backup computer is implemented manually in the event of failure of one of the main computers. Detection of a failure activates an alarm.
The TSC computer will perform the following functions: maintain a data base of Plant parameters independent of the main Plant computers, provide for i
analyses of Plant behavior comparable to those available from the control room, monitor radiological and meteorological parameters and perform disper-sion modeling, act as a communications controller for other ERFs and offsite facilities and provide safety parameter displays. The EOF computer will act primarily as a communication and display buffer, but also will provide an analysis capability at the EOF.
6.2 DAS FACILITIES Main features of the equipment layouts in the control room, programming room and computer input room are shown in Figure 6-2.
DAS components required to support the ERFs are circled on Figure 6-2.
DAS components at the TSC and EOF are indicated in Figures 2-1 and 5-3, respectively.
The environment of the DAS can be characterized as follows: Major components l
of the DAS will be located in the computer input and programming rooms adja-cent to the control room in Area 7 of the auxiliary building (see Figure 6-2).
Fire protection in these rooms will be provided by a CO2 'Y'****
rp0182-0373bl68
6-2 Based upon the current equipment configuration, the estimated heat output will be 37,000 Btu /hr for the programming room and 29,000 Btu /hr for the computer I
input room. These rooms will be temperature controlled. The air conditioning system will have sufficient capacity to remove this amount of heat both during normal operation and during emergency conditions.
Normal cperation of the air conditioning system will provide adequate humidity control for these rooms.
Power requirements for DAS equipment will be approximately 10,800 watts in the programming room, 8,400 watts in the computer input room, 4,800 watts at the TSC and 3,600 watts at the EOF.
Processors and controllers will be powered from uninterruptible sources.
Peripherals, such as CRTs, will be provided with reliable power, backed up by either uninterruptible power supplies or other emergency sources.
The computer input room, programming room, control room and TSC are all lo-cated within the Plant security boundary.
Doors to the computer input room and programming room will be locked to prevent entry by unauthorized person-nel. The processor at the EOF will be located in a secure location with locked doors to prevent unauthorized entry.
Personnel who are authorized to have access to these areas include computer operators, programmers, members of the engineering staff and certain maintenance technicians. Primary control of the DAS, such as starting and stopping the system, will be possible only at the processor locations.
6.3 DAS EQUIPMENT SPECIFICATIONS The Midland computer system and DAS for ERF are shown in Figure 6-1.
The two front-end preprocessors, the three main Plant control computers and the TSC computer are each Modular Computer Systems (MODCOMP), Classic Model 7870 series computers. They each have 1 M bytes of error-correcting MOS memory.
The EOF computer is a MODCOMP 7840 series computer with 256 K bytes of error-correcting MOS memory. The computational speed of these machines is of the order of 10' instructions per second. Depending upon the particular instruction, the time for execution may vary from 200 to 3,000 nanoseconds.
As shown in Figure 6-1, the on-line disk storage for the Plant control / data acquisition computer system consists of one controller and disk drive for each of the three Plant computers. The TSC computer also has its own controller and disk drive.
Each of these 4 disc systems is a MODCOMP Model 4173-3 moving-head disk drive system with 67 M bytes capacity. The maximum access time of these units is 60 milliseconds and the minimum transfer rate is 1.2 M bytes per second. Again, as shown in Figure 6-1, three magnetic tape storage drives are included in the system - one associated with each unit and one in the TSCi These are 9 track drives with a density of 1,600 bytes per inch and a speed of 45 inches per second.
The data acquistion hardware for the Midland computer system consists of a number of analog and digital sensors monitoring key functions throughout the Plant. For each unit, there will be approximately 1,500 channels of analog data and 1,500 channels of digital data. A maximum of 500 analog channels will be sampled at a rate of 1 sample per second. The remainder of the analog l
channels will be sampled at about 0.33 samples per second. Analog signals l
rp0182-0373bl68 l
6-3 i
i i
will be read with a resolution of 12 bits per channel, while digital signals
]
will be treated as 1 bit per channel.
j' The computer at the TSC will have 16 ports available for offsite communi-cations. Eight will be Type RS-232 ports and 8 will be 4-20 ma ports. The data transfer rate will be program adjustable between 50 and 19.2 K baud.
i 3
The operating system software for the Midland computer system will be the j
MAX IV System provided by Modular Computer Systems, Inc. This is a real-time multiprogramming system with an extension for network communications by way of the MAXNET module, also provided by MODCOMP.
It will not be necessary to modify this software to accommodate the requirements of the ERF DAS. Other j
software components that will be part of the Midland computer system include:
l the Acquisition Control Executive (ACE) which performs data acquisition, l
alarming and data manipulation functions; the man-machine interface module;
}
the nuclear application module; and the balance of Plant module. These l
software packages will be provided by Scientific Systems Services.
The data base for the ERFs will be provided by the Plant computer system and j
the radiation monitoring computer. Meeting the ERF DAS requirements will not i
place any added burden on the control components of these systems. All other I
requirements of the DAS will be met by dedicated processors in the TSC and j
EOF.
1 Programs and data for separate functions reside in physically separate storage f
facilities. The MAX IV operating system provides for isolation and separation
)-
of functional tasks. Order is maintained by the Taskmaster, a resident system element which transfers CPU control to the highest priority task and threads a j
new request for CPU time into the CPU queue according to the task priority.
Meacry is dynamically allocated to each active task as it is loaded. Active l
tasks can request additional memory at run time, and memory will be automa-tically deallocated when the task exits. The ability of a task to retain its j
main memory resources is determined by the task's execution priority level.
1 When any task needs memory, and none can be found, the " memory allocator" j
queues a memory request to the Roller Task. This task will roll out the j
lowest priority task (s) which is designated as rollable, and occupy sufficient j
memory pages to satisfy the demand.
]
6.4 SENSOR DATA TO BE ACQUIRED 1
Variables which are available to the Plant computers will be available to the
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j computers in the TSC and EOF. Also a select list of variables from the RMS will be available to the computers in the TSC and EOF. Regulatory Guide 1.97, Revision 2, is being used in conjunction with other documents as a guide in determining that sufficient data will be available in the ERFs to support the functions performed in these locations.
Meteorological data from the sensors on the meteorological tower will be transmitted to the TSC computer where they will be available to the DAS.
Data for the DAS will be obtained via the Plant computers and radiation moni--
toring computer.
Inputs to these computers originating from Class 1E sources i
rp0182-0373bl68
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6-4 i
.i are appropriately isolated by relays, optical isolators or operational ampli-fiers. The isolation of safety-related sources is discussed in Section 8.3 of the Midland FSAR. Cabling between sensors and the Plant computer systems uses shielded twisted pairs. As discussed in Section 6.3 above, up to 500 analog channels will be sampled at a rate of 1 sample per second, with the remainder sampled at about 0.33 samples per second. All digital inputs will be sampled once per second. Analog data will be read with a resolution of 12 bits per channel.
Data for the DAS will be obtained from the automatic scanning action of the front-end processors; manually entered data will not normally be used.
However, there is a provision for the operator to enter values for certain points which are not related to the safety parameter display system. These manually entered values will be appropriately flagged.
6.5 DATA TO BE PROVIDED FOR DOSE ASSESSMENT Data required to support an atmospheric transport and diffusion model and dose projection model will be available from the radiation monitoring computer and the meteorological tower. As shown in Figure 6-1, these data will be input to the TSC computer.
Data from the radiation computer will consist of one-minute averages of the appropriate parameters transmitted once per minute. Meteorological infor-mation will consist of 15-minute averages of the required data transmitted once every 15 minutes. The specific model to be used for the transport and diffusion calculations is currently under development.
Storage capacity and speed requirements of the model are currently being assessed to verify the capability of the TSC computer to support the model.
1 1
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.WIDLAND COMPUTER SYSTEM & EMERGENCY RESPONSE FACILITIES DATA ACQUISITION SYSTEM IN-PLANT SENSORS ISOLATION FOR IN-PLANT SENSORS SAFETY RELATED l
3 COMPUTER UNIT I UNIT 2 INPUT PROCESS 1/0 PROCESSl/0 R00M UNIT I UNIT 2 FRONT-END FRONT-END PREPROCESSOR PREPROCESSOR f_; _ _____ __ _ __ _ _ _.
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O MAIN MAIN DISK CONPUTER
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CONTROL UNIT l-DISPLAYS, UNIT 2-DISPLAYS, ROOM ALARM TYPER, ALARM TYPER, FFYB0ARDS KEYB0ARDS RADIATION MONITORING DISPLAY RADIATION AUXILLARY SHUTDOWN AUXlLLARY AUXILLARY SHUTDOWN BUILDING PANEL DISPLAY MONITORING PANEL DISPLAY COMPUTER l
FIGURE 6-1 SH l 0F 2
i MIDLAND COMPUTER SYSTEM & EMERGENCY RESPONSE FACILITIES DATA ACQUISITION SYSTEM RADIATION MONITORING COMPUTER RADIATION PRIMARY UNIT I MONITORING UNIT 2 MET.
OUTPUT OTHER COMPUTER COMPUTER COMPUTER TOWER DISPLAYS TECHNICAL SUPPORT CENTER SWITCH TSC COMPUTER b
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- -- PRIMARY DATA PATH SECONDARY OR BACKUP DATA PATH FIGURE 6-1 SH 2 0F 2
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7-1 1
q.r 7.0 DATA DISPLAY SYSTEhS 7.1 FUNCTIONAL DISPLAY DEVICES Display devices will be located in the control room, TSC and EOF for display-ing data acquired and processed by the DAS.
Two CRT displays, one for each unit, will be located in the control room dedicated to SPDS functions.
In the TSC there will be a total of five CRT displays. One will be allocated to displaying SPDS parameters and may be switched between the two units. Two displays will be provided for calling up and displaying various Plant system variables related to TSC functions. The other two CRTs will be dedicated to i
the display of in plant and offsite radiological variables and the results of the dispersion model. Two of these CRTs, including the SPDS display, will have graphic capability for displaying trend information.
A printer / plotter will be located in the TSC for making a hardcopy of any selected display. Since this produces a copy of the display shown on the CRT, it will be capable of recording graphics information.
In the EOF there will be a total of four CRT displays. As in the TSC, one will be allocated for displaying appropriate SPDS parameters and may be switched between Unit 1 and Unit 2.
Two CRTs will be available for calling up and displaying various Plant system variables, snd one will be dedicated to the display of selected radiological, meteorological and dispersion modeling data. TVo of the CRTs in the E'? have graphic capability for displaying trend information. As in the TSC, a printer / plotter will be available for making a hardcopy of any selected CRT display.
As shown in Figure 6-1, the computers in the TSC and EOF will be tied directly to the Plant computer system and thus will have access to the entire Plant computer data base.
In addition, data from the meteorological tower and selected data from the radiation monitoring computer will be input to the TSC computer, thus making this data available at all ERT locations.
Since all of this data will be incorporated into the data bases of the ERF computers, it can be displayed in a variety of formats, including graphic and trending dis-plays and summary tables. Trending information will be presented on graphic displays which have a resolution of 256 by 512 addressable elements. All of these displays will be available via operator request.
For displaying historical information, data will be collected on up to 150 pa-rameters at 2-second intervals over a period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to a trip to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> following a trip.
Over the following four hours, data will be collected at ten-second intervals.
In addition, this information can be dumped to magnetic tape which will allow for continued collection of data at ten-second intervals.
The equipment for displaying data in the ERFs will be provided by Aydin Controls and will include Model 5215 display generators, 8000 series high-resolution color monitors and Model 5115 keyboards. The data rate for this equipment will be up to 600 K bytes per second. The screen capacity of these displays will be 80 characters by 24 lines and the screen size will be 19 inches diagonal.
Intensity controls also will be provided.
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1 7-2 Special function keystrokes will be implemented in two different ways.
Special function key pads will be available. Each key will be associated with a specific predefined function.
In addition, a more extensive menu of special functions may be called up on the CRT. The desired function can be executed by entering the appropriate function number via the keyboard. Approximately 20 special functions have been planned. These are currently being developed and will include functions such as value display, value trend, point display, group display, group trend display, group trend print, etc.
Hardcopy printouts for the ERFs will be provided by a Tally Model 1612 printer and a Tektronic printer / plotter in both the TSC and the EOF. The Tally printer has a print rate of 160 characters per second, 132 characters per line and uses a standard 96-character ASCII character set.
The Tektronic printer / plotter produces an 8-1/2" x 11" copy of selected CRT displays at a rate of about 1 frame in 15 seconds. The noise generated by these hardcopy devices will be acceptable for the environments in which they operate.
The graphic display hardware is raster-driven with a resolution of 560 pixels horizontal by 336 pixels vertical. They are capable of displaying eight different colors of which only four or five will appear at one time on any given display. The data transfer rate will be of the order of 5 M bytes per second which will be consistent with the display capability of this equipment.
The refresh rate of the displays is 50 hertz and they have hardware capability for both vector and character generation.
The availability of functional display data to ERF display systems will be evaluated during acceptance testing of these systems.
It is anticipated that the maximum response time to queries for information required during an emergency situation will be less than three seconds.
If longer response times are encountered, provisions will be included to inform the operator that the request is in progress.
If displayed data is inconsistent or faulty, a one-character status suffix will be appended to the displayed value indicating the nature of the inconsistency.
Four different types of inconsistencies will be identified.
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The specific formats of the functional displays are currently under devel-opment. These displays will make appropriate use of tabular summaries, graphics and trending displays. Factors such as placement and grouping of important or related items, spacing and color, use of headers, and other display dimensions will be considered.
The operator / system interface has been designed so as to require a minimum of expertise in order to operate the system.
Specific displays and special functions can be called by entering simple numeric codes and a menu of avail-able displays and functions may be called up to help identify the appropriate code. Requests for a new display or other information must be completed within 30 seconds or the request will be canceled.
The functional display positions at the TSC are shown in Figure 2-1, and for the EOF in Figure 5-3.
As enumerated above, five displays are located at the TSC and four at the EOF. Work stations at the TSC are shown in Figure 2-1; the relationships between the displays and the people using them are indi-rp0182-0373bl68
7-3 cated. Similar information for the EOF is shown in Figure 5-3.
The large size of the CRT screens makes it possible for an adequate group of people to view the appropriate display in an emergency situation. The CRT displays will be bright enough so that room illumination controls will not be necessary.
, 7.2 SPDS All of the parameters in the Plant computer and radiation monitor computer system data bases are potentially available to the SPDS. The specific parameters to be included will be sufficient to adequately assess the safety i
status of the Plant. The unavailability of parameters required for the SPDS will be minimized by using redundant inputs monitoring the same variable whenever possible.
The SPDS displays will be placed on dedicated CRTs to aid their recognition.
These displays will consist primarily of pressure-temperature curves which will be quickly recognizable.
As discussed above, Figures 6-2, 2-1 and 5-3 show the locations of the SPDS displays in the control room, TSC and EOF, respectively. The locations of the SPDS have been coordinated with the devel-opment of these facilities so as to ensure easy access, physical compatibility and to minimize hazards.
The SPDS will not require additional staff for its operation. A key pad of l
special functions and the menu system for displaying available displays and functions will be used to facilitate the ease with which the SPDS can be operated.
As described above, data for the displays required by NUREG-0696 will be obtained from the Plant computer and the radiation monitoring computer data bases. Because of separate computers used for the Plant and ERFs, the displays will have no impact on each other.
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8-1 8.0 DATA COMMUNICATIONS
8.1 DESCRIPTION
The principal paths for the transfer of data between the DAS and the TSC, EOF, SPDS and meteorological data facilities are shown in Figure 6-1.
As illus-trated in this figure, access to this data base can be made from offsite facilities through the TSC computer.
Most of these links are in plant hard-wired data buses, except for the link between the TSC and EOF computers which consists of redundant 9,600 baud dedicated telephone lines.
8.2 GENERAL All data links have been designed to have adequate capacity and to meet or ex-ceed the unavailability requirement of 0.01.
All powered data communications equipment will be supplied from uninterruptible sources. Except for the link between the TSC and EOF, all data channels will be totally within the confines of the Plant security boundary. Further, the integrity of data channels be-tween processors is verified at least every five seconds by means of software checks. This technique provides an essentially continuous testing program of the communication links.
I 8.3 ADDED QUESTIONS FOR DATA LINKS USING EIA STANDARD INTERFACES All data channels have been designed to applicable standards. Data links using EIA standard interfaces conform to applicable standards as regards voltage levels and impedances, data rates and distances spanned, and cables and connectors.
8.4 ADDED QUESTIONS FOR VOICE-FREQUENCY LIhTS The communication channel between the TSC and EOF consists of redundant 9,600 baud dedicated telephone lines. This redundancy is provided to minimize the probability of service failures. The channel between the Plant computer and the TSC, however, consists of one link per unit. These links are totally within the Plant security boundary and can be repaired quickly in the event of failure. Also, as mentioned above, software checks will be used to test the integrity of these channels at least every five seconds so that repairs can be inrtituted immediately in the event of failure.
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9-1 9.0 SYSTEM SUPPORT REQUIREMENTS 9.1 DOCUMENTATION Complete documentation for the Midland computer system and ERF DAS will be maintained in the Plant documentation center. Operators' manuals will be available at each keyboard. Documentation for the system will cover each of the following areas:
operators' manuals, functional system descriptions, hardware documentation and programmers' manuals.
System descriptions and manuals will be written to a level of detail appropriate for their intended Standard procedures will be used to ensure that this documentation is use.
properly maintained and updated.
9.2 TRAINING The training of Plant personnel pertinent to site emergency plans and implementing procedures is discussed in SEP Subsection 8.1.1.
Operators of display systems will be trained in the use of the display system.
This training will be performed onsite using the display systems at the Plant and will include the operator's participation in operating the display system.
Training procedures will include periodic requalification of the operators of the display sytems and will include retraining of the operators to respond to changes in the system.
Maintenance personnel responsible for the DAS and display devices will be trained in the operation and maintenance of these systems. This training will include maintenance personnel participating in the actual operation and maintenance of the equipment. For leased communications equipment, the supplier will perform any needed maintenance and will provide the necessary training in the operation of the equipment.
Documentation on the training of parsonnel will be maintained by the General Office Training and Personnel Department.
9.3 QUALITY ASSURANCE Software development is proceeding according to the following formal steps:
development of functional specifications, preparation of detailed design specifications, outlining of specific programming techniques, multilevel acceptance tests and full system acceptance tests onsite. Hardware verification and validation will be included as part of the acceptance testing procedures.
Several factors will contribute toward assuring an independent quality assurance review. Hardware and software are being supplied by independent vendors. A CP Co engineer has been assigned to work with the sof tware vendor during software development and testing. Also, members of the Plant staff will participate in the full system acceptance tests. Testing procedures will include periodic sample calibration checks from individual sensors through to final operator displays.
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9-2 A system log has been maintained by the software vendor during system check-out.
It will be continued at the site. This log records system modifications, malfunctions and corrective actions taken.
9.4 RELIABILITY As illustrated in Figure 6-1 and discussed in Section 6.1, the Midland com-puter system and ERF DAS are a highly integrated multiproccessor system with redundant and interconnected components to ensure reliability.
The major subsystems are:
the front-end preprocessors, the main Plant computers, the TSC computer, the EOF computer, the communication links between the TSC and EOF, and the functional displays, including the SPDS displays.
The mean times between failures for the more complex of these subsystems have tsen evaluated.
In summary, they are:
184,199 hours0.0023 days <br />0.0553 hours <br />3.290344e-4 weeks <br />7.57195e-5 months <br /> for failure of both front-end prepro-cessors; 66,499 hours0.00578 days <br />0.139 hours <br />8.250661e-4 weeks <br />1.898695e-4 months <br /> for failure of 2 of 3 Plant computers; 1,293 hours0.00339 days <br />0.0814 hours <br />4.844577e-4 weeks <br />1.114865e-4 months <br /> for the TSC computer; and 2,431 hours0.00499 days <br />0.12 hours <br />7.126323e-4 weeks <br />1.639955e-4 months <br /> for the EOF computer.
For practical and operational reasons, the mean time to repair these subsystems has been taken as eight hours although the equipment vendor claims two hours or less.
Using these figures, the computed unavailability for the complete system is 0.00956.
As can be seen, the reliability of the TSC computer is the controlling factor in determining overall system reliability.
Since the communication link between the TSC and EOF consists of two redundant dedicated telephone lines, and the functional and SPDS displays consist of several redundant CRTs, the availability of these subsystems is significantly greater than the TSC computer. They will have little effect on overall system unavailability. For these preliminary calculations, the component mean times between failures have been based upon the hardware vendor's specifications. These figures will be revised as operating experience is accumulated and recorded in the system log.
9.5 MAINTENANCE In order to assure minimum unavailability of hardware, periodic preventative maintenance procedures will be developed and will include maintenance of equipment on a rotating basis. Maintenance support equipment will be avail-able on demand. There is a Plant procedure which addresses the calibration and verification of test equipment in order to maintain the accuracy and reliability of this equipment.
During the course of an accident, the Plant instrumentation personnel will be responsible for the maintenance of the DAS, nonleased communications equipment and display systems. These personnel will be located in the OSC and will be qualified to maintain the hardware by participating in the training programs described in Section 9.2.
In order to minimize replacement times, spare parts will be located in suffi-cient numbers to maintain the system.
Critical items will be stored onsite in the Plant warehouse. These items will be stored in such a manner that the quality of the spare parts will be substantially equivalent to the original l
equipment.
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9-3 A procedure on software maintenance and documentation will be developed to insure that changes to the software are authorized and adequately tested and validated before they are implemented.
A description and date of the change will be recorded in a manner which can be easily reviewed.
The Plant Technical Department is responsible for maintenance of all computer software including the DAS and display systems. Current staffing of the Technical Department provides adequate backup software maintenance personnel.
These personnel will be qualified to maintain the software by participating in
-the on-the-job training programs described in Section 9.2.
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10-1 10.0 JOINT PUBLIC INFORMATION CENTER (JPIC) 10.1 INTEGRATION WITH OVERALL PLANNING Information concerning the integration of the JPIC with the overall emergency plan is included in 3EP Section 7.4.
10.2 LOCATION, STRUCTURE AND HABITABILITY The JPIC will be located in a lecture theater and adjacent classrooms at Delta Community College approximately 13.5 miles east of the Plant in Bay County, Michigan (see Figure 5-1).
Delta College is readily accessible by major high-ways, I-75 and US-10, and is 6 miles from Tri-City Airport. The JPIC will be able to withstand reasonably expected adverse conditions and remain opera-tional.
The radiation doses expected when the JPIC is accessed during a design basis accident (DBA) or other specified accidents would be normal background radiation since the JPIC is more than 10 miles from the Plant.
10.3 STAFFING The initial JPIC facility supervisor will be the Midland Nuclear Plant Public Affairs Director, until the CP Co Corporate Manager of Media Relations arrives, at which time the responsibility will be transferred.
Five media relations staff members from CP Co nuclear plants, Corporate Office and Regions will be present along with adequate technical advisors and clerical support. The flow of information to the news media is discussed in SEP Section 7.4.
Access to all JPIC areas will be through security clearances.
All JPIC workers will display security clearance credentials.
Media representatives will be invited to an annual CP Co sponsored training session to include presentations on radiation, emergency plans and dissemi-nation of public information.
I 10.4 SIZE AND COMMUNICATIONS Media briefings will be conducted in a 250-seat lecture theater auditorium. A permanent stage, audio system, fixed seating and balcony for camera placement are included. Access for media briefings will be controlled through doorways; private access will be provided for JPIC staff.
There are 3 classrooms, each 20 feet by 30 feet, immediately adjacent to the lecture theater for JPIC use as support offices.
One will be assigned to CP Co staff and also serve as rumor control center; one will be assigned to the state and Midland, Saginaw and Bay County staffs; and the third will be assigned to the NRC. Each office will have two telephones and sufficient supplies and materials for communications.
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i 10-2 l
A media working area is one level below the lecture theater and support offices. This office is 30 feet wide and 230 feet long.
It will have 20 telephones immediately available with the capability to double the number within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This media working area is adjacent to a cafeteria and a graphic arts services department.
10.5 RECORDS AVAILABILITY A media information kit will be prepared to give reporters a complete back-ground file on the Midland Nuclear Plant. This kit will include operating diagrams and schematics, color and black and white photographs of the Plant and key equipment, film and videotape footage of the facility and information about the Plant history, staff and operations.
Background information about radiation will also be included.
Large visual aids of the Plant operating cycle and key components will be on display for the briefings.
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