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NUCLEAR REGULATORY COMMISSION ti j
WA%HINGTON D. C. N555
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FEB 101986 1
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MEMORANDUM FOR:
John B. Martin, Regional Administrator, RV THRU:
James M. Taylor, Director Office of Inspection and orcement-FROM:
Edward L. Jordan, Director Division of. Emergency Preparedness and Engineering Response Office of Inspection and Enforcement
SUBJECT:
SURVEY OF LICENSEES FOR INTERFACE WITH THE EMERGENCY RESPONSE DATA SYSTEM
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The policy issue of how best to obtain data from nuclear power 4cilities
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during emergencies was presented to the Commission in SECY-84-481 (enclosed).
i The Commission approved the Emergency Response Data System (EROS) option.
Briefly, the ERDS design concept includes the following:
-q 1.
Parameter inputs to ERDS would be obtained from an existing computer
-Q system at the plant (e.g. SPOS, plant computer, EOF data systems, etc.).
2.
Data will be transmitted to the NRC Operations Center via modem over a commercial telephone line or a dedicated line maintained by NRC (e.g.
ENS).
3.
A processing system maintained by the NRC will receive the data stream via modem.
The system will be designed to receive all varied da'ta. streams and will reformat the data into a consistent format.
The reformatted data will be outputed to an appropriate video display and printer. 5 d 4.
The parameter list would include those necessary to ensure that appropri-ate action is being taken with respect to offsite recommendations.
The list would be limited to those parameters involving plant status and radiological and meteorological conditions.
5.
Licensees will not be required to backfit their systems to include addi-tional parameters to match the NRC parameter list.
Data that is not available from the electronic data stream can be provided by voice commu-nication over existing phone lines.
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Contact:
J. B. Hickman, IE 492-4155 3
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John B. Martin s
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s 1ree upsetins frequency of the iscensees systems wiii determine trensmis-O 6.
s' ion frequency to NRC.
If more Wequent updates are required than those pryvided electronically by a particular licensee, the increased frequency s
fill be accomplished (for a very limited subset of parameters) by voice g A communications over existing telephone lines.s h
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The licensee will have complete control over dsth transmission.
ERDS would be " switched on" bynthe licensee.in the early stage of a declared.,
emergency.
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l Tois ' data transmission concepts has,been presented to several licensees at AIF and other meetings, and has been generally well received.
ERDS provides the potential for improving NRC response and coordination with licensees while lessqq%g the burden on licenrees in supplying data to NRC.
Two tests of the ERDS c$ncept have been conduc0.ed, with McGuire and LaSalle, and in both cases improvements in the quality 6f the assessment and in the reduction of verbal data communications were not h.
s At this point we are in the/ survey and design phase of ERDS implementation.
A contract has teen awarded to visit or coptact all sites, obtain information on T
the licensees data systems, and design /ne ERD 5 system.
In order to accomplish this effort we will need some regional hupport to schedule the site visits.
Therefore, I am requesting that you ser,d the enclosed letter to all licensees in your region by February 21, 1986, and designate an individual as a contact point to work with members of my staff.
A member of my staff will participate
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in each site visit and will be responsible for the interface of the contractor with the licensee. Your contact point should establish initial contact with the liceasee, obtain utility concurrence for the proposed visiti,' identify a -
utility point of contact, and provide the tradition &l " good guy" letter identi-fying the visiting surveyor.
Questions of policy' regarding ERDS should be i d,irected to Ken Perkins at 492-7361.
Questions on planning the si.te visits j.h (y ould @e directed to John Hickman at 492-4155.
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Enclosures:
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To Power Reactor licensees O
This letter is to inform you of an energency communications capability that the NRC is ccaMring establishing with licensed nuclear power facilities and an upcoming site visit by an NRC conuactor to obtain information on how such a system would interface with your incility.
The emergency communication capability baing considered is called the Emergency Response Data Systez (ERDS).
The ERDS concept has been determined by the NRC Te De a design which best addresses the requirements of the NRC with minimal inpact on the licensee.
The development of the ERDS concept began with an amessment of what is the NRC's role in an emergency at a licensed nuclear facility.
The Commission determined that the NRC's primary role is one of monitoring the licensee to assure that appropriate recommendations are made with respect to offsite protective actions.
To fulfill this role the NRC requires accurate, timely data on four types of parameters:
(1) core and coolant system conditions must be known well enough to assess the extent or likelihoed of core damage; (2) conditions inside the containment must be known well enough to assess the likelihood of its failure; (3) radioactivity release rates must be available promptly to assess the immediacy and degree of public danger; and (4) the data from the plant's meteorological tower is necessary to assess the distribution of potential or actual impact on the public.
A list of the particular parameters considered necescary to these assessments is included as Enclosure 1.
h Experience with the voice-only emergency communications link, currently uti-lized for data transmission, has demonstrated that excessive amounts of time are needed for the routine transmission of data and for verification or correc-tion of data that appear questionable.
Error rates have been excessive; initiations have been slow; frequency of updates have been unreliable.
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addition, the current system creates an excessive drain on the time of valuable experts at the NRC and at the f acility.
When errors occur, they frequently create false issues which, at best, divert experts from the real problems for seriously long periods of time.
At worst, incorrect data may cause the NRC to respond to offsite officials with inaccurate or outdated advice that results in i
the implementation of inappropriate protective actions.
Several options were considered for upgrading the data acquisition capabilities at the Operations Center.
The options included various means of acquiring the data: manually, automatically using existing systems, or automatically using new systems. Appropriate options for transmitting the data to the Operations Center were conside.-#:
electronically formatted data, image ^ acsimile, or by I
voice through specially gaiified communicators.
l The crittria used to empare ti.ase options involved accuracy, reliability, timeliness, completeness, cost (in dollars and expert per.sonnel), and
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backfitting requirements.
The NRL determined that automatic transmission of j
selected parameters from licen>&s' existing electronic data systems is most j
capable of providing acceptably complete and reliable data on a timely basis at j
reasonable cost witn the minimum potential for burdening licensee in an emer-gency.
Most licensees either already have developed or are developing elec-j O*
tronic data systems for their emergency response facilities (ERFs)..
Because 3
the role of the licensees' ERFs is similar to the role of the NRC during i
emergencies, the licensees' data systems already include most of the parameters i
desired by NRC.
Those few parameters which are not included in any particular l
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licensee's system can be communicated by voice over the Emergency Notification System (ENS), thus avoiding backfitting requirements on the licensee to include
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additional parameters on their electronic data systems.
Data would be accepted in whatever format the licensee uses and reformatted at the Operations Center, 5
as necessary.
Because of the diversity of data systems utilized by the licensees, the best means for extracting the NRC's parameters from each system would be determined on a case-by-case basis.
The licensees would have control over transmission and would use the system only during emergencies.
This option is the Emergency Response Data System (ERDS).
The design concept for the ERDS is outlined in Enclosure 2.
Previous discussions with several licensees and two tests of the ERDS concept 1
which were conduc'.ed with Duke Power and Commonwealth Edison have indicated that the ERDS concept has the potential to significantly improve the NRC incident response function and our response relationship with licensees.
Therefore, to determine more specifically the factors that would effect imple-mentation of an ERDS we have initiated an Effort to survey the equipment and facilities at licensees' sites and determine the hardware and sof tware require-ments of such a system.
You should expect to be contacted in the next week by a member of this regional office to arrange a site visit by a NRC Headquarters staff member accompanied by a NRC contractor to speak with you on this subject.
The visit is an information gathering process.
It is oriented toward determi-c.ation of:
The availability of a particular set of PWR or BWR parameters in digital form.
The verification and validation method, if any.
D Characterization of the available data feed point (s).
J Access will be needed to documentation and knowledgeable individuals typically from Instrumentation and Control, technical, telecommunications, and computer systems cadres within the plant staff.
Should you have any questions on this site visit please contact (Fill in name and number of regional contact).
Should you have any question on the ERDS concept in general please contact Ken Perkins with the Incident Response Branch at NRC Headquarters.
He can be reached at 301-492-7361.
Sincerely, Division of Reactor Projects
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PWR PARAMETER LISTS
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Primary Coolant Pressure System Temperatures - hot leg Temperatures - cold leg Temperatures - core exit thermocouple Subcooling margin Pressurizer level RCS charging / makeup flow Reactor vessel level (when available) 4 Reactor coolant flow Neutron flux - startup range 1
Secondary Coolant Steam generator levels System Main feedwater flows Auxiliary / Emergency feedwater flows Safety Injection High pressure safety injection flows Low pressure safety injection flows Safety injection flows (Westinghouse)
Borated water storage tank level Containment Containment pressure Containment temperatures Hydrogen concentration Containment sump levels
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Radiation Monitoring Reactor coolant radioactivity System Containment radiatior, level Condenser air removal radiation level Effluent radiation monitors Process radiation monitor. levels Meteorological Wind speed Wind direction Atmospheric stability b
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BWR PARAMETER LISTS Reactor Coolant Reactor pressure r
System Reactor vessel level
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Feedwater flow Neutron flux-Startup range Safety Injection RCIC flow HPCI/HPCS flow Core spray flow LPCI flow Condensate storage tank level Containment Drywell pressure Drywell temperature Hydrogen & 0xygen Concentration Drywell sump level Suppression pool temperature Suppression pool level Radiation Monitoring Reactor coolant radioactivity level Systems Primary containment radiation level Condenser off gas radiation levels Effluent radiation monitor Process radiation levels Meteorological Wind speed Wind direction Atmospheric stability
EMERGENCY RESPONSE DATA SYSTEM (ERDS)
G DESIGN CONCEPT
- V Data Acquisition Parameter inputs to ERDS would be obtained from an existing computer system (e.g. SPDS, plant computer, EOF data systems, etc. ) at the plant.
Data Transmission Data will be transmitted to the NRC Operations Center by modem to commer-cial telephone line or a dedicated line maintained by NRC (e.g. ENS).
Data Collection A processing system maintained by the NRC will receive the data stream by modem. The system will be designed to receive all varied data streams and to reformat the data into a consistent format.
The reformatted data will be output to CR1s and printer.
Parameter List The parameter 1ist would include those parameters necessary to ensure that appropriate protective action is being taken with respect to offsite recommendations.
The list would be limited to those parameters involving plant state.,, radiological and meteorological conditions.
O
'iceasees wili aot be required to beckrit tneir systems to iaciude addi-tional parameters to provide data on NRC's parameter list.
Data that is not available from the electronic data stream can be provided by voice over existing phone lines, i
Transmission Frequency The updating frequency of the licensees' systems will determine transmis-J sion frequency to NRC.
If more frequent updates are required than those provided electronically by a particular licensee, the increased frequency will be accomplished (for a very limited subset of parameters) by voice over existing telephone lines.
I 1
Control lhe licensee will have complete control over data transmission.
ERDS would be " switched on" by the licensee in the early stage of a declared emergency.
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