ML20237D262
Text
l January 8, 1987 William N. Stasiuk, P.E., Ph.D n Director, Center for Environmental V Health New York State Department of Health 404 Tower Building Empire State Plaza A1)any, New York 12237 -
Dear Dr. Stasiuk:
This will confirm arrangements for our meeting to discuss the Emergency l Response Data System. It is scheduled for January 16 at our Operations ,
Center located in the Maryland National Bank Building, 7735 Old Georgetown i Road, Bethesda, Maryland. I will meet you in the lobby of the MNB Building at 10:00 A.M.
~
In the morning, we will plan to discuss NRC's concept of operations and review '
the Operations Center capabilities. The afternoon will be devoted to a discussion of ERDS. I would anticipate concluding the meeting about 3:00 P.M.
l I have enclosed some background material about ERDS and a copy of HR 5192 which was introduced, but not acted on, in the last legislative session.
l If you have any questions, please call me on (215) 337-5246. I l
Sincerely, h Original SI:ned By Paul H. Lohtus ,
Paul H. Lohaus -
State Liaison Officer
Enclosure:
As Stated Distribution: (w/o Encl.) !
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.4 s "L CONCEPTUAL DESIGN OF 5
INCIDENT RESPONSE DATA LINK SYSTEM
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DESIGN CONCEPT t
SYSTEM RELIABILITY HARDv!ARE SOFTWARE DESIGN I EXPENDABILITY l
ADD FUTURE PLANTS LINK TO ERF DAT A' ACQUISli!O, SYSTEM i MAINTAINABILITY
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UTILIZATION OF PREVIOUS WORK '
. SITE DAS 1
SAFET Y PARAMETER DISPL AY RADIATION TRANSPORI SHORT IMPLEMENTATION TIME MINIMUM COSTS 1
STATE-OF-THE-ART TECHNOLOGY 1
SOFTWARE !
HARDWARE i
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INCIDENT RESPONSE DAT A LIN.< FUNCTIONS FAST DATA 1RANSMITTAL i3 INCIDE.'.I OPERATIONS CENTER DETECi INCIDENT CONDITIONS l PROVIDE TECHN! CAL INFORMATION TD TECHNICAL SUPPORT TE AM AND EXECUTE TE AM DAT A RETENSION FOR POST ACCIDE.NT ANA'_YSES O h n
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DESIGN REQUIREMENTS I
- MAX NO. OF PLANTS, 20 i 1
- NO. OF SIMULT ANEGUS INCIDENTS, 4 1
USE OF DEDICATED LEASED TELEPHONE LINES 1200 BPS l MAX NO. OF SAFETY PARAMETERS 140 LOW FREQUENCY DATA, EVERY MINUTES HIGH FREQUENCY DAT A EVERY 10- SECONDS ,
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AUTOMATIC AND MANUAL INCIDENT INITIATION MODES l
DATA STORAGE:
l l NORMAL CONDITION, 90 MINUTES l INCIDENT CONDITION, 15 DAYS j COLOR GRAPHIC DISPLAY OF SAFETY PARAMETER 5 l ALLOWS ACCESS FROM MOST AND KEPC0 IE ISDLATION AT INTERFACE WITH PLANT COMPUTER AND DAS ii l
CONTROLLED ACCESS TO COMPUTER AND BUILDING
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etANT OuTeu1 AND STATUS
SUMMARY
REPORTS l
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I O INCIDENT RESPONSE DATA LINK SYSTEM SYSTEM CONFIGURATION FIGS 4.1 AND 4 2 -
i SITE DAT A ACQUISITION SUBSYSTEM l SHORT-TERM: INTERFACE WITH PLANT COMPUTER K AERI DEVELOPED CROMEMCO-BASED SYSTEMS INST ALLED ST KORI-2. WOLSUNG-] AND KORI-1(?)
i LONG-TERM: ERF DAS DAT A COMMUNICATION SUBSYSTEM DEDICATED LEASED TELEPn0NE LINES
(]) SPEED 1200 BPS COMMUNICATION PROTOCOL ERROR CHECKING OPERATIONS CENTER COMPUTER 2 MEGA-SYTES CPU TAPE DRIVE FIXED DISK DRIVE l l
COMMUNICATION INTERFACE TERMINALS COLOR GRAPHICS TERMINALS PRINT / PLOTTER l WIDE SCREEN PROJECTOR i
FUTURE EXPANSION FIG 4,3 O
CMK/8-56
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(IRDL SYSTEM CONTINUED)
IRDL DAT ABASE MANAGEMENT SUBSYSTE!/ 'i PLANT PARAMETER DATABASE
' INCIDENT CONDITION DETECTION INCIDENT DATABASE t' DATABASE BACKUP ,
DATc LOG AND ST ATISTICAL SUMYARY ;
FIG. 5.1 .
SAFETY STATUS DI5 PLAY (BY KAERI)
APPLICATION SOFTWARE -
O TRANSIENT ANALYSIS PACKAGE:
NSSS AND BOP MODELS 1 PRED!CT FUTURE TRENDS !
o0ST ANALYSIS RADIATION TRANSPORI AND DOSE ASSESSMENT:
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SOURCE RELEASE !
J PLUME TRANSPORT RADIATION LEVEL l EXTERNAL D0cc <
INTERNAL DOSE .
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CMK/8-86
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/i VALIDATION AND VERIFICATION PROGRAM UNIT TESTING SOFTWARE MODULES HARDWARE INTEGRATION TESTING ,
DATA ACQUISITION SYSTEM DATA COMMUNICATION DATABASE MANAGEMENT FIE'. DING TESTING
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l FUNCTION TESTS EMERGENCY DRILL l
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O OPERATIONS CENTER LAYOUT c
FLOOR PLAN (FIG 5 7 ., 7-?)
CONTROLLED ACCESS EXECUTE TE AM TECHNICAL SUPPORT TEAM DUTY OFFICER COMPUTER AND OTHER EQUIPMEST DOCUMENT!
LARGE SCREEN PROJE:TCP P0hER SUPPLY
([) UNINTERRUPTABLE POWER SUPPLY (UPS)
COMPUTER EQUIPMENT ;
AIR CONDITIONING ,!
COMMUNICATION TWO DIRECT TELEPH0hE LINES TO EACH PL ANT AUTO DIALING j INTER CALLING l CONFERENCE CALLING +!
VOICE RECORDING (
ENVIRONMENT COMFORTS FOR LONG WORKING HOURS LIGHTING, 200-500 LUX [
j AIR CONDITIONING l NOISE CONTROL
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CMK/8-86
1 di O u SHORT-TERM RECOMMENDATIONS SELECT TYPE OF OPERATIONS CENTER COMPUTER MAXIMIZE USE OF EXISTING DEVELOPMENT j COMPUTER SUPPORTS l 4? PLICATION SOFTW4RE FUTURE EXPANSION PROCEED d!TH DEVELOPMENT OF IRDL DATABASE MANAGEMENT SUBSYSTEM, 4 - 6 MONTHS l
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COM?LETE SITE DAT A ACQUISITION SYSTEMS FOR REY'INING OPERATING PLANTS
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C0Y.ETE SAFETY ST ATUS DISPL AY SOFTWARE LINX IRDL WITH KORI-2. THEN LINK WITH KCRI-1. WOLSUNG-1. KORI-5. AND KORI-6 INST AL. REACTOR TRANSIENT AND RADI ATION DOSE ASSESSMENT PACKAGES AS OPTIONS i
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CMK/E-86
1 O LONG-TERM RECOMMENDATIONS I
I REPL ACE CROMEMCD-BASED SITE DAS WITH ERF DAS WHEN INSTALLED .
.2 -3 YEARS LATER i
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FURTHER IMPROVE 1RDL SOFTWARE BASED ON l OPERATIONS CENTER EXPERINCE AND USER 1 l .
FEEDBACK I
EXPAND IRDL LINK WITH NEW 0?ERATING RLANIS l
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l' Table 3.i Min num Lif ety Parameters
- 1. Primary coolant system l Pressure,WR ;
' Thermal power Power range, 10 i Source range Core exit thermocouple ,
- Hot-leg temp l
- cold-leg temp i
- Primary cool. ant loop flows Vessel level (if avail)
- P2r pressure Pzr l'evel II. Secondary system Main feedwater flows Aux / emergency feedsater floss ,
- Steam generator press !
Steam generator levels, WR I
f!I. Auxiliary coolant system '
High press safety injection flovs .
low press safety injection ficws RHR flows
( Letdown hx out flow
(
IV. Containment system Containment press Containment temp-upper comprtat Containment hydrogen conc C on t a i nmen t. sump levels V. Raciation monitoring Reactor coolant radioactivity Containment radiation levels Condenser air removal rad level !
hoble gas effluent rad levels Gaseous effluent flow rates Liquid discharge rad level !
VI. Meteorological data Upper wind speed Lower wind speed ,
Upper wind direction Lower wind direction i Precipitation in last 15 min Ambient air temp Unit vent stack flow Atmospheric staDility Lower to Upper delta T
(}
\
Note:
- refers to fast frequency transient data.
3-2
s' Energency Response Data System (ERDS) r~
b System Concept:
The Emergency Response Data System concept is a direct electronic data line to the electronic data systems of nuclear power facilities for use only during emergencies at the facilities. The data to be transmitted would be a limited set most likely available on the existing emergency data computers at the sites.
NRC would accept the data in the transmission format and at the update frequency most convenient to the licensee and the licensee would control activation of the system.
l Current Status:
l] An ERDS Requirements Analysis is currently in progress primarily being conducted l by a contractor. The requirements analysis effort consists of visits to the licensees by NRC staff to reflect agency policy and by contractor staff to I determine the design of the data systems on site and the availability of the data to be provided to the NRC. A system design will be developed as well as I
detailed equipment specifications and cost estimates. The site visits have been completed and a system design report is expected in February 1987.
Projected Implementation:
Implementation of the ERDS system is expected to begin near the end of FY 1987.
Prioritization of plants has not been done yet, but the criteria is expected to include: ease of implementation / cost, cooperativeness of licensee, and opera-O tienel history of tne feciiity. Daly iimited pient connections are expected tne first year due to high initial costs for the processing hardware and software at Headquarters. l l
i e
Document Name:
O "" S Requestor's ID:
LOPRESTI Author's Name:
john Document Comments:
O 1
i l
l l
I O
8/86 ERDS FY87 BUDGET REQUIREMENTS O l The proposed adjustment to the FY 87 budget includes a reduction in the 1
funding of the ERDS project by $500K with $530K retained to fund a dalayed ERDS implementation. )
This proposal is unacceptable for two reasons:
1
- 1. ERDS implementation will provide a major improvement to the NRC incident response capability. Therefore, timely implementation is-essential. Any funding cut which might delay implementation must be avoided.
- 2. Actual implementation of a working system will require an increased expenditure in the initial phases for the Headquarters portion of the system. A working Headquarters portion of the system, currently estimated at ~$723K, is necessary to effectively use the transmitted data from those sites where ERDS would be installed.
This makes the preservation of the funding in the initial years of l the project that much more essential. A cut in ERDS funding to
$530K might effectively prevent the implementation of a working ERDS system from any site in FY 87.
With the current requirements analysis expected to be concluded in 4
cerly FY 87, we plan to begin implementation in late FY 87. We do not f
Owantoureffortstoberestrictedbyalackoffunding.Itisessential to timely implementation of a working ERDS system that current funding lovels be maintained.
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< Rehm #5 - Emergency Response Data System (ERDS)
U System Concept:
The Emergency Response Data System concept is a direct electronic data line to the electronic data streams of nuclear power facilities for use only during emergencies at the facilities. The data to be transmitted would be a limited set most likely available on the existing emergency data computers at the sites.
NRC would accept the data in the format and at the update frequency most convenient to the licensee and the licensee would control activation of the system.
I Current Status:
An ERDS Requirements Analysis is currently in progress primarily being conducted l
by a contractor. The contract is expected to extend through 1986 with completion near the end of the year. The requirements analysis effort consists of visits to the licensees by NRC staff to reflect agency policy and by contractor staff to determine the design of the data systems on site and the availability of the l data to be provided to the NRC. A system design will be developed as well as detailed equipment specifications and cost estimates. Several visits have already taken place, specifically to Commonwealth Edison and Northeast Utilities, Rancho Seco, WNP-2, Palo Verde, San Onofre, Diablo Canyon, Surry, North Anna, i Brunswick and Robinson. Site visits are scheduled for Salem, Hope Creek, Trojan, 1
Crystal River, FitzPatrick, Nine Mile Point, and Ginna during June and July.
Problems:
The scheduling of the site visits with the licensees has proceeded slower than Q
was originally anticipated. This has been due in part to difficulties in
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, D contacting the appropriate individual in the licensee's organization and in determining a mutually agreeable time frame for the visit. Now that the initial scheduling problems have been resolved it is anticipated that future visits can be arranged while the current ones are being conducted. The total delay appears to have been about three months. Whether this time can be made up during the-project has yet to be determined.
Projected Implementation:
Implementation of the EROS system is expected to begin near the end of the current requirements analysis effort. Although the requirements analysis will more accurately determine the cost of implementation current estimates are:
O Total-Site Costs: (Based on 114 units)
Hardware @ $6.5 K/ unit $ 740 K Software @ $21.8 K/ unit $2,486 K Design @ $3.2 K/ unit $ 367 K !
l Implementation @ $10.1 K/ unit $1,155 K i
Headquarters Costs:
Hardware $ 58 K Software $ 270 K Design and Implementation $ 395 K-
-l Total $5,471 K ,
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NOTICE OF OFFICE OF M AN AGEMENT AND BUDGET ACTION j-t,
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TO: STEPHEN SCorT ACTION DATE NUCLEAR REGULATORY 00MMISSION WASHINGTON, D.C., 20555
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Nuclear Regulatory Commission f 05/02/35 '
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ON 04/29/86, YOU REQUESTED APPROVAL OF THE F3LLOWING INFORMATION COLLECTION:
TITLE: EMERGENCY RESPONSE DAT A SYSTEM REQUIREMENTS ANALYSIS ,
AGENCY FORM NOS.- '
,f i IN ACCORDANCE WITH THE PAPERWORK REDUCTION ACT, WE HAVMIAEEN THE FOLLOUIN3 l ACTION ON THIS INFORMATION C3LLECTION: ;
APPROVED FOR USE THROUGH 04/30/87. OMB NO. 3150-0134.
THE OFFICE OF MANA3EMENT AND DUD 3ET CONTROL NUMBER MUST BE DISPLAYED IN
- CORDANCE WITH 5 0FR 1320. UNLESS OTIIERWISE PR3VIDED IN " REMARKS,"
&IRATIONDATESMUSTALSOBEDISPLAYEDAS REQUIRED BY 5 CFR 1320. r, EFFECT ON BURDEN: RESPONSES REPORTING HOURS PREVIOUS STATUS 0 0. ,
NEW STATUS 60 2,069 DIFF E.B EN C E 60 2,080 l'
EXPLANATION OF DIPPERENCE: i s g' ADJUSTMENTS (
CORRECTION-ERR 3R 0 s0 i CORRECTION-REESTIMATE D 0 CHANGE IN USE O y 0 PROGRAM CHANGES INCREASE 60 2,080 j DECREASE O O '
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j NOTICE OF 3FFICE OF MANAGE!!ENT AND BUDGET ACTION P4:;E 2 IB NO. 3150-0134 A BSTR ACT:
- NUCLEAR dEAETORS, NUCLEAI( P3WFR PL ANT SA FETY' 1
! NRC I. REQUESTIN3 DATA ON THE DESIGN FOR OF EMER3ENCY DATA SYSTEMS OF
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NUCLEl}yt s f0WEy PDANTS IN ORDER
NRC IO DESIGN ITS " EMERGENCY RBSPONSE' t D ATA S YSTEM." ,N f IN T ' l
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) ALLOUANCE LETTER: NO FUNChIDW: MULTIPLE FUNCFIONS ON PLAN: NO 4 ,
EXCEID DUDGET: NO 3504(Bl: N/A '
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', NO. OF FORMSi 1 USE: PUBLIC REQUEST: NEW -
RESPONDENTS: 60 60 HOURS: 2,080-AFFECTED PUBLIC: BUS /INSI ItESPONSE{:
S D AL1, Bt'SINESS: NO ACTIVITY TYPE: 999
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/ j PURP'CSEr. PLAN MGMT j 1 F REQUENCY: OTHEE l COLI.FCTION METii0D: MAIL S/A R ET'E'NTID N: COLLECTION AGENT: RQSING DPT,9;;CT CONFIDENTIALITY: NO COMPULSORY STATUS: VOLUNTARY ,
FEDERAL COST: 1 PUBE C 03ST: '
F 7IEWER: JEFFERSON B. IIILL U '
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i I APPROVED B7: ! /S/J AM ES B. MACRAE FOR !Oi/ ICE OF iNFORMATION 105/02/B6 !
!5N!,hdEGULATORY AFFAIRS ! .
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1PORTANT: BECAUSE THIS INFORMATION COLLECTI3N HAS BEEN APPROVED, PLEASE SEVD 70 THE 3.H.B. AS S30N AS AV AILADLE: ONE COPY 3F THE .Fl%51 PRINTED (OR OTHERWISE ,
R EPR O DUC ED) REPORT FORM, OR DEPOR $?ING
- OX PEC3RDKEEPING tflQUIR EM ENT, TRANSMITTAL LETTER, INSTRUCTIONS, AND ANY T3 UMENT2'bEING SENT T3 Ef 7ti, R ES PONDENT.
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INTRODUCTION Describe NRC Emergency Response ROLE 1
, j Monitor the licensee to assure appropriate protective action is being taken With respset to offsite recommendations. -
Support the licensee (technitta,1 analysis and logistic support) .
, Support offsite authorities,,iincluding confirming the licensee's recornendation to offsite atichorities.
i Keep other feder*21 agencies and entities informed of the status of the ine' dent. :.
t Feep the abdia informed oO the NRC's knowledge of the status of the incident, including coordination with other public affairs groups.
Brieflj discuss objectives of ERDI-Mission oriented liOT NDL (Eue attached for more detail)
Ottly during event ( ALERT) $
Lessen impact on Licensee communicator LesssubjecttoerrorthanvoNdadata .-
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s O ERDS (See attached for more detail)
Identify limited parameters required (typically 60)-
(See attached list)
Least impact on licensee Will accept data in licensee format Will accept data at licensee frequency of updates May need some software to assemble data points If equipment is needed to deliver data stream from licensee port NRC will provide (eg, MODEM)
Demonstration with Commonwealth Edison and Duke Power (See attached)
Very effective data capture Less ENS voice traffic and higher quality discussions
,g/ Higher quality and prompt assessments
! Provided adequate basis for confirming PM recommendations Licensee will activate data stream (OFF/ON Switch)
Most likely at ALERT level.
Not intended to provide earlier data.
Realtime data only No flight recorder concept (earlier data provided by voice)
INVITATION Visit NRC Operations Center QUESTIONS O
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} EMERGENCY RESPONSE DATA SYSTEM (ERDS) system Concept:
The Emergency Response Data System concept is a direct electronic data line to the electronic data streams of nuclear power facilities for use only during emergencies at the facilities. The data to be transmitted would be a limited set most likely available on the existing emergency data computers at the sites. NRC would accept the data in the format and at the update frequency most convenient to the ,
licensee and the licensee would control activation of the system. ,
l Current Status:
1 An ERDS Requirements Analysis is currently in progress primarily being conducted by a contractor. The contract is expected to extend through 1986 with completion near the end of the year. The requirements analysis effort consists of visits to the licensees by NRC staff to i l
reflect agency policy and by contractor staff to determine the design of the data systems on site and the availability of the data to be provided to the NRC. A system design will be developed as well as I
(]) detailed equipment specifications and cost estimates. Several visits I have already taken place, specifically to Commonwealth Edison, Northeast Utilities, Virginia Power, Sacramento Municipal Utility District, Arizona Public Service, Southern California Edison, l Washington Public Power, and Pacific Gas and Electric.
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U STATUS OF ERDS DEMONSTRATIONS
- July 19,1984 Duke Power Company McGuire Successfully conducted test of data transmissions from the Duke system. Data set limited to a list of 69 specific data points to test the appropriateness of the NRC's parameter list. System has been maintained and allows access to all Duke facilities during events and !
exercises. '
- August 13,1985 Commonwealth Edison Co. LaSalle Successfully conducted test of data transmission from the LaSalle system. As part of this test the LaSalle computer called our computer to initiate the transmission. In addition this transmission required that we translate the data from an incoming ASCII character string to text. The data set consisted of 60 specific data points. System is expected to be maintained at both facilities for possible future use.
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- Automatic activation based
- Licensee activated.
on plant parameters. Probably at Alert level.
Potential regulatory tool.
- Data continuously recorded
- Data provided under emergency at Operations Center. conditions only.
- Some connections direct to
- No direct connection.
plant sensors, potentially degrading instrumentation.
- Initial data list about 400
- Data list about 60 variables, variables, later reduced to comparable to SPDS set."
125.
- High cost due to requirement
- Relatively low cost due to usage for a totally new system.. of existing systems.
- Extensive backfit, requiring
- Minimal backfit, software for dedicated onsite computer. data assembly and modem for transmission.
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- Increased data may encourage
- Limited data list necessary NRC to direct plant operation. to assess plant safety.
- Accuracy and reliability are
- Accuracy and reliability are excellent. excellent.
- Timeliness is excellent.
- Timeliness is expected to be excellent. Initiation will depend on system configuration.
- Completeness is potentially
- Completeness is expected to be excellent due to parameter excellent. Site surveys have availability. indicated good parameter coincidence.
- Reduces data gathering and
- Reduces data gathering and j transmission burden on transmission burden on !
licensees. licensees. Supplemental voice transmissions have been reduced. 1 0
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O PARTICIPANTS NAME ORGANIZATION PHONE
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