ML20062H459
| ML20062H459 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 11/27/1990 |
| From: | John Jolicoeur NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Annino E NORTHEAST UTILITIES |
| References | |
| NUDOCS 9012040321 | |
| Download: ML20062H459 (39) | |
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'd UNITED STATES 8\\
i NUCLEAR REGULATORY COMMISSION
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November 27, 1990 Docket Nos. 50-213 50-245 50-336 50 423 Mr. Edward L. Annino i
Northeast Utilities Post Office Box 270 Hartford, CT 06141 0270
Dear Mr. Annino:
I would like to take this opportunity to thank Northeast Utilities for volunteering to participate in the Emergency Response Data System (ERDS).
I am sure that the implementation of ERDS will prove to be beneficial both to the NRC and to Northeast Utilities.
Enclosed you will find a survey designed to provide the hardware, communications, data point and administrative information necessary for our contractor to design the ERDS system interface and data base for your plants.
Please note that one copy of the Data Point Library Reference File form (Enclosure 2) will be needed for each ERDS data point.
This reference file will be used to provide physical significance to the numerical data transmitted over ERDS for members of the NRC emergency response organization.
Each reactor unit is treated as an individual plant by ERDS, therefore, a separate data feed is required for each of your units.
Please complete the enclosed sucvey and Data Point Librarv Reference File for each of your reactor units and return them to me with a r.opy to Tony LaRosa, the ERDS project manager at NLS/El Division, at the folkwing addresses:
Jotn R. Jolicoeur U.S. Nuclear Regulatory Commission Mail Stop MNBB 3206 Washington, DC 20555 Tony P. LaRosa NUS Corporation El Division 545 Shoup Ave.
P.O. Box 50736 Idaho Falls, Idaho 83405 This request is covered by Office of Management and Budget Clearance Number 3150 0150 which expires March 31, 1992.
The estimated average burden hours is 32 person hours per licensee response, including staff snd management review and preparation of the requested response.
These estima'ed average burden hours pertain only to those identified response-related matters and do n.01 include the time for any follow on implementation.
Send comments regarding this burden estimate or any other aspect of this collection of informationff 9012040321 901127 1=
PDR ADOCK 05000213 L
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e November 27, 1990
. including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, DC 20555; and to the Paperwork Reduction Project (3150 0150),
Office of Management and Budget, Washington, DC 20503.
I am looking forward to working with you to ensure a smooth impicmentation of ERDS at your plants.
If you have any questions, please contact _ Tony LaRosa at (208) 524-9227 ormeat(301)492-4155. Again thank you for your continued support of the ERDS program.
Sincerely, Original signed by:
John R. Jolicoeur Incident Response Branch Division of Operational Assessment Office for Analysis and Evaluation
Enclosures:
1.
ERDS Communications Descriptions and Survey Questionnaire 2.
Data Point Library Reference File 3.
Data l.'.nt Library Reference file Definitions
- 48. Critical Safety function Parameters for BWRs 4P. Critical Safety function Parameters for PWRs 5.
Engineering Units Coding Scheme 6.
Zero Reference Coding Scheme 7.
Coding Scheme for Unit Name and Unit 10 8.
Computer Point Selection cc w/ encl:
T. LaRosa See next page DISTRIBUTION ELJordan DFRoss 00A R/F NRC PDR ABWang, NRR GGZech
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. H. F. Haynes, Nuclear Unit Director J. S. Keenan, Nuclear Unit Director Millstone Unit No. 1 Millstone Unit No. 2 Northeast Nuclear Energy Company Northeast Nuclear Energy Company Post Office Box 128 Post Office Box 128 Waterford, Connecticut 06385 Waterford, Connecticut 06385 Charles Brinkman, Manager Board of Selectmen Washington Nuclear Operations Town Hall C-E Power Systems Haddam, Connecticut 06103 Combustion Engineering, Inc.
12300 Twinbook Pkwy J. T. Shedlosky, Resident Inspector Suite 330 Haddam Neck Plant Rockville, Maryland 20852 c/o U. S. Nuclear Regulatory Commission Post Office Box 116 East Haddam Post Office J. P. Stetz, Nuclear Station Director East Haddam, Connecticut 06423 Haddam Neck Plant Connecticut Yankee Atomic Power Company RFD 1, Post Office Box 127E East Hampton, Connecticut 06424 G. H. Bouchard, Nuclear Unit Director Haddam Neck Plant Connecticut Yankee Atomic Power Company RFD 1. Post Office Box 127E East Hampton, Connecticut 06424
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Mr. Edward J. Mroczka Senior Vice President l'
Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06141-0270 l
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cc:
i Gerald Garfield, Esquire R. M. Kacich, Manager Day, Berry and Howard Counselors at Law Generation Facilities Licensing City Place Northeast Utilities Service Company Post Office Box 270 Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-0270 W. D. Romberg, Vice President O. O. Nordquist Nuclear Operations Director of Quality Services Northeast Utilities Service Company Northeast Utilities Service Company Post Office Box 270 Post Office Box 270 Hartford, Connecticut 06141-0270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Regional Administrator Radiation Control Unit Region I Department of Environmental Protection U. S. Nuclear Regulatory Commission State Office Building 475 Allendale Road Hartford, Connecticut 06106 King of Prussia, Pennsylvania 19406 Bradford S. Chase, Under Secretary First Selectmen Energy Division Town of Wsterford Office of Policy and Management Hall of Records 80 Washington Street 200 Boston Post Road Hartford, Connecticut 06106 Waterford, Connecticut 06385 S. E. Scace, Nuclear Station Director Millstone Nuclear Power Station W. J. Raymond, Resident Inspector Millstone Nuclear Power Station Northeast Nuclear Energy Company c/o U. S. Nuclear Regulatory Commission Post Office Box 128 Post Office Box 811 Waterford, Connecticut 06385 Niantic, Connecticut 06357 C. H. Clement, Nuclear Unit Director Millstone Unit No. 3 M. R. Scully, Executive Director Northeast Nuclear Energy Company Connecticut Municipal Electric Energy Cooperative Post Office Box 128 30 Stott Avenue Waterford, Connecticut 06385 Norwich, Connecticut 06360 Ms. Jane Spector-Federal Energy Regulatory Commission Michael L. Jones, Manager Project Management Department 825 N. Capitol Street, N.E.
Massachusetts Mur.icipal Wholesale Room 8608C Electric Company Washington, D.C.
20426 Post Office Box 426 Ludlow, Massachusetts 01056 Burlington Electric Department c/o' Robert E. Fletcher, Esq.
271 South Union Street Burlington, Vermont 05402
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n ENCLOSURE 1 i
ERDS COMMUNICA110NS DESCRIPil0N AND SURVEY OVEST10NNAIRE The following is a questionnaire pertaining to the Nuclear Regulatory Commission's (NRC) Emergency Response Data System (ERDS).
It consists of a series of questions concerning plant 1/0 points, software protocols, data formats, transmission frequencies, and other plant computer specific information to be used in the ERDS computer database files.
Also, included here are descriptions and examples of data streams that the NRC is expecting to see transmitted over the communication line, i
The purpose of collecting the data is to develop a plant specific database that will be retrieved into the ERDS once the sy. stem is activated by a utility, it will also be used to design and implement ERDS software that can receive the i
utility's data transmission. In essence, this information will provide the basis for building a profile of the plant in the EROS database.
In some cases, the 1/0 point data may be distributed over several computers.
The ERDS considers this situation a multi-feeder site and Section IV must be filled out for each feeder.
't 1
i Rev. 0,A NRC 314 q.
N 19 1
i
O ENCLOSURE 1 1.
CONTACTS Note:
Please provide name, title, mailing address, and phone number.
A.
Survey Coordinator (i.e., contact for later clarification of questionnaire answers):
B.
Computer Hardware Specialist (s):
C.
Systems Software Specialist (s):
D.
Application level Software Specialist (s):
E.
Telephone Systems Specialist (s):
Rev. 0 A NRC 314 N 19 2
~ ~
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ENCLOSURE 1 EROS COMMUNICA110NS DESCRIP110N A.
Hardware
.The following hardware will be supplied:
for a single feeder site:
Codex 2234 modem V.22 2400 bps, asynchronous, auto dialing, auto-answer, error correcting, using the AT command set P
for a multiple feeder site:
Codex 6015 multiplexer, Codex 2260 modem V.32 9600 bps, asynchronous, auto dialing, auto-answer, error correcting, using the AT command set e
The modems are intended to be operated in the auto reliable link mode (referred to as MNP in the modem man'uals) with speed conversion and flow control enabled.
Speed conversion allows the computer to communicate with the modem at a baud rate which is independent of the baud rate the modem is using to communicate with the I
remote modem. This feature is important because the modems have the ability to adjust their transmission rate downward if the remote modem is operating at a
. lower speed. However, in order to use speed conversion, the site computer must support some form of flow control.
Three types of flow control are supported.
by the modems:
XON/X0FF,:RTS/ CTS, and DTR/ CTS.
All of the above features are discussed in the modem manuals, f
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Rev. 0.A NRC-314 N 19 3
l t
i ENCLOSURE 1 B.
Software i.
Data Transmission All transmissions, from both the site and the ERDS, will be terminated with a carriage return (<CR>).
Site will initiate a link request in ASCll using:
a.
the three character site designatcr, the word LINK, local site time and date in the format MM/DD/YY/HH:HM:SS, and a <CR>.
If the site does not receive a response from the ERDS within one minute, it should send another link request message and continue sending them
.at one minute intervals.
If more than five minutes elapses without a response, site personnel should notify the NRC before disconnecting the
- line, i
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b.
ERDS will respond in ASCll with:
the three character site designator, the word ACCEPTED or DENIED, and a (CR>.
If the ERDS responds with the denied mtssage, the site should wait one minute and then send a link request message and continue sending them at one minute intervals.
If more than five minutes elapst; without a response, site personnel should notify the NRC before disconnecting the line.
Rev. 0.A NRC 314 4
N 19 i
x
ENCLOSURE 1 When the ERDS is ready to receive data, it will send an initiate message c.
in ASCll using:
the three-character site designator, the word INITIATE, and a <CR>'.
If the ERDS does not send an _ initiate message within one minute of the accept message, the site should send the link request message (described in Section !!.3.i.a.).
d.
Upon receipt of the initiate message, the plant begins transmission of data at a 15 second rate.
The data string consists of:
a header containing the three-character site designator and date and time in the format MM/DD/YY/HH:HM:SS, the data packet sequenced with point identifier, value, and quality tag,
'a trailer containing the checksum value of the data packet, and a <CR>.
When the site or ERDS wishes to terminate the connection, an ASCII p
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message will be sent containing:
the three-character site desi_gnator, the word TERMINATE, and a <CR>.
r f.
If_a site.is inadvertently terminated (due to loss of communications
_or, receipt'of terminate mes' sage) and the incident is still underway, the site should reconnect with the ERDS by redialing and using the reconnect. link request message.
This message is in AScil and will Rev. 0.A NRC 314 5
N 19
ENCLOSURE 1 contain:
i i
the three character site designator, the word RECONNECT, local site time and date in the format MM/DD/YY/HH:MM:SS, and a <CR).
Upon receipt of this message, the ERDS will respond with the accept and initiate messages as described in Sections II.B.I.b and ll.B.i.c.
If the ERDS responds with a link deny message (described in Section II.B i.b), the site should stop trying to reconnect and send a link request message (described in Sect. ion ll.B.i.a).
If the ERDS does not respond to the site's reconnect request within one minute, the site should send another reconnect request and continue sending reconnect requests once a minute, if more than five minutes elapses without a response, site personnel should notify the NRC before disconnecting the line.
It is the responsibility of the site to monitor the outgoing line for loss of communications.
l l
Rev. 0.A NRC 314 N 19 6
G ENCLOSURE 1 ii.
Data format The following three delimiters have been identified:
(1) field delimiter (*),
(2) data set delimiter (\\), and (3) carriage return (<CR>).
f Note:-
The length of the messages sent by the ERDS (e.g., ACCEPTED, DENIED, INITIATE, TERMINATE) are variable and it is recommended that the site software use the data set delimiter as the message delimiter for messages received from the ERDS.
Link requests will be in ASCll as described in 1.1.a, with each field a.
separated by a field delimiter and the request.irminated with a data set delimiter.
For example, pal
- LINK *01/12/89/ll:48:50\\<CR>.
b.
The ERDS response will be in ASCll as described in !!.B.i.b. with each field separated by a field delimiter and the response terminated with
'a data set delimiter.
For example, pal
- ACCEPTED \\<CR>.
When the ERDS is ready to receive data it will respond in ASCII as c.
described in II.B.i.c with each field separated by a field delimiter and the response terminated with a data set delimiter.
For example, pal
- INITIATE \\<CR>..
- d.. Data streams will be in ASCll and will consist of three parts (header, data, and trailer) as described in II.B.i.d. with each field separated by a field delimiter and each of the three parts separated by a data set.alimiter.
For example, Header:
pal *01/12/89/ll:50:30\\
'B21CP004* 0.l'34E+00*3*.....(for each parameter)\\
Data:
2 Trailer:
0000056000\\<CR>
1 Rev. 0.A NRC-314 7
N 19 l
~ - - -
l ENCLOSURE 1 The point identifier may be up to 12 characters in length, e.
f.
The value may be up to 20 characters in length.
- 9. 'The following quality tags will be accepted by the ERDS:
Good
=0 Value is within range tolerance for discreet points or input points are within tolerance for composed points.
Off-scan 1
Point is currently out of.
service.
Suspect
=2 Value is not bad yet should not be considered good. This quality will occur primarily on composed values when enough good inputs are present to allow the calculation to be made yet a bad
-quality on other inputs may make the result questionable.
Bad
-3 Value is not within tolerance for discreet points or calculation of a composed point may not be made due to the qualiti,es of its inputs.
Unknown 4
No quality indicator available.
Operator Entered
=5 Value has been manually entered, overriding the discreet or composed value.
Rev. 0.A NRC-314 N 19 8
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1
'4 ENCLOSURE 1 1
High Alarm 6
Value is in high alarm.
f Low Alarm 7
Value is in low alarm, i
h.
The checksum which accompanies each update set will be an integer value calculated by summing each of the bySs3 vf the transmission, up to and including the dataset delimiter following the body of the update set (the body of the update set being the portion containing the parameter.
{
value, and qualitv indications). This integer checksum value will then.
i be encoded into the update set as a 10 digit value, left padded with zeros as required to fill the 10-digit field. The checksum is the sum of the transmitted bytes.
l 1.
The reconnect link request iessage will be in ASCII as described in Section II.B.i.f with each field separated by a field delimiter and the request terminated with a data set delimiter.
For example, pal
- RECONNECT *01/12/89/ll:48:50\\<CR).
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Exceptions Please note any exceptions which must be taken to Section 11 and explain why.
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-NRC-314 11 N-19
.T ENCLOSURE 1 111.
SELECTION OF DATA FEEDERS A.
How many data feeders are there (six maximum)?
R.
Identify the' selected data feeders and provide the following for each:
(1) a short description of the categories of data points it will provide (e.g., met, rad, or plant data points, by unit) and (2) the rationale for select.ing it if another system can also provide its categories of data points.
' C.
Which data' feeder is the site time determining feeder? This should be the
. feeder which is providing the majority of the data points.
(
Rev. 0.A NRC-314 12 N-19
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ENCLOSURE 1 IV.
DATA FEEDER INFORMATION Note:
A new Section IV must be filled out for each feeder system selected.
A.
General Questions i,
Identification of Data feeder What is the name in local parlance given to this data feeder (e.g.,
a.
Emergency Response Information System)? Please give both the acronym and the words forming it.
k b,
is this the site time determining feeder?
W. hat is the update frequency of this feeder (in seconds)?
c.
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' Identify the manufacturer and model number of..the data feeder hardware.
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'$ 1 c.. What method of: timekeeping is' implemented on this feeder -system e
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4-ENCLOSURE 1 iii.
Data Communication Details
- a. -Can this data feeder provide asynchronous serial data communication (RS-232 C) with full modem control?
b.
Will this feeder transmit in ASCII or EBCDIC?
1 Can this feeder transmit at a serial baud rate of 2400 bps?
If not, c.
at what baud rate can it transmit?
-d.
Does the operating system support XON/X0FF flow control?
- 1. Are any problems foreseen with the NRC using XON/X0FF to control the transmission of data?
If it is not feasible to reconfigure a serial port for the EROS _ linkup e.
(i.e., change the baud rate, parity, etc.), please explain why.
4 f.
Can the serial port dedicated to the ERDS be configured so that the NRC need not, emulate a specific brand _of-terminal (i.e.,
can it be configured to be a " vanilla" terminal)?
i.
Rev. 0.A NRC 314 15 N 19
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fT iv._ Data Feeder Physical ='.nvironment'and Management hg y
a.. ;Where is the data feeder located in-terms of the TSC, E0F, and control.
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0 ENCLOSURE 2 DATA PolNT LIBRARY The Data Point Library is a site specific database residing on the ERDS computer which expands upon the basic information in a typical data point dictionary.
The data being displayed at the NRC's Operations Center for the ERDS parameter will be the same as the plant's Emergency Response Team's data. That is, it will have the same value, timestamp, and be in the same engineering units.
This requires that the Operations Center personnel adjust their thinking to accommodate the plant, functioning in terms of the plant's unique design and communicating with the plant's Response Team in the latter's unique engineering and operational " language", in order to do this, the Operations Center personnel need information which relates the data both to the plant's design and to the manner in which the plant's team utilizes and reacts to the data.
The types of information contained in the Data Point Library are the data point identifier, description, engineering units, range, alarms and/or technical specification limits and engineering sy3 tem data.
There will be one record in the plant's Data Point Library for each data point the plant will be sending to the ERDS.
Because the points selected for transmission to the ERDS are indicative of plant
" health" and are associated with Critical Safety Functions, they are the indicators the plant's Response Team uses to determine the proper actions to take
.to mitigate _an incident. Where required and useful, the Data Point Library will present textual information to the Operations Center user to provide information supplementing the point's value which will be useful in understanding 'how the plant team interprets the data. For instance, associated with.a transmitted data point. representing the reactor vessel level, the Data Point Library. should contain the physical zero reference point, conversion factor for the height above the top of active fuel, type of detectors, effects of running reactor coolant
- pumps, effects of cold calibration, effects of elevated containment temperature, etc.
Associated with a reactor water storage tank level transmitted as a percentage should be the capacity of that tank in gallons, number of reactor quality water stcragt tanks at the plant site, zero reference point conversion factor fr m, percent to gallons, etc.
Rev. 0.A NRC-314 N-19 1
( y
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gs ENCLOSURE 2.
The Data. Point. Library will' be particularly useful to the Operations Center-user l
4 when evaluating the plant's action in predicting aff site radioactive releases.~
e g-Associated with an' effluent gaseous release data point expressed in CPM, the Data O
Point Library Reference Sheet should indicate thic assumptions regarding isotopic a
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mix, the current calibration factors of detectors, the discharge point or points
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for monitored releases, expected stack flow rates Lnder various fan combinations, and any default values used by the plant team in '. heir calculations.
l Two examples of typical Data Poi _nt Library entries are included..The first is an example for a BWR-and the second-is'an example for a PWR.
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ENCLOSURE 2 BWR DATA POINT LIBRARY REFERENCE File DATE:
06/05/89 REACTOR UNIT:
XYZ DATA FEEDER:
N/A NRC ERDS PARAMETER:
(ST LEVEL POINT ID:
C34SZO4 PLANT SPEC POINT DESC.: CS TIM 1A LVL GENERIC /COND DESC.:
Condensate Storaae Tank A level ANALOG / DIGITAL:
A ENGR UNITS /OlG STATES:
ENGR UNITS CONVERSION:
Each 1% = 1692 Gallons MINIMUM INSTR RANGE:
0 MAXIMUM INSTR RANGE:
100 ZERO POINT
REFERENCE:
SEALEV REFERENCE P0lNT NOTES:
At 0%'245.000 Gals Remain in Tank PROC OR SENS:
P NUMBER OF SENSORS:
2 HOW PROCESSED:
Averaae SENSOR-LOCATIONS:
245,000 Gal Above Tank Bottom ALARM / TRIP SET POINTS:
Low level At 12%
NI DETECTOR POWER 1
SUPPLY CUT-0FF POWER-LEVEL:
N/A NI DETECTOR POWER SUPPLY TURN-ON POWER LEVEL:
N/A INSTRUMENT FAILURE MODE:
Low Rev. 0.A NRC-314 3
N-19
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ENCLOSURE 2 TEMPERATURE COMPENSATION
.FOR OF TRANSMITTERS:
'N/A-f LEVEL REFERENCE LEG:
N/A UNIQUE SYSTEM DESC.:
This averaaed sensor readina is for the normally used volume of the tank. The remainina 245.000 aallons are monitored by two discrete
' alarms at 150.000 and 50.000 callons total remainino tank contents.
Total tank volume is 414.200 aallons.
NOTE:
A second identical tank normally dedicated to XYZ Unit 1 is available for
' cross c' onnectino to this tank at the bottom (ECCS) ' suction line.
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.Rev. 0.A NRC-314
- N-19'
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ENCLOSURE 2 PWR DATA POINT LIBRARY REFERENCE FILE DATE:
06/05/89 REACTOR UNIT:
ABC DATA FEE 0ER:
ERIS NRC ERDS PARAMETER:
AX-FD FL 1/A POINT 10:
AF105A PLANT SPEC-POINT DESC.: AFW Flow SG 11 MTR GENERIC /COND DESC.:
AFW Flow SG 11 Frm Elec AFW Pumo ANALOG / DIGITAL:
A ENGR UNITS / DIG STATES:
GPM ENGR UNITS CONVERSION:
N/A MINIMUM INSTR RANGE:
0 MAXIMUM INSTR RANGE:
500 i
ZERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES:
N/A PROC OR SENS:
S NUMBER OF SENSORS:
1 HOW PROCESSED:
N/A SENSOR LOCATIONS:
On Line To SG 11 Outside Containment ALARM / TRIP SET POINTS:. Hiah Flow At 500 GPM NI DETECTOR POWER SUPPLY CUT-0FF' POWER LEVEL:
N/A NI DETECTOR POWER SUPPLY TURN-0N POWER LEVEL:
N/A INS 130 MENT FAILURE MODE:
Low Rev, 0.A NRC-314 5
N-19
a 3
ENCLOSURE 2 l
TEMPERATVRE COMPENSATION FOR DP TRANSMITTERS:
N/A
-LEVEL REFERENCE LEG:
N/A UNIQUE-SYSTEM DESC.:
There are one electric and two turbine driven AFW oumos.
The electric oumo has dedicated discharae lines to each SG.
The flow element for this coint reoresents the last sensor orior to the line enterina containment.
The two turbine-driven cumos use separate cioina to the SGs.
Maximum rated flow for this Dumo is 450-GPM.
Shutoff head is 1200 PSIG.
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- N 19-l-
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e ENCLOSURE 2 PWR DATA POINT LIBRARY REFERENCE FILE DATE:
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REACTOR UNIT:
DATA FEEDER:
NRC ERDS PARAMETER:
POINT 10:
PLANT SPEC POINT DESC.:
GENERIC /COND DESC.:
ANALOG / DIGITAL:'
ENGR UNITS / DIG STATES:
ENGR UNii5 CCN'.'ER910N:
MINIMUM INSTR RANGE:
MAXIMUM INSTR RANGE:
ZERO POINT
REFERENCE:
REFERENCE POINT NOTES:
PROC OR SENS:
NUMBER OF SENSORS:
HOW PROCESSED:
SENSOR LOCATIONS:
ALARM / TRIP SET POINTE:
NI DETECTOR POWER SUPPLY CUT-OFF POWER LEVEL:
NI DETECTOR POWER SUPPLY TURN 0N POWER LEVEL:
INSTRUMENT FAILURE MODE:
Rev. 0.A NRC-314 N-19 7
1 e
- a. "
ENCLOSURE 2 TEMPERATURE COMPENSATION FOR OP TRANSMITTERS:
LEVEL REFERENCE LEG:-
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UNIQUE SYSTEM DESC.:
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w ENCLOSURE 3 DATA POINT LIBRARY REFERENCE FILE DEFIHlil0NS DATE:
The date that this form is filled out or modified.
(Eight characters)
REACTOR UNIT:
The nuclear power plant name and abbreviation from the enclosed list of sites.
(Three characters)
DATA FEEDER:
If there is more than one data feeder for your system, enter the acronym for the data feeder from which the point comes, if there is only one data feeder, enter "N/A" in this field. (Ten characters)
NRC ERDS PARAMETER:
One of the parameters from the enclosed BWR or PWR parameter list.
A single value should be transmitted for each parameter for each loop.
If not on the list, insert "Not Listed" or "NL".
(Twelve characters)
POINT ID:
Alphanumeric point description used to label the point during transmission.
(Twelve characters)
(
PLANT-SPECIFIC Licensee computer point description for the transmitted POINT DESCRIPTION:
point.
(Forty characters)
GENERIC OR CONDENSED Parameter description from the enclosed list of points DESCRIPTION:
for a BWR or PWR, If not on the list, condense the plant specific point description.
(Thirty two charac-ters)
ANALOG / DIGITAL:
"A" if the signal is analog or numerical or "0" if the signal is off/on.
(One character)
ENGINEERING UNITS Engineering units used by the licensee for display on OR DIGITAL STATES:
licensee output devices.
Use the engineering units abbreviations from the enclosed list when possible.
When specifying pres:9re, use '" PSIA" or "PSIG" rather than " PSI".
For digital signals, give the "0FF" and "0N" state descriptors.
(Twelve characters)
ENGINEERING UNITS Notes abcut any special features of the A/D conversion CONVERSION:
and staling.
(Forty characters)
MINIMUM INSTRUMENT Engineering units value below which data cannot go RANGE:
(bottom-of-scale value).
(Ten characters)
-MAXIMUM INSTRUMENT Engineering units value above which data cannot go (top-RANGE:
of-scale value).
(Ten characters) i l
Rev. 0.A NRC-314 1
N-19
e a
ENCLOSURE 3 ZERO REFERENCE POINT:
Zero point of engineering units 5,cale, used primarily for levels or heights.
Use the zero reference point abbreviations from the enclosed list when possible.
(Six characters)
REFERENCE POINT NOTES:
Notes about the reference point or other important and special features of the parameter.
(Forty characters)
PROC OR SENS:
Is the point formed by processing more than one signal, or is the source a single sensor ("P" or "S")?
(One character)
NUMBER OF SENSORS:
The number of signals processed in a full calculation assuming no bypassed or inoperative sensors.
(Three characters)
HOW PROCESSED:
The processing algorithm (sum,
- average, weighted average, highest, lowest, or a short description).
(Forty characters)
SENSOR LOCATIONS:
Description of the location (s) of the instrument (s) used.
(Forty characters)
ALARM OR TRIP The most important setpoints for the parameter.
State SETPOINTS:
whether the limit is high or low.
(Forty characters)
NI DETECTOR POWER The power level at which the power supply for the NI SUPPLY CUT-OFF POWER detector switches off.
(Fifteen characters)
LEVEL:
s NI DETECTOR POWER The power level at which the power supply for the NI SUPPLY TURN 0N POWER detector switches on.
(Fifteen characters)
LEVEL:
INSTRUMENT FAILURE The mode in which this instrument fails. Possible MODE:
answers are HIGH, MEDIUM, or LOW. If available, provide the numeric value at which the instrument fails. (Thirty characters)
TEMPERATURE This question pertains to differential pressure COMPENSATION FOR transmitters.
Pos.sible answers are "YES" or "N0" ("Y" DP TRANSMITTERS:
or "N"),
if the answer is "N0", please attach a copy of the correction curve (One character)
LEVEL REFERENCE LEG:
The type of level measurement (dry or wet) used on the
-level reference +1eg.
(Three characters)
UNIQUE SYSTEM Additional important information which will assist the DESCRIPTION:
NRC Operations Center personnel in understanding how the plant team interprets the data.
(600 characters) l l
Rev. 0.A NRC-314 N 19 2
e c
ENCLOSURE 48 CRITICAL SAFETY FUNCTION PARAMETERS FOR BOILING WATER REACTORS REACTIVITY CONTROL PARAMETER DESCRIPTION TYPICAL UNITS Ni POWER RNG Nuclear Instruments, Power Range NI INTER RNG Nuclear instruments, Intermediate Range AMP NI SOURC RNG Nuclear Instruments, Source Range C/SEC CORE COOLING REAC VES LEY Reactor Vessel Water Level IN MAIN FD FLOW Feedwater Flow into the Reactor System RCIC FLOW Reactor Core isolation Cooling Flow GPM i
RCS INTEGRITY RCS PRESSURE Reactor Coolant System Pressure PSIG HPCI FLOW High Pressure Coolant Injection Flow GPM e
LPCI FLOW Low Pressure Coolant Injection Flow GPM CR SPRAY FL Core Spray Cooling System Flew GPM DW FD SMP LV Drywell Floor Drain Sump Level IN RADI0 ACTIVITY CONTROL I
EFF GAS RAD Radioactivity of Released Gasses MCI /HR EFF LIQ RAD Radioactivity of Released Liquids MCl/HR CND A/E RAD Condenser Air Ejector Radioactivity C/ MIN DW RAD Radiation Level in the Drywell R/HR MN STEAM RAD Radiation Level of the Main Steam Line MR/HR CONTAINMENT CONDITIONS DW PRESS Drywell Pressure PSIG DW TEMP Drywell Temperature q
F SP TEMP Suppression Pool Temperature F
SP LEVEL Suppression Pool Water level-IN H2 CONC Drywell or Torus Hydrogen Concentration 02 CONC Drywell or Torus Oxygen Concentration MISCELLANE0US PARAMETERS CST LEVEL Condensate Storage Tank Level WIND SPEED Wind Speed at the Reactor Site MPH WIND DlR Wind Direction at the Reactor Site DEG STAB CLASS Air Stability at the Reactor Site f
i Rev. 0.A
'4RC-314 H 19 1
ENCLOSURE AP CRITICAL SAFETY FUNCTION PARAMETERS FOR PRESSURIZED WATER REACTORS REACTIVITY CONTROL PARAMETER DESCRIPTION TYPICAL UNITS NI POWER RNG Nuclear instruments, Power Range
?.
N1 INTER RNG Nuclear instruments, Intermediate Range AMP NI SOURC RNG Nuclear instruments, Source Range C/SEC CORE COOLING REAC VES LEV Reactor Vessel Water Level IN TEMP CORE EX Highest Temperature at the Core Exit F
SUB MARGIN Saturation Temperature - Highest CET F
CORE FLOW Total Reactor Coolant Flow MLB/HR STEAM GENERATORS SG LEVEL 1/A Steam Generator 1 (or A) Water Level
?.
SG LEVEL 2/B Steam Generator 2 (or B) Water Level r.
SG LEVEL 3/C Steam Generator 3 (or C) Water Level Y.
SG LEVEL 4/D Steam Generator 4 (or D) Water Level 5;
SG PRESS 1/A Steam Generator 1 (or A) Pressure SG PRESS 2/B Steam Generator 2 (or B) Pressure SG PRESS 3/C Steam Generator 3 (or C) Pressure Y.
SG PRESS 4/D Steam Generator 4 (or D) Pressure Y.
MN FD FL 1/A Stm Gen 1-(or A) Main feedwater Flow LBM/HR MN FD FL 2/B Stm Gen 2 (or B) Main Feedwater flow LBM/HR MN FD FL 3/C Stm Gen 3 (or C) Main Feedwater Flow LBM/HR MN FD FL 4/D Stm Gen 4 (or D) Main Feedwater Flow LBM/HR AX FD FL 1/A Stm Gen 1 (or A) Auxiliary FW Flow GPM AX FD FL 2/B Stm Gen 2 (or B) Auxilia:y FW Flow GPM AX FD FL 3/C Stm Gen 3 (or C) Auxilia*y FW Flow GPM AX FD FL A/D Stm Gen 4.(or D) Auxiliary FW Flow GPM HL TEMP 1/A Stm Gen 1 (or A) Inlet Temperature F
HL TEMP 2/B Stm Gen 2 (or B) Inlet Temperature F
HL TEMP 3/C Stm Gen 3 (or C) Inlet Temperature F
HL--TEMP 4/D Stm Gen 4 (or D) Inlet Temperature F
CL TEMP 1/A Stm Gen 1 (or A) Outlet Temperature F
CL TEMP-2/B Stm Gen 2 (or B) Outlet Temperature F
CL TEMP 3/C Stm Gen 3 (or C) Outlet Temperature F
CL TEMP 4/D Stm Gen 4 (or D) Outlet Temperature F
l Rev. 0.A NRC-314 1
N 19
C 1
u o
ENCLOSURE AP REACTIVITY CONTROL PARAMETER DESCRIPTION TYPICAL UNITS RCS INTEGRlTY s
RCS PRESSURE Reactor Coolant System Pressure PSIG PRZR LEVEL Primary System Pressurizer Level t;
RCS CHG/MU Primary System Charging or Makeup Flow GPM HP S1 FLOW High Pressure Safety injection Flow GPM LP SI FLOW Low Pressure Safety injection Flow GPM CTMNT SMP NR Containment Sump Narrow Range Level IN CTMNT SMP WR Containment Sump Wide Range level IN RADIOACTIVITY CONTROL I
EFF GAS RAD Radioactivity of Released Gasses MCI /HR EFF LIQ RAF Radioactivity of Released Liquids MCl/HR CONr tvi RAD Condenser Air Ejector Radioactivity C/ MIN CNLANT RAD Radiation level in the Containment R/HR 1
Ms LTDN RAD Rad level of the RCS Letdown Line C/SEC PAIN SL 1/A Stm Gen 1 (or A) Steam Line Rad Level MR/HR "AIN SL 2/B Stm Gen 2 (or B) Steam Line Rad Level MR/HR MAIN SL 3/C Stm Gen 3 (or C) Steam Line Rad Level MR/HR MAIN SL 4/D Stm Gen 4 (or D) Steam Line Rad Level MR/HR SG BD RAD 1A Stm Gen 1 (or A) Blowdcwn Rad Level MR/HR SG BD RAD.2B Stm Gen 2 (or B) Blowdown Rad Level MR/HR SG BD RAD 3C Stm Gen 3 (or C Blowdown Rad Level MR/HR i
SG BD RAD 40 Stm Gen 4 (or D Blowdown Rad Leval MR/HR 1
CONTAINMENT CONDITIONS CTMNT PRESS Containment Pressure PSIG CTMNT TEMP Containment Temperature F
-H2 CONC Containment Hydrogen Concentration
?;
MISCELLANEOUS PARAMETEP1 BWST LEVEL Borated Water Storage Tank Level t'.
WIND SPEED Wind Speed at the Reactor Site MPH WIND DlR Wind Direction at the Reactor Site OEG STAB CLASS Air Stability at the Reactor Site Rev. 0,A NRC 314 N-19 2
f5 i O
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ENCLOSURE 5 ENGINEERlHG UNITS CODING SCHEME PSIG Pounds per square inch gauge
=
PSIA Pounds per square inch absoiute
=
INHp Inches of Water Pressure
=
7.
Percent INCHES FEET FTalN Feet and inches
=
FTDEC Feet and decimal feet
=
GAL Gallons
=
LB Pounds or pounds mass
=
GPM Gallons per minute
=
KGPM Thousands of gallons per minute
=
LB/HR Pounds per hour
=
KLB/HR' Thousands of pounds per hour
=
MLB/HR Millions of pounds per hour
=
CPM Counts per minute
=
CPS Counts per second
=
' AMPS NAMPS Milliamps
=
uAMPS Microamps
=
DEGF Degrees Fahrenheit
=
DEGC Degrees Centigrade MR/HR Millirem per hour
=
R/HR Rem per hour
=
Cl/CC Curies per CC
=
C1/ML Curies per ML'.
=
uC1/CC Microcuries per CC
=
uC1/ML Microcuries per ML
=
C1/S Curies per second uC1/S Microcuries per second'
=
DEGFR Degrees'true (for wind direction from)
=
DEGTO legrees true (for wind direction to)
=
DF/FT Cegrees Fahrenheit per. foot DC/M Degrees Centigrade per meter
=
.DC/HM D)grees Centigrade per 100 meters DF/HFT regrees Fahrenheit per 100 feet
=
'STABA itability class in form of A - G
=
STABI
- Stability class in form of integer, where A = 1, B = 2
=
MPH Miles per hour
=
M/S Meters per second
=
~Rev. 0.A NRC-314 1
N-19
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i; ENCLOSURE 6 ZERO REFERENCE CODING SCHEME i
i This field applies to levels and heights only. Leave it blank for temperatures, pressure, and flows. Give the physical point represented by the number zero for the parameter from the choices below.
}
. Top of active fuel
=
UPHEAD Upper head
=
LWHEAD Lower head
=
MSSKRT Moisture separator skirt
=
TOPHTR Top of pressurizer heater bank
=
SURGE Surge line penetration
=
SPRAY At the spray nozzle
=
UTUBES Top of S/GU tubes TUBSHT At S/G tube sheet
=
TNKBOT Bottom of tank sump (e.g., CST)
=
COMplX Reference too complex for database entry
=
CNTFLR.
Containment floor SEALEY Mean sea level
=
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1 i
Rev. 0.A.
NRC-314 N-19' 1
/~
3o o o e
ENCLOSURE 7 May 30. 1989 CODING SCHEME FOR UNIT NAME AND UNIT 10 ARKANSAS NUCLEAR ONE 1..ANI GRAND GULF 1............GG1 QUA0 CITIES 1..........
0Cl ARKANSAS NUCLEAR ONE-l..AN2 HATCH-1.................HTl QUA0 CITIES 2..........
0C2 BEAVER VALLEY l.........BV1 HATCH 2.................HT2 RtNCHO SECO 1...........RS)
BEAVER VALLEY 2.........BV2 HOPE CREEK 1............ hcl RIVER BEND 1............RBI BELLEFONTE 1............ bel INDIAN P0!NT 2..........lP2 ROBINSON 2..............R02 BELLEFONTE 2............BE2 INDIAN POINT 3..........lP3 SALEM 1...............
BIG ROCK POINT..........RPI JAMES A FITZPATRICK.....FZ1 SALEM 2...............
.SA)
BRAIDWOOD l.............BRI KEWAVNEE................KW1 SAN ONOFRE 1...........
501
.SA2 BRA 10 WOOD 2.............BR2 LA CROSSE (GENOA 2).....LCl SAN ONOFRE 2...........
502 BROWNS FERRY 1..........BF)
LASALLE COUNTY 1........LSI SAN ONOFRE 3...........
503 BROWNS FERRY 2..........BF2 LASALLE COUNTY 2........LS2 SEABR00K l..............SBl BROWNS FERRb 3.......... BF3 LIMERICK 1..............LM1 SEQUOYAH 1..............SE1 BRUNSWICK 1.............BKl LIMERICK 2..............LM2 SE000YAH 2..............SE2 BRUNSWICK 2.............BK2 MAINE YANKEE.....:......MY1 SHEARON HARRIS 1........HR1 BYRON 1.................BY1 HCGulRE 1...............MCl SH0REHAM................SH)
BYRON 2.................BY2 MCGUIRE 2...............MC2 SOUTH TEXAS PROJECT 1...STI CALLOWAY 1..............CW1 MILLSTONE 1.............MSI SOUTH TEXAS PROJECT 2...ST2 CALVERT CLIFFS 1........CCl MILLSTONE-2.............MS2 ST. LUCIE 1.............SL)
CALVERT CLIFFS 2........CC2 MILLSTONE-3.............MS3 ST. LUCIE 2............
l CATAWBA 1.....
.........CTl MONTICELLO.............M01 SURRY 1................
SL2 CATAWBA 2...............CT2 NINE MILE POINT-l.......NMI SURRY 2.................
SUI CLINTON 1...............CL1 NINE MILE P0lNT 2.......NM2 SUS 0VEHANNA 1..........
501 SU2 COMANCHE PEAK 1......... CPI NORTH ANNA 1............NAl SUS 0VEHANNA 2..........
502 COMANCHE PEAK 2.........CP2 NORTH ANNA 2............NA2 THREE MILE ISLAND 1.....TM1 CONNECT!CVT YANKEE......HN1 OCONEE 1...............
0Cl THREE MILE ISLAND 2.....TM2 C00K 1..................CK1 OCONEE 2...............
002 TR0JAN..................TR)
C00K 2..................CK2 OCONEE 3...............
0C3 TURKEY POINT 3..........TP3 C00PER..................C01 OYSTER CREEK...........
0Y1 1URKEY P0lNT 4.......... TP4 CRYSTAL RIVER 3.........CR3 PAllSA0ES............... pal V. C. SUMMER............VS1 DAVIS BESSE 1..........
081 PALO VER0E 1............PV1 VERMONT YANKEE..........VY1 DIABLO CANYON 1.........DCl PALO VERDE 2............PV2 V0GTLE 1................V01 DIABLO CANYON 2.........DC2 PALO VERDE 3............PV3 V0GTLE 2................v02 4
ORESDEN 2..............
0N2 PEACH BOTTOM 2..........PE2 WATERFORD 3.............WF3 DRESDEN 3..............
0N3 PEACH BOTTOM 3..........PE3 WATTS BAR l.............WB1 OUANE ARNOLD............DAl PERRY 1.................PY1 WATTS BAR 2.............WB2 FARLEY 1................FAI PERRY 2.................PY2 WNP 2...................WP2 FARLEY 2................FA2 PILGRIM 1...............PGl WOLF CREEK..............WCl FERM1 2.................FE2 POINT BEACH 1...........PB1 YANKEE ROWE.............YR)
FORT CALHOUN 1..........FCI POINT BEACH 2...........PB2 Z10N 1..................ZN1 FORT ST. VRAIN 1........FV1 PRAIRIE ISLAND 1........P!1 Z!0N 2...............
..ZN2 GINNA...................Gil PRAIRIE ISLAND 2........P12 Rev. 0.A NRC 314 N 19 1
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ENCLOSURE E
- 0MPUTER POINT SELECTION minimum set of computer points, available on the fewes 9umoer of feecers from a site, anich fully cettribe each of th the ERDS Parameter List, e carameters on vihen multiDie computer Ooints exist to oescribe a certain Caramete usually one coint or a small subset of points which meet the following r, there is desiracility criteria
For fluids systems (e.g., HPCI, Building Ventilation, Main feeowater, etc.) the points representing the farthest location cownstream in the system are most cesirable.
Examples:
If the ventilation system exnausts from all buildings the oower
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clock converge ano ascena up a single plant vent stack, effluent process raciation monitors on the plant stack neea bethen only tne cascribed under " gaseous effluent" versus describing the individual etfluent monitors which may exist for each of the exhaust lines wnich converge.
If an injection or feedwater system has a set of points available
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which include flows measured at the pump discharges, at a combined header and at the point in the system just prior to injection into the loops or steam generators then the points which should be (flow measured just prior to injection into loops or steams generators).
Computer points which have uncergone the maximum amount of esnge en ano etner data coint validation schemes snould be selecteo, that many utilities are in the process of upgracing computer system ae are aware validation technioues and that what exists now may be replaceo at some future cate.
Computer points representing the widest expecteo range of the Darameter should be selected.
For example:
If there is a choice of computer coints for " Containment Pressure" with one representing the range i to
+5 PSIG ano another representing the range -5 to +100 PSIG the wice-range -5 to +100 PSIG computer point should be selectec:
its accuracy may not be as great near the normally expecteo pressure of even though
-1 to +1 PSIG,
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I I
b*O f
Q o o e e
The coint composeo of the maximum numoer of inputs should be useo cesiracle point may be composeo (processeo) within the feteer comouter or The may ce cocoosed by a separate microprocessor outsice the feecer as in the Monitors (SMM) ano meteorological tower systems. case of PW selecting the most composto points should not be apThe philosophy of parameters associated with PWR coolant loops (e.g.,pliec in the case of Pressure, S/G Level, Main Feeowater Flow, ect.) to the extent oft-hot. T cold, S selecting points such as " Average T-hot", because loop specific parameters are preferable for use in coolant loop-specific accicents such as Steam Generator Tube Breaks, Loop 1", " Average T-hot Loon 2", etc. should be selected. Composed points suc
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