ML20244D376
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JUN 2 61985-MEMORANDUM FOR: . William J. Dircks l Executive Director for Operations .
I FROM: James M. Taylor, Director V Office of Inspection and Enforcement
SUBJECT:
TMI ACTION PLAN - COMPLETED ITEM Pursuant to your memorandum of June 3, 1981', enclosed is a report of the .j completion of TMI Action Plan Item III. A.3.4, Nucicar Data Link (NDL). There a
are no followup assignments necessary with completion of this action item. 1 Grig.nrJ J.:;:d By 1 James 61. Tcybr )
l James M. Taylor, Director Office of Inspection and Enforce: cent ;
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Enclosure:
As Stated l cc: V. Stello, Jr. , DEDROGR H. R. Denton, HRR J. G. Davis. NMSS 4 R. B. Minogue, RES Regional Administrai. ors I-V 0 R. Hartfield, RM M. King, RM l
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Completion of TMI Action Plan Item III.A.3.4 Nuclear Data Link (NDL)
O q Actions Indicated in NUREG-0660 1
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The scope for a nuclear data link will be defined. " Nuclear data link" being the term given to a system that will remotely access facility data and transmit the data and display information in the NRC Operations Center. NRC links with '
the various nuclear facilities, methods of transmission, and the display in the d operations center will be studied.
L Schedule Indicated in NUREG-0660 l
The schedule for development and implementation would be determined by commis- ;
sfon decisions on future direction of the NDL.
O Background and Closecut-Action l A conceptual design for an NDL was produced under contract with Sandia National J Laboratories, and, in April 1981, the Commission directed IE to proceed with an l NDL prototype program. However, beginning in June 1981, a series of Congres-l sional actions and requests have caused the NRC to reassess releasing a Request for Proposals to conduct a prototype study. In the'FY 1983 Pay Raise Supple-1
( ment and the FY 1984 Appropriations Bills, the Congress took actions that i
effectively rejected several NRC requests to the Congress to allow the NDL to i
proceed. However, the NRC's FY 1984-85 Authorization requires the NDL concept j l
to be included as part of any analysis of alternative means of. upgrading NRC -
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The FY 1984-85 Authorization Act requires analysis of four issues before an NDt.
or similar system can be implemen9d: (1) the appropriate role of the Commis-m.
(d sion during an accident, (2) ti.e i , formation needed by the Commission to j support that role, (3) the alternative means of acquiring that data, and (4) any changes in Commission authority necessary to enhance Commission re- l 1
sponse to nuclear emergencies. The Act also requires a cost-benefit analysis of the alternatives considered for acquiring the data.
IE proceeded to address the questions raised by the Congress and to compare l
several alternatives for upgrading emergency data acquisition capabilities for the Operations Center. Alternative conceptual approaches were developed; their positive and negative attributes were tabulated; and these attributes were then compared to experiences gained during the Federal Field Exercise, other drills, and actual events. !
O IE concluded that the design which best addresses the Congressional criticisms of the NDL, while meeting the requirements of NRC, is one which utilizes electronic data transmission systems already being developed by licensees for I
their own emergency response facilities. This concept, called the Emergency Response Data System (ERDS), was approved by the Corxnission in March 1985. The design concept for ERDS can be summarized as follows: f I
Parameter inputs to ERDS would be obtained from an existing computer system (e.g. SPDS, plant c.omputer, EOF data systems, etc.) at the plant.
I Data will be transmitted to the NRC Operations Center by modem to commercial telephone line or a dedicated line maintained by NRC (e.g., ENS). l l
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A central processing system located in the NRC Operations Center will receive the data stream by modem. The system will be designed to receive all varied O dete streems end to reformet tne date into e consistent formet. The reformet-ted data will be output to CRTs and printer. 1 The parameter list would include those parameters necessary to ensure that appropriate protective action is being taken with respect to offsite recommen-dations. The list would be limited to those parameters involving plant status, radiological, and meteorological conditions.
Licensees will not be required to backfit their systems to include additional 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.
O The updating frequency of the licensees' systems will determine transmission 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.
l Licensee action will be required to initiate data transmission in the early I l
stage of a declared emeregency. ]
The NRC responded to Congress in May 1985 addressing the questions they had J
raised. In June 1985, IE released a request for proposals to design the ERDS system. With the approval of a course of action and the initiation of the
(] design and implementation effort, this TMI Action Plan Item is now completed.
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ROUTING AND TRANSMRTAL SUP ,
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" Attached is the Generic Issue Management Control.
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sheet on. the issue assigned to you ,
System (GIMCS)1. We need to update these as of the for~ resolution third quarter FY 85, and provide som.e additional information for.the Annual Report or} Resolution.- '
of Safety Is. sues. For ERDS we need to provide 1 a memo to the EDO closing out the issue. A ve attached a sample for your use in closing it out, , ';
and an excerpt frocc.NUREG-0660 that addressestthe ,-
original issue.. 'If we decide not to'.close 1.t out, we'll need to p.rovide a schedule for implementation of ERDS, and a justification for slippage'in the existing schedule from last year's annual report, ' '
which showed the final milestone as 8/84. ,
Please. provide me with the marked-up GIMCS sheet by.
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.I June 7th. . The memo to the ED0 'should' ha -etart_ad tirouah the system ASAP so we can close it out by' i 00 Ncr r use sus -... as a m.way of approves.' concurrences. disposses. .
clearences, and similar actions .
Fit 0M: (Name, org. symbol, Agency / Post) , , Room No.-Sids.
the end'of the 3rd quarter of FY85 Phone No.
Andle 8e88-1ct OPrioNAL POftM 41 (Itov. 7-76)
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i GENERIC ISSUE MANAGEMENT CONTROL SYSTEM . l
{ i O tesoe Number tssve Type Act4oa Level Office /Div/Br Tes' Manacer Tac No III.A.3.4 Safety / Active-L1 IE/DEPER/ IRE J. Hickman None Medium i
Title ---------------- Emergency Response Data System
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Work Authorization --- Commission decisions 4/28/81 and 3/3/83 (Congressional hold 'in Supplemental Appropriations Act of 1983.)
Contract Title ------- No contract issued since Commission decisions l Contractor Name/
FIN No. ------------ To be determined Work Scope ----------- ' Determine, through in-house effort, practical options for "
implanting a method of acquiring and transmitting data based '
on each licensee's existing electronic data systems (e.g.,
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SPDS). ,
Determine, through contractor eff, ort, the hardware and software necessary to implement a method of acquiring and transmitting data based on each licensee's existing electronic data systems.
b Affected Documents --- None
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Status --------------- Apaperdescribingnewapproachhasbeenpreparedtoinform the Commission and to recommend that the Commission direct the Of fice of Congressional Affairs to inform the appropriate Congressional committees.
Problem / Resolution --- None.
Technical Resolution -
Milestones Original Current Actual Prepare and submit new -
10/84 12/07/84 proposal to EDO for Commission approval.
EDO concurrence and -
01/85 12/21/84 1 transmit proposal to Commission.
Commission approval. -
03/B5 -
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, Completion of TMI Action Plan Item III.D.2.4(2) j Gi h Le Dese ." measurements O i Actions Indicated in NUREG-0660 t j
i I will place approximately 50 thermoluminescent dosimeters (TLD) around each 1 site in coor ion with States and utilities. During n 4-operstion, quarterly reports from thes er will ided to NRC, State, and Federal organizations. e event of an acci ent., t,he h dosimeters can be read at a fr ncy appropriate to the needs of the situation.
Schedule Indicated In NUREG-0660 IE,wiEcomplete-the TLDJnstallation before full-power operation _of-new-reRTors and by August 1980 for pera tors. Nolchiddle wasapecified for development, preparation, and implementation of the program for generation of routiae pe riodic r rts of TLD measurement results.
O Backoround and Closecut Ntion In st 1979, IE established the NRC TLD Direct Radiation Monitoring Network to x e measure amblent radiation levels around NRC licensed facilities. 'The TLD network s
is a cooperative' effort between IE, NRC Regional Offices,'and participating States.
N The program is administe' red by IE Headquarters. The operation of the program, consisting in part of processiilg badges, shipping and packaging, data processing,
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and reporting, is the responsibilityofQhe Emergency Preparedness and Program Support Branch, Region.- I. ,.At'most sites, t'hes(LD badges are exchanged and placed in the field . locations'by 23 State Offices participating under contract to the NRC.
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For sites located'in nonparticipating States, the field work is performed by individuals under contract to NRC. In this program, TLD badges are scheduled to be exchanged, shipped, and processed in Region I on a quarterly schedule.
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O The speci 'c objectives of the TLD program are as follows:
(1) To e ablish preoperational, historical, baseline radiation dose levels, I wheneve possible, for each monitored facility; 'l 1
l (2) To provide ngoing radiation dosimetry data during routine operations; (3) To provide pdst-accident radiation dosimetry to' aid in assessment of '
population expo res and radiological impact; l (4) To allow for independent verification of the adequacy of NRC licensees
environmental radiatihn monitoring programs; (5) To provide unifom treatme t of dosimeters with respect to handling, I
shipping, calibrating, read'ing, and data processing for all monitored l facilities in the United States,; and (6) To provide unifom, consistent e ironmental radiation monitoring data for use by the Congress, Federal an)\ State agencies, monitored facilities,
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and the public. \
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IE completed installation of TLDs at all operating \reactors by August 1980 in accordance with the TMI Action Plan schedule. Present y TLDs are located around 55 NRC licensed facility sites consisting of 93 nuclear p r reactor plants in operation or under construction. The facilities are listed in Enclosure 1. In April 1982, the first report on the results of the NRC TLD Direct Radiation Monitoring Network was published (NUREG-0837, Volume 1, Numbers 1 and 2). The report co ered the first two calendar quarters of 1981. The second report, covering 'the second half of 1981, was published in May 1982 (NUREG-0837, Volume. -j 1, Numbers 3 and 4). These reports presen'ted the TLD measured radiation levels .
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l for each monitoring station at each site. The radiation levels aroprovided j
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in two fonns,: (1) the integrated exposure over the quarterly time period, and '
(2) the daily ex'posure rate.
With '.he establishment of the NRC TLD Direct Radiation Monitoring Network, the i
installation of TLDs at all operating reactor sites, and the development of the pryram for routine reports on the results of the TLD measurements, this TMI Action Plan Item is now completed.
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, Enclosure 1 NRC Licensed facilities Included in the NRC TLD Direct Radiation Network 3 (This information is reproduced from Table 2 - NUREG-0837 Volume 1)
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\ Utility State sP lant Operator Docket No. Status
- Alabase Browns Ferry TVA 50-259, 260, 296 0, 0, O Farley Als Power 50-348, 36 V 0, O Arkansas Arkansas Arkansas P&L 50-313, 368 0, O California Diablo Canyon Pac G&E 50-275. 323 CC Rancho Seco SMUD 50-312 0 San Onofre SCE 50-206, 361, 362 0. C, C Colorado Ft. St. Vrain PSC of C0 50-267 0 l
connecticut Haddas Neck Conn Yankee 50-213 0 * '
Millstonei ME Nuclear 50-245, 336, 423 0, 0, C Energy to Florida crystal River Fla Power 50-302 0 St. Lucie i FP&L 50-335, 389 0, C !
Turkey Pt. i FP&L 50-250, 251 0, 0 j Georgia Hatch Georgia Power 50-321, 366 0, 0 I Illinois Dresden Coe Ed 50-10, 237, 249 0, 0, O LaSalle com Ed 50-373, 374 C, C Ouad Cities < Can Ed 50-254, 265 0, 0.
Zion Con Ed 50-295, 304 0, o i Iowa Duane Arnold Iowa Elec 50-331 0 Maine Maine Yankee Maine Yankee 50-309 0
. Maryland Calvert Cliffs 'BG&E 50-317, 318 0, 0 Massachusetts Pilgris 8oston Ed 50-293 0 Yankee Rowe Yankee Atomic 50-29 0 Michigan Big Rock Pt. Consumer 50-155 0 0.C. Cook Ind & Mich 50-315, 316 (> .. O Palisades Consumers 50-255 0 Minnesota Monticello Northen States 50-263 0 Prairie Island Northrn States 50-282, 306 0, 0 Mississippi Grand Gulf Miss. P&L 50-416, 417 C, C !
Nebraska Cooper Nebraska PP0 50-298 0 I Ft. Calhoun Omaha Pub Pwr 50-285 0 i New Jersey Nope Creek PSEE 50-354, 355 C, C !
Dyster Creek Jersey Central 50-219 0 Salas PSE&G 50-272, 311 0. C New York Fi.zPatrick NY Power Auth 50-333 0 G nna Rochester GEE 50-244 0 Indian Pt. Con Ed (2) 50-247, 206 0 NY Power NY(3) 50-286 0 Nine Mile Ft. Niagara Mohawk 50-220 0 Shoreham LILCD ~ 50-322 C N Carolina Brunswick Carolina P&L 50-324, 325 0, 0 McGuire Duke Power .50-369, 370 C, C Chio Davis-Besse Toledo Edison 50-346 0 Zlamer CGEC 50-358 ;
Dregon Trojan PG&E 50-344 0 s ;
Pennsylvania Beaver Valley Duquesne Light 50-334, 412 0, 0 Peach Botton Phila Elec Co. 50-277, 278 0, C i' TMI Met Ed 50-289, 320 0, 0 S Carolina Oconee Duke Power 50-269, 270,.287 0, 0, O H.B. Robinson Carolina P&L 50-261 0 Summer SC E4G 50-395 C Tennenee Sequoyah TVA 50-327,' 328 0, C Watts Bar TVA 50-390, 391 C, C ,
Vermont Vermont Yankee VT Nuclear Pwr 50-271 0 '
Assoc Virginia North Anna VEPC0 50-338, 339, 404 0, 0, C Sorry VEPC0 50-280, 781 0, 0 Wisconsin Kewaunee Wisc Pub Svc 50-305 0 1 Lacrosse' Diaryland Fwe 50-409 0 'I Pt. Beach Piqua AEC Wisc 50-266, 301 0, 0 - '
Mich
" Status Codes 0 - aperating facility '
C - facility under construction
Task Ill.A.3 May 1980
- 4. huclear data link (NCL),
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Description:
" Nuclear data Ifnk" is the term given to a system that will reenotely access facility data and transmit the data and di:; play information in the hRC Operations Center. The irtformation will allow NRC to analyze and evaluate the plant situation in emergency conditions and to develop or evaluate proposed accident iaitigating actions. Sandia has been contracted as sys",ets integrator _for ceveloping the concept for data acquisition from licensed facilities and for upgrading the NRC operations center at headquarters.
The program Sandia develops will define the scope for an NRC nuclear data link.
This work will be coordinated with the criteria being developed by NRR for 1Jcensee data links in the TSC and EOF (item !!!. A.1.2) and with various groups in the industry. NRC links with the various nuclear facilities, methods of transmission, and the display and arrangement of the upgraded NRC headquarters ~
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operations center will be studied. Consideration will be given in the initial development to a series of alternate data inouts (i.e., 20-100-500 parameters monitored) and associated problems and implications of availability (i.e., from .
plant computer, is hardwiring to monitor / sensor necessary, is signal in analog i
or digital forto, what form should output signal be in? What standardization l{
criteria must be developed for interfacing and tieir. with the licensee data.
links for the TSC an-j EOF (item III. A.1.2) and the industry-operated data centers -
j reconwnended by the NRC Special Inquiry Group?). (See also item 23, Table C-3, Appendix C.) 'l
. 'i A status report on the Sandia study was presented to the Commissioners in !
February 1980. j NOL.
Commission decisions will determine future direction of the i i
- b. Schedule:
The NOL system Phase I study, including development of an implementat;on schedule and cost
- estimates, was completed in April 1980. '
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kescutces: IE FY80 - 5250,000 (also possible 5300,000 from supple- I mental); RES FYB0 - 0.3 my and $300,000 (f uture resources are dependent on l
Commission decisions); ADM FY80 -0.3 my, FY81 - 0.4 my and 5126,000.
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Ill.A.3-5 '
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TABLE 2 "BWR PARAMETER LIST Primary Coolant- Reactor pressure System Reactor vessel level 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 temperatures Hydrogen and oxygen concentration Drywell sump levels Suppression pool temperature " j Suppression pool level ]
Radiation Monitoring f Reactor coolant radioactivity level
. System Primary containment radiation level ,'
Condenser.off gas radiation level Effluent radiation mdnitor Process radiation levels O Meteorological wind speed Wind direction Atmospheric stability I
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