ML093430578
| ML093430578 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 06/01/1981 |
| From: | Bayne J Power Authority of the State of New York |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML093430579 | List: |
| References | |
| IPN-81-37, NUDOCS 8106090469 | |
| Download: ML093430578 (30) | |
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POWER AUTHORITY OF THE STATE OF NEW YORK 10 COLUMBUS CIRCLE NEW YORK. N. Y. 10019 (212) 397-6200 TRUSTEES JOHN S. DYSON CHAIRMAN GEORGE L. INGALLS VICE CHAIRMAN RICHARD M. FLYNN ROBERT I. MILLONZI FREDERICK R. CLARK June 1, 1981 IPN-81-37 GEORGE T. BERRY PRESIDENT
& CHIEF OPERATING OFFICER JOHN W.
BOSTON EXECUTIVE VICE PRESIDENT-PROCEDURES
& PERFORMANCE JOSEPH R. SCHMIEDER EXECUTIVE VICE PRESIDENT & CHIEF ENGINEER LEROY W. SINCLAIR SENIOR VICE PRESIDENT
& CHIEF FINANCIAL OFFICER THOMAS R. FREY SENIOR VICE PRESIDENT
& GENERAL COUNSEL Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
Subject:
Indian Point 3 Nuclear Power Plant Docket No. 50-286 Submittal to NRC of "Conceptual Design for Upgrading Emergency Support Facilities"
Dear Mr. Eisenhut:
In response to your letter dated February 18, 1981, the Power Authority of the State of New York submits herewith the attached document entitled, "Conceptual Design for Upgrading Emergency Support Facilities", for Indian Point 3 Nuclear Power Plant.
Should you or your staff have any questions,please contact Very truly yours, yy yn Senior Vice President Nuclear Generation cc:
attached US.
e e 8106 09 f)qi;g
cc:
Mr. T. Rebelowski Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 38 Buchanan, New York 10511 Mr. Ron Barton United Engineers & Constructors, Inc.
30 S. 17th Street Philadelphia, Pa.
19101
ATTACHMENT I CONCEPTUAL DESIGN FOR UPGRADING EMERGENCY SUPPORT FACILITIES POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286
- l. TECHNICAL SUPPORT CENTER 1.1 LOCATION The onsite TSC will be located in an area in the western half of the second floor of the 1P3 administration building.
This area is within 200 feet of the control room, which can easily be reached within 2 minutes.
There are no major security barriers between these two facilities other than access control stations for the TSC and control room.
1.2 STAFFING AND TRAINING As specified in the IP3 Emergency Plan, the TSC will be staffed by members of the plant technical services organization, Westinghouse technical personnel ( as required ) and other contract and corporate office technical personnel (as required). -This staff will be directed by the Technical Support Group Leader who will normally be the Tech Lnical Services Superintendent.
Other senior members of the TSC staff (i.e. Reactor Analyst Su~pervisor or Technical Services Engineer) will act as the Technical Support Group Leader if the Technical Services Superintendent is not available.
The specific functions of the TSC staff include, as a minimum:
- l.
Analysis and resolution of thermodynamic and thermal hydraulic problems.
- 2.
Analysis of problems involving mechanical, electrical, instrument or control systems and development of solutions.
- 3.
Design and coordination of installation of short term modifications.
- 4.
Development of guidance regarding plant conditions for emergency director and operations functions.
- 5.
Assistance in formulating procedures and instructions as needed for emergency operations; and
- 6.
Resolution of questions concerning the operating license requirements with NRC representatives.
Training of TSC personnel shall be accomplished by regularly scheduled exercises, drills, and classroom work as detailed in the emergency plan.
1.3 SIZE Figure 1 shows the general arrangement plan for the TSC.
Provisions have been made for a total of close to 4000 square feet of habitable working space including 1000 square feet for TSC data system equipment and the necessary repair maintenance and service facilities, 720 square'feet of space for personnel access to functional displays, 380 square feet of space for communications equipment, 215 square feet for document storage and 202 square feet for private NRC consultations.
Overall, the facility has 1811 squake feet of dedicated office space for an anticipated staff of less than 20 persons from the utility.
6K J
FIGURE I
1.4 STRUCTURE Initially, the IP3 Administrative Building was investigated to evaluate if it could withstand the effects of a safe shutdown earthquake (SSE) without collapsing, and was found adequate.
Revisions proposed to the Administration Building to accomodate the TSC were reviewed and changes from original drawings were incorporated in the mathematical model of the Administration Building.
The mathematical model assigns two translational (N-S and E-W) and one torsional degree of freedom to each floor.
Consequently, total (lumped) mass and total (lumped) mass moment of inertia are computed for each floor. Each story stiffness is calculated assuming that steel columns will resist lateral (translational and torsional) displacements.
For the first two stories the presence of steel bracing between column lines at the north and south building ends, and the concrete buttress at the east end of the building, is accounted for in addition to steel columns when calculating the story stiffness.
The dynamic analysis of the Administration Building model was performed by using the NASTRAN computer program and assuming that the seismic excitation of an OBE intensity (defined in figure Al-l of appendix A of the IP3, FSAR, Volume 5) is applied at foundation level (15.0 EL).
Soil-Structure interaction effects and through soil structure to structure coupling effects were considered negligible and not accounted for.
The results obtained indicated that with the modification of the West face of the building with shear walls and bracing from elevation 15' to elevation 47'-6", the building response accelerations to an OBE excitation will be acceptable.
Flooding at the IP3_s.te has been nonexistent.
The highest recorded water elevation at the site was 7.4 feet above mean sea level during an exceptionally severe hurricane in November, 1950.
According to studies detailed in the IP3, FSAR, the highest water level postulated to occur during the most severe conditions is 15 feet above mean level.
No TSC structure or'support facility is located below the 15 -
3" elevation.
The administration building was designed for the effective velocity pressure, exposure B, shown in ANSI A 58.1 -
1972 edition. Design pressure at various heights of the structure above ground level are:
0 to 29 Feet 17 psf 30 to 49 Feet 23 psf 50 to 99 Feet 30 psf 100 to 149 Feet 35 psf Roofs and enclosed structures were designed to withstand an outward pressure of 20 psf as per NYS Building construction code dated July 1, 1972.
1.5 HABITABILITY The following shielding and HVAC design study shows that the TSC will be habitable according to all applicable criteria.
REFERENCES
- 1.
B&R Calc. No. 15-06-02S, "PASNY -
Habitability of Technical Support Center"
- 2.
- 3.
K.G. Murphy & K.M. Campe, "Nuclear Power Plant Control Room Ventilation System Design for Meeting General Criterior 19",
13th AEC Air Conference
- 4.
NRC Reg. Guide 1.52 Rev. 2 "Design, Testing and Maintenance Criteria for Post Accident Engineered Safety Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light Water-Cooled Nuclear Power Plants"
- 5.
"Reactor Shielding Design Manual", Rockwell, id
- 6.
B&R DWGS. SAI01, A071 and SC050
- 7.
U.S.N.R.C. Standard Review Plan Sec. 6.4, "Habitability Systems" NUREG-75/087
- 8.
Emergency Plan for Indian Point No. 3 Nuclear Power Plant; Power Authority of the State of New York, Docket No. 50-286; Appendix 10.3, Table I.
- 9.
NUREG-0737, "Clarification of TMI Action Plan Requirements,"
Item II.B.2.
PURPOSE The urpose of this study is to report the calculated shielding design features of the Technical Support Center (TSC), including:
- bulk shielding
- Shield door and labyrinth design
- air recirculation requirements These design features are meant to insure-that radiation levels within the TSC will result in iitegrated doses, (i.e., whole body gamma ray, thyroid and beta skin doses), below design criteria.
DESIGN ASSUMPTIONS
- 1.
The TSC will be isolated and the TSC filtration system will be placed in operation immediately after a postulated LOCA, as determined by the radiation monitoring systems.
- 2.
Reference 2 (p. 14.3.5-15) assumes a containment leak rate of 0.1% per day for the initial 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following a LOCA, and 0.045% per day for the remainder of the 30 day period.
- 3.
A nominal wind speed of lm/sec. was used, as recommended by reference 3.
METHOD OF ANALYSIS The analysis is based on the use of the Burns and Roe computer code FSPROD-DBAA (NU 0860) for the calculation of the radiation source terms and for the integrated doses (whole body gamma, thyroid and beta skin) due to the internal radiation environment within the TSC. Bulk shielding thickness requirement was calculated with the QADBR (NU 0040) joint-kernel computer code. Additional shielding analysis, e.g., filter shielding and shield door requirements, were done from fundamental principles and used geometric attenuation formulae as presented in reference 5.
RESULTS The following shield design features are incorporated in the TSC:
- 1.
The filtration system consists of a set of two 2-inch filters in series.
Whereas the combined efficiency is 99.75%, the analysis is based on an assumed efficiency of 99%, as per reference 4.
- 2.
The combination of no air infiltration plus use of 2 sets of filters permits the TSC to operate without the need for air recirculation. The integrated 30 day dose due to the internal TSC environment is:
Whole body gamma ray
= 0.5 Rem Thyroid
= 13.0 Rem Skin beta dose
= 8.7 Rem We note that an inleakage rate as low as 10 CFM would cause the thyroid dose to exceed the design limit, unless recirculation is incorporated.
- 3.
The bulk shielding corresponding to 8 inches of ordinary concrete (density of 150 lb/ft3) surrounding the TSC reduces the outside cloudy integrated dose to personnel within the TSC to 2.7 Rems.
DESIGN CRITERIA As per Criterion 19, Appendix A of 10CFR5O, the design limits for the integrated dose for the thirty (30) day time period following a postulated loss-of-coolant accident are:
Whole body gamma ray dose A
5 Rem Thyroid dose i
30 Rem Skin beta dose
< 30 Rem DATA
- 1.
The filter efficiencies of each 2" charcoal bed and particulate hepa filter were taken to be:
elemental iodine 95%
organic iodine 95%
particulate 99%
- 2.
The TSC fresh air intake rate is 1000 CFM.
- 3.
The TSC volume is 1.12 x 105 ft. 3
- 4.
Although the FSAR assumes an iodine removal coefficient of 32 hr-l, the analysis used the conservative value of s = 9.8hr. -1, as given in reference 8. The difference is not significant.
- 5.
Atmospheric dispersion factors, x/Q, were calculated as per reference
- 3. The values are (for the air intake):
Time Interval x/Q (sec/m3) 0 - 8 hrs 9.89 - 04*
8 - 24 hrs 5.83 - 04 1 - 4 days 2.27 - 04 4 - 30 days 6.53 - 05
- read as 9.89 x 10-4
- 6.
Reactor operating power of 3216 Mwt, with a corresponding thermal 14 neutron flux of 1 x 10 n/cm2 -
sec.
- 7.
Shielding credit was taken for the 6" concrete floor and ceiling for the TSC, as well as the 6" concrete slab between the upper floors.
- 8.
In addition to the isolation of the TSC following a postulated LOCA,- all ingress and egress will be via a double door vestibule type. This permits the assumption of no air infiltration.
- 9.
The east and south walls of the filter room will be shielded with 16" of concrete (150 lb/ft3), or 20" of concrete block (density of 120 lb/ft3).
The north wall of the same room will be shielded with 22" of concrete (150 lb/ft3) or 28" of concrete block (density of 120 lb/ft3).
The resultant maximum integrated dose, in the area immediately adjacent to the filter room, due to the accumulated source on the filters, will be about 0.3 Rem;
- 10.
Steel (3o =7.85 g/cc) has a shielding effectiveness 3.2 times that of ordinary concrete (2
= 2.35 g/cc) for 2MeV gamma rays.
- Thus, 2-1/2" steel is equivalent to 8" ordinary concrete.
The east side of the TSC will contain two shield doors.
The single door (facing a corridor) is partially shielded by the dumbwaiter (with its enclosed concrete block walls) and will contain 2" steel plate.
The double door, facing the sleeping area, will contain 2-1/2" steel plate.
- 11.
The north wall of the equipment access area shall be removed and the said area shall become part of the technical support center pressurized with filtered air.
The east wall of the aforementioned area shall not be a shield wall and neither shall the door on it shall be a shield door. The door connecting the HVAC area and the equipment access area shall be a shield door made out of 2" thick steel.
- 12.
The HVAC room will be a restricted area due to the shine entering the room through the air intake duct, unshielded. At several feet from the duct, the dose rate is estimated at 60 mREM/hr. during the first couple of hours following a postulated LOCA.
The maximum integrated dose values for the HVAC room are:
whole body gamma ray
= 3.5 Rem thyroid
= 13.0 Rem skin beta dose
= 8.7 Rem In order to meet the habitability requirements, radiation monitoring equipment will be provided which will:
- 1.
Automatically provide TSC inlet air filtration which precludes the admission of contaminated air into the TSC.
- 2.
Provide local area radiation monitors to alert personnel to a high radiation condition.
Both area monitors and particulate detectors will alarm locally and will be provided with remote readout and alarm in the TSC communications room.
Portable monitoring equipment dedicated to the TSC will be used (if necessary) to provide additional detection capability.
Protective equipment in the form of anticontamination clothing and respiratory protective gear will be stored in the TSC and provided for the staff who must travel between the TSC and the control room or the EOF under adverse radiological conditions.
1.6 COMMUNICATIONS The TSC voice communications equipment will include all of the equipment specified in section 2.7 of NUREG-0696.
Interplant communications are provided by a dimension PBX system and which will obtain power from the TSC diesel in the event of loss of onsite power. Offsite telephone switching facilities are provided with battery backup by the phone company.
1.7 INSTRUMENTATION, DATA SYSTEM EQUIPMENT AND POWER SUPPLIES The TSC will have its power requirements satisfied by a new Motor Control Center (MCC) rated 480V, 3-phase, 3-wire, installed on el. 15' of the IP3 Administration Building. The new MCC will be used exclusively for the TSC's power control requirements.
A new 480V unit substation located in the Turbine Generator Building at el.15' will furnish the 480V power to the new MCC bus.
In the event, of a unit substation power failure, an automatic transfer switch will transfer the normal MCC Supply from the unit substation to a standby emergency diesel generator set which will start-up automatically upon sensing the normal power supply failure. The diesel generator will be starting on full operating load.
The TSC data system equipment will be supplied from the MCC through an isolation transformer and an uninterruptible power supply (UPS) designed to eliminate normal line transients and those associated with the starting of the diesel generator.
Figure II shows the general arrangement of the data system equipment.
Significant design features of this system are:
Primary and backup 32 bit computer systems, each with its own set of peripherals including large moving head disks, magnetic tapes, line printers and CRT's for program development and maintenance.
Three color graphic CRT displays in the TSC, each with its own keyboard and hard copy device.
Redundant, remote multiplexed I/0 to handle the input of non IE signals.
IE signals will be sent to the TSC data system through IE qualified SPDS channels via fiberoptic modems which will provide the necessary isolation in accordance with GDC 24.
High speed data link between the TSC data system and the Environment Monitoring Computer which will provide to the TSC all the meteorological and offsite radiological information that will be available in the EOF.
Data concentrator and high speed modems to provide a display in the EOF with the same information as is available in the TSC.
The above hardware configuration will also be used as the new plant process computer. Extensive testing will be performed on the entire system to assure that the plant process computer programs do not degrade the integrity of data supplied to the TSC or the security of the software used to process TSC data.
1.8 TECHNICAL DATA AND DATA SYSTEM The TSC data system will have-as input more than 1000 plant variables including all those parameters specified as type A, B, C, D and E variables in Regulatory Guide 1.97, Revision 2, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident."
In addition, data available to the SPDS and EOF will also be available in the TSC.
The TSC data system will provide sensor validation, signal quality checks and multiple stage parameter alarming capability.
All data available to the TSC-data system will be stored in a continuous mode onto a short term storage device. Continuous storage utilizes a pre-defined buffer area in which the oldest data is over-written when the buffer is full.
Data in short term storage is periodically dumped to the long term storage device to archive all relevent information.
Short term storage is designed to accumulate 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> of data. Transfer of data from the short term storage device to the long term (permanent) storage device is made every 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> or on operator command. A message is displayed to alert the operator that a data transfer should be initiated. Use of both short term and permanent storage devices provides optimum capability for data retrieval and archiving.
MODEHS AND CIRCUITS CONTROL RlM FIDEROPTIC lOMDEM TO
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SECOHOIARY CIAtINEL a
FIACKUP SPhJS DI SPLAY PPI'S I(
FIOURlOPllC PPI To 11IhS I AI! 2 SECOIDA1Y sll~i(tiI Eflux
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(EERGENCY OPERATIONS FACILITY DISPAY COLIT\\
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, *A AN MlODEMS PROPOSED SYSTEII C0,;IFIGUIPRTION FOR PASNY INDIAN POIIIT UNIT NO.
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Data retrieval is provided using color graphic CRT's and line printers.
All CRT stations can access data independent of the other stations. Any stored information can be recalled and displayed using variable time and range formulas.
Graphical trends and charts as well as alphanumeric logs can be requested by the operator. Output of alphanumeric information to the printer can be initiated by operator command.
/
Information on the short term storage device is available for immediate recall.
Information which has been transferred to permanent storage can be retrieved by mounting the required storage mediums to the playback device.
In addition to the three-color graphic display stations located in the internal radiation monitoring, waste management and plant recovery sections of the TSC (see figure I), a network of video monitors will provide plant variable information to other TSC locations.
The primary (non-qualified) SPDS display will be available to any color graphic display station in the TSC.
1.9 RECORDS AVAILABILITY AND MANAGEMENT The TSC will have a complete and up-to date set of plant records and procedures (as indentified in section 2.10 of NUREG-0696) in the form of microfilm, microfiche, aperature cards and hard copy records.
The necessary reproduction and display equipment will be available in the TSC to provide hard copy of any records to TSC personnel.
Document control procedures will be modified to assure that updated copies of all of the above records and procedures are stored in the TSC.
- 2.
OPERATIONAL SUPPORT CENTER 2.1 HABITABILITY The OSC will be located in an area adjacent to the TSC and will share TSC's HVAC facilities. Refer to figure 1 for the general arrangement of the OSC.
2.2 COMMUNICATIONS Communication facilities will be established to meet the requirements of section 3.3 in NUREG-0696.
- 3.
EMERGENCY OPERATIONS FACILITY 3.1 LOCATION, STRUCTURE, AND HABITABILITY The EOF will be comprised of two existing facilities: the Emergency Control Center (ECC) and Recovery Center (RC). The relationship of these facilities to the plant is shown in figure III.
The locations of the ECC and RC provide optimum functional and availability characteristics. A backup EOF is under study (refer to note).
Note:
Con Edison/PASNY are negotiating to use the New York State Office of Disaster Preparedness Southern District Office in Poughkeepsie as the backup EOF. This facility is 33.2 miles from the site.
If it is decided to utilize this facility, an exemption request will be discussed with the staff.
The ECC and RC buildings are well engineered structures for the design life of the plant.
The ECC is being evaluated for modifications that will bring the protection factor to greater than 5. The present walls already provide this protection factor, and the existing roof is being evaluated by an architect engineer for upgrading to this level of protection.
The existing HVAC system is capable of functioning with HEPA filters.
These filters will be installed in the system. The system has the capability of operating in a recirculation mode with filtered intake providing fresh air makeup.
A study will be undertaken to determine if the RC meets-the-habitability requirements in NUREG-0696 and if any modifications are needed.
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3.2 STAFFING AND TRAINING All licensee activities in the EOF will be supervised by the Emergency Director who will normally be the Resident Manager. The Emergency Director is responsible for coordinating all phases of the emergency response to regain control of the accident condition and to mitigate its consequences.
His authorities and responsibilities include recommendations for protective actions to authorities responsible for implementing offsite emergency measures and the reclassification of any emergency condition as warranted by circumstances.
The Radiological Assessment Team Leader reports to the Emergency Director in the EOF. His primary function is to provide the Emergency Director with current and projected offsite radiation dose estimates. Secondary functions may include, e.g., advice and recommendations concerning emergency exposure levels, recommendations for radiological monitoring methods, interpretation of inplant monitoring or sampling results etc.: This position will normally be filled by the Radiological and Environmental Services Superintendent.
The Communications Team Leader (CTI) reports to the Emergency Director in the EOF. The CTL is charged with providing clear, accurate communications and serving as liaison between the Emergency Director and the onsite emergency organization and onsite or offsite organizations or agencies.
Training of EOF personnel shall be accomplished by regularly scheduled exercises, drills and classroom work as detailed in the emergency plan.
3.3 SIZE In the following discussion refer to figures IV, V and tables I and II.
VI and associated Currently, 16 people are projected to be in the ECC as follows:
PASNY -8 Local - 4 State - 1 FEMA
- I NRC
- 2 The remainder of Center.
At this individual is as Lower Level Upper Level the anticipated NRC staff will locate in the Recovery level of staffing, the square footage of working space per follows.
Comp. Rm.
Cont. Rm.
Comp. Rm.
Obs.. 'Deck Conf. Rm.
Mtg. Area Total Equipment Space Personnel Space 155 370 220 140 235 215 1335 200 1135 Sq. ft. / person = 1135/16 = 70.9 Adequate space is available in the Recovery Center to provide working space for better than 70 people which will more than satisfy the need of the remaining EOF personnel.
Adequate space is alloted in the EOF facilities for data system equipment, its repair, maintenance and service. There is space for ready access to communications equipment.
In several cases, equipment is accessible from more than one work station, or is centrally located for accessibility.
EOF data displays will be placed in locations that will provide ready access to all utility, local, state, NRC, and FEMA personnel.
Plant records and historical data areavailable in the Recovery Center. For details of the records available, please refer to. section 3.8.of this report.
There is separate office space in the Recovery Center and/or ECC available to the NRC. There is adequate space for separate office space for 5 NRC personnel.
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T.
LOWER LEVEL CC FIGURE IV
TABLE I LOWER LEVEL (ECC)
FURNITURE AND EQUIPMENT LIST TELEPHONE COMMUNICATION CABINET (3)*
TAPE RECORDER PHONE COMMUNICATIONS TERMINAL BOXES RADIO COMMUNICATIONS TERMINAL BOXES UNINTERRUPTIBLE POWER SUPPLY BATTERY PACKAGE (2)*
ELECTRIC DISTRIBUTION PANELS REFERENCE COUNTER AND STORAGE DESK WITH RADIO/TELEPHONE COMMUNICATIONS EQUIPMENT AND STORAGE SIDE TABLE MAP TABLE AND STORAGE CRT DESK WITH RADIO/TELEPHONE COMMUNICATIONS EQUIPMENT AND STORAGE CRT FOR DOSE ASSESSMENT AND PLANT PARAMETERS (2)*
REFERENCE COUNTER AND STORAGE CRT (MIDAS) (3)*
MAP REFERENCE CONSOLE AND STORAGE DESK AND STORAGE CABINET AND BACKUP MET RECORDER CABINETSILENT 700 DISK DRIVE (MIDAS)
PRINTER (MIDAS)
REUTER STORES CPC AND B/U MET TAPE,BOOK AND DISK STORAGE CPU AND TAPE DRIVE (MIDAS)
TELEPRINTER (REUTER STOKES)
PDP 11/04 COMPUTER (ARAC)
PRINTER PLOTTER (ARAC)
TELEPRINTER (ARAC)
FIRE SUPPRESSION CONTROL PANEL CRT (ARAC)
TABLE AUTOMATIC ALARM SYSTEM PANEL
- Note:
The number in parenthesis corresponds to the number of pieces of furniture/equipment.
4 ~
A I~1 UPPER LEYEL (ECC FIGURE V
0 0
TABLE II UPPER LEVEL (ECC)
FURNITURE AND EQUIPMENT LIST KITCHEN UNIT TABLE DESK AND COMMUNICATIONS (6)*
PROJECTION SCREEN CRT (DOSE ASSESSMENT AND PLANT PARAMETERS) (2)*
- Note:
The number in parenthesis corresponds to the number of pieces of furniture/equipment.
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FIGURE VI 0
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3.4 RADIOLOGICAL MONITORING Portable radiation monitors will be provided in both the ECC and in the RC.
An Eberline Model RM-14 type instrument equipped with a "Frisker" will indicate gamma levels.
A continuously sampling gas monitor will indicate the level of airborne radioactivity. The RM-14 and gas monitor alarms will be preset to alert ECC and RC personnel of adverse conditions.
Upon activation of the preset air monitor, the appropriate personnel will begin taking periodic filter samples, utilizing an air sampler.
The samples will be analyzed in a facility utilizing shielded radiation detectors.
The technique is capable of distinguishing radioactive concentrations as low as 10 - 7 microcuries/cc.
3.5 COMMUNICATIONS
'The EOF is. equipped with regular dial telephones, radio communications and direct line phones between the EOF and the TSC and control room.
EOF/NRC voice communication currently exists with the hotline telephone on the NRC emergency notification system (ENS) to the NRC Operations Center and a dedicated telephone on the NRC health physics network (HPN). These lines will be installed in the NRC work area within the ECC and RC.
EOF/State and local emergency operations centers voice communications currently exists with the Nuclear Emergency Hot Line Network.
The primary means of communication is telephone and backup is provided by radio. Further means of backup will be provided by redundant power sources (5 KV generator and batteries) for the telephone system. A microwave radio system will provide back-up channels for critical voice communications.
Three. spare commercial telephone lines to the plant are available for use by the EOF during emergencies, and three additional lines will be installed.
Other communications facilities as specified in section 4.6 of NUREG-0696 will also be available in the EOF.
3.6 INSTRUMENT, DATA SYSTEM EQUIPMENT, AND POWER SUPPLIES The EOF will have access to three data systems.
The Environmental Monitoring Computer (MIDAS) and associated displays and printers.
A color graphics display console connected to the TSC data system via data concentrators and modems (see figure II)
Remote data collection and display station linked to the atmospheric release advisory capability service (ARAC) directed by the Lawrence Livermore Laboratory.
All data systems servicing the EOF will have power supplied by uninterruptable power supplies to prevent the loss of data during power supply failures and fluctuations.
Figure VII shows the general arrangement of the MIDAS data system. Not shown on the figure is the input from a backup meteorological tower.
Information can be obtained from the system via a graphics display console, remote access via standard dial up lines and remote access terminals or via a link to the TSC data system (see fugure II).
The color graphics display console in the EOF will have access to all the information available to the TSC data system including the SPDS displays.
The remote data collection and display station linked to the ARAC system consists of a mini-computer data acquisition hardware connected to the meteorological tower, a high speed data link to the Lawrence Livermore Laboratory site and a graphics display console. Data from the meteorological tower will be transmitted through the station to the Livermore laboratory where it will be analyzed along-with data from the National Weather Service and Air Force Global Weather Central to provide atmospheric dispersion data which will be transmitted back to the site, and available for display on the graphics display console. The system will be used as a backup for the MIDAS system.
3.7 TECHNICAL DATA AND DATA SYSTEM Through the MIDAS or ARAC systems, the EOF will have access to those meteorological variables specified in proposed revision 1 to Regulatory Guide 1.23, "Meteorological Measurements Programs in Support of Nuclear Power Plants,"and in NUREG-0654, revision 1, appendix 2.
Sensor data of the type A,B,C,D and E variables specified in Reg.
Guide 1.97, Revision 2, will be accessible through the color graphics.
display station connected to the TSC display system. The SPDS displays will also be available through this display station.
FIGURE vii INDIAN POINT MIDAS SYSTEM HARDWARE CONFIGURATION ME EOROLOGICAL TOWER I
COMPUTER ROOM CALIBRATIO SWITCHCOMMUNICATIONS.
MULTIPLEXER DISC AII CDNr It t
MO F.MPACK TAPE
38-RECORDS AVAILABILITY J MANAGEMENT Stored in the EOF will be up-to-date records including:
The Site Emergency Plan, Records related to licensee, state, and local emergency response
- plans, Offsite population distribution data, evacuation plans, environs radiological monitoring records.
Other records will be obtained from the TSC by facsimile transmittal.
Document control procedures will be modified to assure that current and com plete copies of all of the above records and procedures will be stored in the EOF.
- 4.
SAFETY PARAMETER DISPLAY SYSTEM 4.1 LOCATION & SIZE One of four color graphic control room displays connected to the TSC data system will be dedicated to the primary SPDS display. Any of the four control room displays can be directed to this function if the primary display fails. The control room will also contain two plasma displays connected to the seismically qualified backup SPDS system.
Any of the three TSC color graphic display stations or the color graphic display station in the EOF can be directed to display the same SPDS as is available on the primary SPDS in the control room.
Displays in the control room will be located in free standing enclosures, whose design and location will be such as to not interfere with normal movement or with full visual access to other control room operating systems and displays.
4.2 DISPLAY CONSIDERATIONS The primary SPDS will be an integral part of the TSC data system and as such will employ elements of a common data base and the same color graphics display system.
The SPDS will be made up of a display hierarchy consisting of the following levels:
Level 1 -
Overall Status Level 2 - Function Status Level 3 -
Sub-Function Diagnostic Figure VIII shows examples of the overall status and one of the level 2 displays while figure IX shows 2 examples of level 3 displays.
These examples are supplied to indicate the formats being considered for the SPDS.
The actual parameters to be used are currently under revie and will be supplied in an addendum to this conceptual design submittal.
FIGURE VIII LEVEL 2 LEVEL 1 a
FIGURE IX LEVEL 3
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Maximum operational utility and flexibility is provided by allowing the operator to communicate with and direct the operation of the CRT displays.
4.3 DESIGN CRITERIA As an integral part of the TSC data sytem, the primary SPDS will meet all of the design criteria for that system (refer to section 1.7).
To provide for operation during and following earthquakes, a fully IE qualified backup SPDS will be supplied to the control room only.
The qualified SPDS (see figure II) utilizes a microprocessor - based design for the signal processing equipment in conjunction with a display having alphanumeric representation and associated keyboard for each of its two channels. Each channel accepts and processess input parameter signals and transmits its output to the alphanumeric display. In addition, each channel transmits its output to the TSC data system.
- 5. NUCLEAR DATA LINK 5.1 Description Because of its considerable capacity and flexability it is anticipated that the TSC data system will be able to supply all the information required of the nuclear data link (NDL) when the NRC requirements for this system become better defined.
The computer room located in the TSC has been design with additional space to accommodate any NDL related equipment.
Power supplies and HVAC equipment all will have spare capacity.