ML19344D667
| ML19344D667 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, Zion, LaSalle  |
| Issue date: | 12/26/1979 |
| From: | BECHTEL GROUP, INC., BECHTEL POWER CORP. |
| To: | |
| Shared Package | |
| ML19344D666 | List: |
| References | |
| NUDOCS 8004250428 | |
| Download: ML19344D667 (32) | |
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4 DESIGN' CRITERIA
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col'CEPTUAL DESIGN DESCRIPTION t
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ZION, DRESDEN, QUAD CITIES, AND LA SALLE-i NUCLEAR POWER STATIONS-.
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TABLE OF CONTENTS PAGE 1.0 SCOPE AND OBJECTIVES 1
2.0 FUNCTION 1
3. 0' ARCHITECTURAL AND STRUCTURAL 2
4.0 HEATING, VENTILATING, AND AIR CONDITIONING 5
5.0 INSTRUMENTATION 7
6.0 ELECTRICAL POWER SUPPLY 9
7.0 RECORDS STORAGE AND REPRODUCTION FACILITIES 10 8.0 COMMUNICATIONS 12 t
9.0 SPARE PAFTS 12
10.0 REFERENCES
12 APPENDIXES A
Quad Cities Floor Plan B
Dresden Floor Plan C
Zion Floor Plan D
La Salle Floor Plan E
Civil / Structural Design Criteria F
HVAC System Diagram t
G TSC Monitored Parameters t
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Abstract This report defines the design criteria and provides a conceptual design for the Technical Support Centers to be installed at the Commonwealth Edison. Company (CECO) Zion, Dresden, Quad Cities, and La Salle nuclear power stations.
This document contains descriptions of facility heating, ventilating, and air conditioning (HVAC) design, electrical power supply, instrumentation features, arrangement, permanent engineering records storage, and communications links.
The Technical Support Centers described are intended to ful f ill the requirements of Section 2.2.2.b of NUREG 0578.
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1.0 SCOPE AND OBJECTIVES This report provides design criteria and a conceptual design for four technical support centers (TSC).
These TSCs will be constructed on2 each at the Zion, Dresden, Quad Cities, and La'Salle nuclear power stations.
Each TSC will be designed to respond to emergency conditionn for all of the nuclear power units on that site.
2.0 FUNCTION The function of the TSC is to reduce the need for control room access and to provide support to the reactor command and control function following a plant accident.
In the event th' TSC is not available, the TSC functions would be carried out in the control room.
The TSC provides:
a)
Alternative to control room monitoring and diagnosis of accident conditions b)
A location for technical and management review and approval of emergency activities c)
Communication of plant status to the offsite emergency operations center, NRC, government agencies, and nuclear steam system supplier.
2.1 ALTERNATIVE TO CONTROL ROOM MONITORING AND DIAGNOSIS OF ACCIDENT CONDITIONS a)
Establish the location, type, and cause of the accident.
b)
Assess damage resulting from the accident and determine the status of plant power block and engineered safety features.
c)
Predict facility response and' determine post-accident performance, d)
Recommend and approve corrective control room actions required to isolate and contain defective systems, and to bring the reactor to a cold shutdown
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2.2 TECilNICAL AND MANAGEMENT REVIEhi AND APPROVAL OF EMERGENCY ACTIVITIES a)
Determine the immediate ef fect of the accident on the health and safety of the public, and recomajend actions to minimize adverse effects.
b)
Monitor key parameters to assure the continued health and safety of the public during the entire post-accident period.
c)
Plan logistics for personnel and materials for emergency procedures.
3.0 ARCIIITECTURAL AND STRUCTURAL 3.1 GENERAL ARCHITECTURAL DESIGN CRITURIA Each TSC will cons: st of a space or adjacent spaces large enough to provide adequate working space for a team of 25 people and supporting equipment.
The people will work in this space for 8 to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> per day; no sleeping accommodations are provided.
Maximum uce of the station's existing facilities for eating, washing, and toilet accommodations is planned.
Generally, no lunch, shower, or toilet space is provided within the TSC.
The TSC space or spaces will be as flexible as possible with respect to layout, work stations, furnishings, storage, communications, and equipment to allow the physical arrange-ments to respond as tasks are formulated.
The habitability requirements of the TSCs including shielding, air conditioning, lighting, and acoustics, will be designed to minimize environmental stresses.
The layout and fur-nishings will be designed to provide a range of flexible settings including individual isolation and group conference activities as well as accommodating extended monitoring and problem solving work occupancy.
In. addition to shielding and air treatment, protective brdathing apparatus (respirators) and potassium iodide pills will be stored within the facility for use as required.
Fire protection for the TSC will be provided in accordance with Nuclear Mutual Limited and authorities having jurisdiction, yr. Y 2
The TSC work station areas may normally be used as t aining rooms, conference rooms, or temporary work areas.
5 e TSC will not be used for permanent office work space.
3.2 SITE LOCATION AND DESCRIPTION Each TSC will be located within the site sccurity boundary, although the TSC areas are not considered vital areas to the plant security system.
Each TSC will be sited to allow physical access to the station control room within a walking time of 5 minutes or less.
The estimated horizontal and vertical walking distances have been noted on the attached TSC floor plans (Appendixes A through D).
The Quad Cities Station TSC will be located in an existing building near the southeast corner of the power block.
This building is the former station gatehouse, which has been replaced by a new security building.
The building will be altered and a second floor added for its intended TSC purpose.
This location is approximately 130 feet frc.m the station
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service building, which houses the records storage area and affords quick access to the station control room.
The location plan of the Quad Cities TSC, and the proposed TSC floor plan are shown in Appendix A.
The Dresden Station TSC is planned to be a new structure built against the south side of the existing administration building, adjacent to the records storage building.
The existing facilities in the administration building obviate the need to duplicate such facilities within the new TSC.
The location plan of the Dresden TSC and the proposed TSC floor plan are shown in Appendix B.
The Zion Station will be located on the mezzanine level (elevation 617'-0") of the existing auxiliary building and turbine building.
This location is two floors directly below the Unit 1 control room.
The existing spaces will be modified to provide TSC office and conference areas as-necessary.
The location plans of the Zion TSC and the proposed floor plan'are shown in Appendix C.
The La Salle Station TSC will be located on the basement mezzanine level (elevation 694'-6") of the existing service building.
This. location is near the existing records storage vault and existing lavatory facilities.
Also located on this same floor level are the NRC and security offices.
There is easy access from the gatehouse to the TSC area using the existing corner stairwell.
The location of the LaSalle TSC, as well as the proposed TSC floor plan, are shown in Appendix D.
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3.3 ARCHITECTURAL CONCEPTS Architectural design, materials, and finishes of the TCSs will conform to the existing stations they serve.
3.4 STRUCTURAL Col;CEPTS a)
General The TSCs shall be designed in accordance with the criteria established herein.
The TSCs shall be evaluated for-cknsistency with the criteria estab-lished for the remainder of the plant, i.e.,
appro-priate sections of the plant FSAR shall be complied
- with, b)
Seismic Classification The TSCs are not Seismic Category I structures as defined in URC Regulatory Guide 1.29, Seismic Design Classification.
TSCs shall be designed for seismic loads in accordance with UBC requirements for Zbne 1, using an importance factor of 1.5.
c)
Natural Phenomena Severe natural phenomena such as floods and tornadoes shall be evaluated for consistency with the criteria established for the remainder of the plant; occupancy may not be possible for all conditions.
Analysis procedures shall be followed to confirm that the structures will not collapse.
d)
Shielding Requirements Minimum concrete thicknesses shall be established to limit personnel exposures to 5 rem to the whole body over a 30-day period.
3.5 CIVIL / STRUCTURAL DESIGN CRITERIA Appendix-E provides a_ description of quality standards, shielding requirements, 'and design loads.
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4.0 HEATING, VENTILATING, AND AIR CONDITIONING 4.1 FUNCTION The technical suppcrt center HVAC system performs the following functions:
a)
Provides heating, ventilating, and air condi-tioning for inside design conditions allowing personnel comfort and safety at all times, including in the event of a nuclear incident b)
Automatically shifts ventilation dampers in the makeup air path to a filtration / adsorption mode upon detecting high airborne radiation contamination c)
Minimizes infiltration from outside 4.2 DESIGN BASES a)
The system is designed to perform the technical support center heating, ventilating, air condi-tioning, filtration, and radiation adsorption in a safe, reliable, efficient, and economical manner, b)
The equipmer.t and components are not 0-listed or manufactured to Seismic Category I requirements.
Redundant ventilation systems are not provided.
c)
Heating, Ventilating, and Air Conditioning The HVAC requirements for the technical support center are based on the following:
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1)
Outdoor temperature of approximately -10F winter and 95F summer
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2)
The HVAC system will maintain the center at approximately 70F during normal operation 3)
Providing filtration and adsorption to main-tain radiation levels below maximum permissible concentration 4)
The HVAC systen will utilize a minimum amount of outside air to provide' ventilation require-ments and preclude excess infiltration of outside air.
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4.3 DESCRIPTION
The technical support center HVAC system is shown on the flow diagram, Appendix F.
The HVAC system is constant volume, low velocity, single zone-type with supply, return, and outside air duct work.to distribute air to the various areas, a)
The HVAC system will consist of the following HVAC units:
1)
The makeup air filter unit will be used only during a nuclear incident.
This unit will have sufficient charcoal capacity to clean the outside air before discharging it to the air handling unit.
The makeup filter unit will be sized for 1,000 cfm capacity, with 250 cfm taken from the outdoors and 750 cfm taken from the return duct.
2)
The air handling unit will be package-type consisting of filters, Dx cooling coil, electric heating coil, and belt-driven centri-fugal fan.
The air handling unit will operate during normal plant operation and during a nuclear incident to supply treated air to the TSC area and to maintain the TSC area at 1/8-inch w.g.
positive pressure with respect to the outside.
3)
The condensing unit will be either air-cooled or water-cooled, whichever is more practical.
b)
Components Design 1)
The charcoal adsorber will be the tray type with side access.
Charcoal adsorber tent canisters will-be provided.
2)
The outside air, return air, and makeup air filter upstream and downstream damper will be the tight' shutoff parallel blade type.
. Seals will be provided on the blades and jamb.
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e A room heating and cooling the rmos ta t is provided with en-fan-auto switch to control the electric heating coil and direct expansion coil which is piped to an air-cooled condensing unit.
The refrigeration condensing unit is interlocked to operate when there is a cooling requirement and the cooling coil solenoid valve is open.
Pressure gages are provided across each filter bank and the adsorber.
Excessive pressure drop will be alarmed.
A radiation detector is provided downstream of the supply air fan.
In the event that radiation is detected, an alarm will be annunciated, the outside air damper will close, and the system will operate with full recirculation.
A thermistor temperature detection system is provided for the charcoal adsorbers which will detect and annunciate an alarm in the event of excessive heat in the charcoal bed and will activate charcoal filter unit supply fans.
In the event that a system malfunction occurs, an alarm is energized and annunciated in the TSC and the main control room.
TSC personnel can investigate the cause of the mal-function and, if necessary, can override automatic controls and manually operate the air handling unit and its associated equipment.
During low air flow or in the absence of air flow in the ducts, an alarm indicates fan failure.
5.0 INSTRUMENTATION 5.1 INPLANT DATA The computer capabilities at each of the stations will be enhanced to provide TSC data displays.
New computers will interface the present station computers by DMA or by RS 232 data links.
Usage of the new computers for the TSC function will provide consistency of data presen '
tation and implementation at the BWR stations.
The new comnsters will be purchased by Ceco; sof tware implementation for the TSC function will be by CECO.
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The Zion TSC data will be provided either in the same manner as at the BWR stations or by replacing the present station computers with new computers moved from another CECO station.
Software implementation will be by CECO.
The data presentation for the TSC function at all stations will be by color graphics CRT displays.
Two typers will provide hard copy records, one for alarm presentations and one for a user input / output interface.
CCTV will be used to supplement the computer derived data when it is found to be advantageous.
Direct hardwired displays will also be used where advantageous.
Appendix G provides a specific list of data to be available in each TSC.
The following types of data will be available within the TSC.
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a)
Plant safety parameters:
1)
Secondary system (Zion only) 3)
ECCS system 4)
Feedwater and makeup system 5)
Containment b)
Inplant radiological parameters:
1)
Containment i
3)
Effluent treatment 4)
Release paths c)
Offsite radiological data:
'1)
Meteorology 2)
Offsite Radiation Level.
In addition, radiation monitors and portable air samplers will be provided to measure radiation levels and airborne
. radioactivity concentrations within the TSC.
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e The hardwired interconnection of the TSC to Class lE signals will be isolated to ensure that operation of, or failure within, the TSC does not degrade the quality of control room signals.
No such interconnection will be used if the infor-mation is available from the unit (or plant) computer.
No existing Class lE signal circuit will be opened to provide separate isolation to the TSC if a suitable buffered non-Class 1E associated circuit is already available; the TSC isolater will be placed in the associated circuit.
5.2
'OFPSITE RADIOLOGICAL DATA Meteorological data (wind speed and wind direction) will be displayed with the TSC.
Calculational capability will exist within the TSC or be available from an of fsite location for assessment of of fsite c
meteorological conditions and doses.
6.0 ELECTRICAL POWER SUPPLY Each TSC shall be considered a separate entity from the existing power block.
A normal source of electrical power will be taken from an existing non-Class lE 480 vo't load center that is part of the station common services.
When normal power is lost, a backup power supply from a diesel generator, as well as a TSC battery, will be provided.
The power requirements for the TSC will approximate 85 kW.
6.1 LOADS TSC electrical power requirements:
a)
IIVAC Supply fan 5 hp (each)
Compressor 15 hp Condenser fan 3 hp Resistance heating 20 kW b)
Lighting 2
2 3 watts /ft x 2,500 ft 7.5 kW p.*Y 9
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Other Battery charger 15 kW Convenience outlets 10 kW Copying machines 5 kW TOTAL 85 kW 6.2 DESIGN In the event of loss of the normal source of ac power, a non-Class lE standby power supply system will be provided.
This system will include a diesel generator, nominally sized at 100 kW, which will start if power has not been restored after approximately 30-60 seconds.
The TSC computer will be connected to an uninterruptible pouer supply.
The batteries shall be sized to furnish suf ficient power to ensure the operation of the computer and its peripheral equipment and to provide emergency lighting as required in the TSC.
The diesel generator will have sufficient capacity to recharge the battery designated for TSC operation.
All TSC loads will be transferred from their normal source of power to the diesel generator in an orderly fashion once the diesel generatcr has started.
Return of normal source voltage will not disconnect loads from the diesel generator.
% manual-or operator-initiated transfer of load will be reo.; ired.
The diesel generator shall have a day tank with gravity feed to the diesel generator.
A 7-day capacity storage tank with fuel pumps will feed the diesel day tank.
A fire hazards evaluation of this equipment may have to be performed based on the the proximity of this equipment to other site-sensitive safety-related equipment.
The electrical design for the TSC is to consist of the power distribution, electrical controls, lighting, and grounding systems and shall be designed in accordance with the latest applicable sections of the National Electrical Code.
7.0 RECORbS STORAGE AND REPRODUCTION FACILITIES A records storage area will be provided within the TSC.
This area will contain design documents required to diagnose plant problems at the system level.
Information required for detailed diagnosis at the component level will be available at the station records center.y.?
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e a)
The following documents will be stored within the TSC:
1)
Syste m P& ids 2)
Electrical single-line diagrams 3)
Electrical elementary diagrams 4)
Station manual, plant operating procedures, and emergency operating procedures (GSEP) 5)
Plant technicel specifications b)
The following documents will be stored in their normal plant records storage area and will be available to the TSC:
1)
General arrangement drawings 2)
Equipment location drawings 3)
Proccss flow diagrams 4)
Piping area drawings i
5)
Electrical wiring diagrams 6)
Interconnection wiring diagrams (if available) 7)
Control logic diagrams 8)
Mechanical equipment list 9)
Instrument index 10)
Instrument-setpoint index 11)
Piping class summary sheets 12)
Radiation zoning drawings (normal operation and podi accident) 13)
Radiation line classification drawings 14)
Vendor print index 15)
Site aerial photographs and maps out to the LPZ 16)
Airborne radiation records p.1
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These documents will be stored on aperture cards, microfiche, or in hard copy form.
A microfiche reader, a 35 mm reader /
printer, and a copy machine will be located within the TSC.
These machines will be supplied with either offsite electrical power, or power from the onsite backup power source.
8.0 COMMUNICATIONS Offsite communications will be provided via standard telephone and microwave link.
Approximately 10 telephones will be provided for communication to the emergency offsite response center, NRC,. government agencies, and nuclear steam system supplier.
A microwave communications link will be available between each TSC and CECO headquarters in Chicago.
Offsite communications other than telephone for NRC representa-tives will be provided by the NRC.
Two modems will be available within the TSC which can be utilized to transmit data.
These modems can be utilized to transmit data from the TSC to the NRC, nuclear steam system supplier, architect-engineer, or CECO engineering staff in Chicago.
Communications between the TSC and the control room will be provided via two different means.
9.0 SPARE PARTS A limited spare parts inventory will be maintained to allow minor repairs to instrumentation and reproduction equipment.
The spare parts inventory will be itemized after selection of specific equipment.
10.0 REFERENCES
NUREG 0578, TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations, July 1979 i
NUREG 0585, TMI-2 Lessons Learned Task Force Final Report, October 1979 U.S. Nuclear Regulatory Commission, Regulatory Guide 1.140 ASilRAE Handbook 'of Fundamentals, Equipment, Systems, and Applications Sw?
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APPENDlX F 5"
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, PROPOSED iECHNICAL SUPPORT CENTER S.HEET 1 of i,,'
A,
,H V A C FLOW DIAGRAM.
Nen e d>
r o.
APPENDIX G TSC MONITORED PARAMETERS 1.0 TSC PARAMETERS FOR BWRS (OUAD CITIES, DRESDEN, AND LA SAbi,E STATIONS)
- 1.1 PLANT SYSTEM PARAMETERS a)
Reactor pressure 2)
Reactor water level 3)
Reactor water temperature 4)
Relief and safety valve position 5)
Source range monitor (SRM) readings b)
Emergency Systems 1)
Pump status a.
RIIR (LPCI) b.
311R service wat'er (CCSW) c.
Core spray d.
iligh pressure coolant injection (IIPCI)
(IIPCS for La Salle)
2)
Flows a.
Core spray b.
LPCI c.
IIPCI (llPCS for La Salle) 3)
Pump discharge pressure a.
Core spray b.
LPCI c.
HPCI (IIPCS for La Salle) c)
Containment 1)
System parameters Suppression pool water temperature a.
b.
' Suppression pool water level c.
Wetwell pressure d.
Drywell pressure e.'
Wetwell hydrogen concentration f.
Drywell hydrogen concentration
. g.
Main steam isolation valve, leakage control system (La Salle only) 2)
Isolation: valve status groups I, II, and III
- ThislistdoesnotapplytoD$'c~ ben 1.
See Section'2.0.
~
,,o l.2 RADIATION PARAMETERS a)
Drywell Radiation b)
Standby Gas Treatment System Blower Status c)
Release Paths 1)
Reactor building vent - high range noble gas 2)
Main chimney - high range noble gas d)
Area Radiation Monitors 1)
Reactor building 2)
Auxiliary building (La Salle only) 1.3 METEOROLOGICAL DATA
~
a)
Wind Speed b)
Wind Direction t
1.4 TSC RADIOLOGICAL DATA t
a)-
TSC Radiation Level b)
TSC Airborne Radioactivity Concentration 2.0 TSC PARAMETERS FOR DRESDEN 1 2.1 PLANT SYSTEM PARAMETERS.
V a)
Reactor Coolant System Parameters 1)
Reactor pressure 2)
Reactor water level 3)
Steam drum level 4)
Source range monitor (SRM) readings b)
Emergency Systems 1)
Pump status a.
IIPCI b.
Core spray Post-incident / containment c.
d.
Standby liquid control p.7 l
y 2)
Flows a.
HPCI b.
Core spray 3)
Pump discharge presssre a.
IIPCI b.
Core spray c.
Fost-incident / containment 4)
Emergency condenser a.
Level b.
Valve status c.
Vent monitor i
c)
Containment 1)
System parameters a.
sphere level b.
Sphere pressure c.
Sphere hydrogen concentration 2)
Isolation valve status
(
2.2 PLA!!T RADIOLOGICAL PARAMETERS i
a)
Containment Radiation b)
Release Paths 1)
Radwaste stack - high range noble gas 2)
Main chimney - high range noble gas c)
Area Radiation Monitors 2.3 METEOROLOGICAL DATA a)
Wind Speed b)
Wind Direction i
2.4 TSC RADIOLOGICAL LEVEL 2
a)
TSC Radiation Level b)
TSC Airborne Radioactivity Concentration l.
I 4:s.*Y
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t' 3.0 TSC P/gjAJ1ETLil5 FOR ZI0fi 3,1 PLANT SAFETY PARAMETERS a)
Core Exit Temperature b)
Reactnr Coolant System 1)
RCS hot leg temperature 2)
RCS cold leg temperature 3)
RCS pressure 4)
Pressurizer level c)
Secondary System 1)
Steam line pressure 2)
Steam generstor level - nurrow range 3)
Steam generator level - wide range d)
ECCS 1)
High head safety injection' pump flow e)
Containment Parameters 1)
Containment pressure 2)
Containment sump water level 3.2 RADIATION PARAMETERS-a)
Steam Generator Blowdown Radiation b)
Condenser Air Ejector Radiation c)
Containment Radiation - High Range d)
Effluent Radioactivity 1)
Noble gases 2)
Halogens and particulates f)
TSC Data 1)' TSC radiation _ level 2)
TSC airborne radioactivity concentration 3.3
-METEOROLOGICAL DATA a)
Wind Speed b)
Wind _ Direction p.*Y 1197A gmclD
- lD 030 T' M r.
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