ML20004C762

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Submits Conceptual Design Info in Response to to All Licensees Re post-TMI Requirements for Emergency Operations Facility
ML20004C762
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/01/1981
From: Lundvall A
BALTIMORE GAS & ELECTRIC CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
TASK-3.A.1.2, TASK-TM NUDOCS 8106050190
Download: ML20004C762 (13)
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A fps'h BALTIMORE T4 4'

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ARTHUR C. LUNDVALL. JR.

Vict PREssDENT 5-June 1,1981 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Mr. Darrell G. Eisenhut, Director Division of Licensing

Subject:

Calvert Cliffs Nuclear Power Plant Unit No.1 & 2, Docket No. 50-317 & 50-318 Emergency Response Facilities Conceptual Design

Reference:

NRC letter dated 2-13-81 from D. G. Eisenhut to All Licensees, Post-TMI Requirements for the Emergency Operations Facility.

Gentlemen:

The referenced letter provided clarification for TMI Action Plan item III.A.I.2, specif ying that we provide conceptual design informa+ ion for the emergency response f acilities by June 1,1981 including the following:

.l (1) Tatk functians of the individuals required to report to the TSC and EOF upon activation and for each emergency class; and (2)

Descrir"os of TSC instrumentation, instrument quality, instrument accuracy a.nd reliability.

(3)

Descriptions of TSC power supply sys+ ems, power supply quality, reliability and availability, and consequences of power supply interruption.

(4)

Descriptions of the design of the TSC data display systems, plant records and data available and record management systems.

(5) Descriptions of the esta transmission system to be installed between the TSC and control room (6)

Description of data to be provided to the EOF.

8186050190

  • (June 1, 1981)

The following are our responses to the above items:

~

(1)

See Attachment A.

(2)

TSC instrumentation consists of existing plant process instrumentation loops and loop power supplies frc n which isolating transmitters derive the respective analog signals to be fed to a data acquisition and display system which has read-outs in the TSC. Where practical and possible, existing safety-related loops are used as the signal source. This helps to ensure high instrumentation quality, availability, and reliability. The instrumentation read-outs in the TSC will have an error of less than 1 75% of process 0

range. Attachment B lists the TSC inputs.

(3)

The TSC power supplies are de. scribed below by function:

(a)

Heat, ventila+ ion and air conditioning system (HVAC)- a portion of the Controll'oom H"AC system was previously ured to landle the area now occupied by the Tech Support Center. This system was supplemented by a 10 ton chiller & 3 fan coil units all of which are powered from a motor control center that will be picked up by a diesel generator within about 50 minutes after a loss of offsite power.

(b) Lighting - The lighting in TSC is powered from a panel that is picked up by a diesel generator in the event of loss of offsite power. In addition the TSC has emergency lighting that is powered from a self contained uninterruptable po-supply providing about 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> battery backup.

(c)

Computer Equipment - All essential computer equipment necessary for the continuous monitoring & recording of required plant parameters are powered from an uninterruptable power supply (UPS) providing about a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> battery backup. In the event of a UPS failure, essential computer loads will be automatically transferred to an alternate power source.

(4)

See Attachment C.

(5) See Attachn ent C (6)

See Attachment D.

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If you require any further information at this time, please do not hesitate to call.

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Sincerely, l

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3. A. Biddison, Esquire G. F. Trowbridge, Esquire Mr. E. L. Conner, 3r.

Mr. R. E. Architzel

Attachment A TASK FUNCTIONS TO BE PERFORMED AT THE EMERGENCY RESPONSE FACILITIES EMERGENCY CLASS FUNCTION ALERT SITE

  • GENERAL
  • Emergency Response Command and Coordination TSC EOF EOF Radiological Assessment

- Onsite Conditions TSC TSC TSC

- Offsite Conditions TSC EOF EOF Accident Assessment - Plant Operations TSC TSC TSC Accident Mitigation TSC TSC TSC Emergency Classification TSC EOF EOF Emergency Notification and Communication 1

TSC EOF EOF Initiation of Onsite Pr(tective Actions TSC TSC TSC Recommendation of Offsite Protective Actions TSC EOF EOF Radiation Exposure Control (Onsite)

TSC TSC TSC Re-entry TSC EOF EOF Personnel Accountability TSC EOF EOF Analysis of Mechanical, Electrical & Instrument Control Problems TSC TSC TSC Core Protection TSC TSC TSC Offsite Engineering Support Related to Safety Analysis, N/A EOF EOF Environmental Monitoring, Licensing, and Plant Modifications I

Offsite Support for Mechanical Maintenance, Construction and N/A EOF EOF Procurement Offsite Administrative Support Related to Offier Supplies, N/A EOF EOF Food Service, Clerical Support, Housing and Com..unication Services

  • Task Functions will be performed at the EOF subsequent to its activation. Activation will be in accordance with NUREG-065t,

Attachment B UNIT SYSTEM PROCESS PARAMETER ~

l 2

COMON CONTAINMENT Contalnment 11 Pressure indication X

Containment Dome Temp X

X Con t a i nnen t 21 Pressure Indication X

Hydrogen Concentration X

X Containment Sump Water-Level X

X EE.RGENCY HPSI Flow to Loop IIA X-CORE COOLING

" Loop llB X

x

" Loop 12A#

X

" Loop 12B X

LPSI Flow to Loop 11A X

" Loop llB X

" Loop 12A X

" Loop 12B X

Containment Spray Header 11 Flow X

12 Flow X

LPSI Flow-Control X

X HPSI Flow to Loop 21B X

" Loop 21A X

" Loop 22B X

" Loop 22A X

LPSI Flow to Loop 21B X

" Loop 21A X

" Loop 22B X

" Loop 22A X

Containment Spray Header 21 Flow-X 22 Flow X

Charging Pumps Discharge Flow X

X Salt Water Pumps Discharge Hender Pressure X

X Salt Water Pumps Pressure X

X Component Cooling Pump 11 Discharge Pressure X

Component Cooling Pump 12 Discharge Pressure X

Shutdown Heat-Exchanger 11 Outlet Temp.

X Shutdown :-ieat-Exchanger 12 Outlet Temp.

X l

Refuel Water Tank 11 Level X

Service Water Header 11 Pressure X

Component Cooling Pump 21 Discharge Pressure X

Component Cooling Pump 22 Discharge Pressure X

Shutdown Heat-Exchanger 21 Outlet Temp.

X Shutdown Heat-Exchanger 22 Outlet Temp.

X Ref uel Water Tar.k 21 Level X

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Page 2 UNIT SYSTEM PROCESS PARAMETER 1

2 COMW3N Service Water Header 21 Pressure X

FEEDWATER Aux. Feedwater Flow Steam Generator

& MAKE-UP 11 X

Aux. Feedwater Flow Steam Generator 12 X

Condensate Storage Tank 12~ Level X

Aux. Feedwater Flow Steam Generator 21

^X Aux. Feedwater Flow Steam Generator 22 X

Feedwater Flow to Steam Generator 11 X

12 X

21 X

22 X

Condensate Storage Tank 11 Level X

12 Level X

MAIN STEAM Steam Generator Level 11 X

12 X

Steam Generator 11 Pressure X

12 Pressure X

Steam Generator Level 21 X

21 X-21 Pressure X

22 Pressure X

NUCLEAR

% Power (INTERMEDIATE)

X X

INSTRGiEN' RATION Q-Power X

X Thermal Power X

X

% Power Source Range X

X In-Core Flux Detectors X

X in-Core Thermocouples X

X RADIATION Waste Processing Area Radiation NONITORING Monitor X

X Liquid Waste Discharge Radiation X

Containment High Range (East)

X X

(West)

X X

Noble Gas Main Vent Low Range X

X Mid X

X High X

X Main Vent Flow X

X Condensate Vacuum Pump Discharge Radiation X

X Condensate Vacuum Pump Flow Rate X

X REACTOR RCS FIow Loop 11B X

COOLANT Loop 12B X

SYSTEM Subcooled Margin Loop 11 X

Subcooled Margin Loop 12 X

Pressurizer Level Hot X

X Cold X

X Pressure X

X RCS Hot Leg Temp Loop 11 X

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Page 3 UNIT SYSTEM PROCESS PARAMETER 1

2 COM ON RCS-HOT LEG TEMP. Loop 12 X

RCS Cold Leg Temp Loop llA X

" Loop llB X

" Loop 12A X

RCS Flow Loop 21B X

Loop 22B X

Subcooled Margin Loop.21 X

Loop 22 X

RCS Hot-Leg Temp Loop 21 X

Loop 22 X

RCS Cold Leg Temp Loop 21A X

Loop 21B X

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" Loop 22A X

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Attachment C The TSC Data Acquisitior. and Display System (DADS), Figure C-1 is being implemented to address the requirements for a TSC as described in NUREG 0578 and NUREG-0696. The system will" tap"into existing process loops and direct this information to the TSC computer which will process this information for the displaying of real time and historical data.

The TSC DADS will support a minimum of three (3) accident assessment " work stations" in addition to the official accident assessment / logging work station. The three work stations will each consist of:

A CRT/ keyboard terminal for accessing the data base; a.

b.

A three pen trend recorder; and, c.

A medium speed line printer.

Via the work station consoles, one is able to access any of the data being monitored by the system and to direct the displaying of this data on its CRT, its line printer, or its trend recorder.

The system will ultimately be able to support multiple data links with off-site terminals.

The plant design documents will be available.

Communications in the TSC are provided by two page systems, a sound power system, a dedicated phone to the NRC, three standard phone lines and several other dedicated telephone lines..

The TSC conforms with the habitability requirements of NUREG 0578 and NUREG 0696. The structure itself is part of the existing Seismic Class I Auxiliary Building, and the air handling system is part of the Control Room air handling system. Radiation monitoring and alarm equipment for the TSC will be provided. The TSC location and arrangement are shown in Figures C-2,-3 and -4.

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Attachment D The Emergency Operations Facility (EOF) for the Calvert Cliffs Nuclear Power Plant will be located approximately 12 miles Northwest of the plant with a driving time of 20-25 minutes. The building will be a ne3v structure with no special radiation shielding and a conventional ventilation system.

Figure D-1 shows the preliminary functionallayout for the EOF. It is expected that the relative layot* and location of various functional areas will change as the floor plan is finalized. The. k functions for the EOF are listed in Attachment A.'

The power supply for the EOF will be an uninterruptable power supply rated at approximately 15 KVA. The size, communications, instrumentation and data ditplays for the EOF will be censistent with the requirements of NUREG-0696 and -0654 and will adequately support the monitoring of all radiologicalincidents at Calvert Cliffs Nuclear Power Plant which require the activation of the EOF. Inasmuch as the site location of the EOF has just been approved by Baltimore Gas and Electric Company, we are unable to provide any greater design detail at this time.

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F reliminary Concept of Offnite Dr.ergency Opern_ti_on Facility ( EOF)

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