U-600083, Forwards Addl Accident Monitoring Instrumentation,Per NUREG-0737,TMI Item II.F.1.Info Complete & Adequate to Provide Confirmation That TMI Item & SER Confirmatory Issue 21 Implemented
| ML20126C921 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 06/11/1985 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM U-600083, NUDOCS 8506140576 | |
| Download: ML20126C921 (45) | |
Text
_ -_
U-600083 L30-85 (06-11 )-6 1A.120
/LL/NOIS POWER OOMPANY CLINTON POWER STATION, P.O. BOX 678, CLINTON, ILLINOIS 61727 June 11, 1985 2
Docket No. 50-461 Director of Nuclear Reactor Regulation Attn: Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Clinton Power Station, Unit #1 Additional Accident Monitoring Instrumentation NUREG-0737, TMI Action Plan Item II.F.1
Dear Mr. Butler:
Item II.F.1 of TMI Action Plan NUREG-0737 contains six requirements for accident monitoring instrumentation:
II.F.1.1 Noble Gas Effluent Radiological Monitor II.F.1.2 Sampling and Analysis of Plant Effluents II.F.1.3 Containment High-Range Radiation Monitor II.F.1.4 Containment Pressure Monitor II.F.1.5 Containment Water Level Monitor II.F.1.6 Containment Hydrogen Monitor The NRC Safety Evaluation Report for Clinton Power Station (NUREG-0853) described the NRC Staff review of this additional instrumentation in Sections 6.2.7 (for II.F.1.4 through II.F.1.6);
11.5.1 (for II.F.1.1 and II.F.1.2); and 12.3.4.1 (for II.F.1.3) .
Additional design details were requested by the NRC Staff to completely close out this TMI action item. This action item was designated Confirmatory Issue No. 21.
Previous Illinois Power submittals on design details have resolved Items II.F.1.3 through II.F.1.6 as described in Supplement No. 4 to the Safety Evaluation Report. The CPS Final Safety Analysis Report (FSAR) is being amended to incorporate design details for the remaining Items II.F.1.1 and II.F.1.2. An advance copy of changes in FSAR Sections 7.6, 11.5, and Appendix D in Amendment 34 is attached for your review.
8506140576 850611 DR ADOCK 050 4jl i
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r-U-600083 L30-85 (06-11)-6 1A.120 Illinois Power considers the information contained herein complete and adequate to provide confirmation that the requirements of TMI Action Plan Item II.F.1 and SER Confirmatory Issue No. 21 have been implemented.
Please contact me if you have any further questions on this matter.
Sincerely yours, M ' !
F. A. S ange erg !
Director - Nuclear L). censing and Configuration Nuclear Station Engineering TLR/lah Attachment cc: B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety
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Attachm:nt CPS-FSAR AMENDMENT 34 JULY 1985 7.6.1.2.5 Control Room Air Intakes Radiation Monitorine Subsystem The purpose of this subsystem is to indicate when excessive amounts of radioactive material exist in the control room minimum air intake ducts and to initiate appropriate action to minimize the dose to the control room inhabitants. The subsystem consists of four channels of radiation monitors and is part of the integrated radiation monitor system described in Subsection 7.7.1.19.
7.6.1.2.5.2 Power Sources The two channels receive power from one safety-related divisional bus, and the other two channels receive power from the other safety-related divisional bus.
7.6.1.2.5.3 Eculement Desian The equipment design of this subsystem is as described in Subsection 7.6.1.2.2.3 with the exception that the actuated devices are as follows:
- 1. The trip output will start the applicable makeup air filter train and isolate the air intake as described in Subsection 7.3.1.
7.6.1.2.5.4 Environmental Considerations The environmental considerations of this subsystem are as described in Subsection 7.6.1.2.2.4.
7.6.1.2.5.5 ocerational Considerations The operational considerations of this subsystem are as described in Subsection 7.6.1.2.2.5.
7.6.1.2.6 Standby Gas Treatment System (SGTS) Exhaust High Range Radiation Monitoring System - Instrumentation and Controls .
7.6.1.2.6.1 System Identification In thir subsection, the instrumentation and controls associated with the safety-related SGTS exhaust high range radiation monitoring system are discussed. (This system was precured and designed as a safety-related system in order to provide a moniter which meets and/or exceeds Category 2 requirements of 1:cgulatory Guide 1.97. This system, however, is not redun-dant and is not designed to mitigate the consecuences of an 7.6-12
CPS-FSAR AMENDMENT 34 JULY 1985 accident.) This system provides the capability for continuous accident range noble gas monitoring and sampling of SGTS effluent for postaccident releases of radioactive iodines and particulates..
The SGTS. exhaust high range radiation monitoring system is comprised of the following subassemblies:
- a. SGTS Exhaust Isokinetic Sample Probe (CAE-PR009).
This probe is located in the 18-inch diameter common SGTS exhaust line at approximate elevation 779 feet, and samples the discharge of the standby gas treatment systems (Division 1 and/or 2).
- b. Grab Sample Pallet (GSP-1; OPROSS) . This assembly-is located in the diesel generator building at elevation 762 feet, approximately 20 feet from the SGTS exhaust line, and r'eceives the sample from the isokinetic probe. The functions of this assembly are to:
- 1. Collect postaccident particulate and iodine samples at approximately the rate of 1/60 of >
the normal sample flow rate;
- 2. Allow safe removal of the collected particulate and iodine samples for transport of the laboratory for analysis; and 3., Purge the system of radioactive gases. Ambient air is drawn through the system via a valving arrangement on the grab sample pallet and
. the sample pump and is discharged to the SGTS exhaust line.
- c. Bulk Filter Assembly (BFA-1; OPR06S) . The bulk filter assembly is located in the diesel generator building at elevation 762 feet approximately 6 feet from the grab sample pallet. The function of this filter is to remove radioactive particu-lates and iodines from the sample, so the' sample is entirely gaseous in composition before it enters the noble gas pallet described below. The bulk filter assembly is housed in a lead onclosure to limit personnel exposures from the deposited radioactive particulates and iodines.
- d. Sample Cooler (OPR13A). The sample cooler is located in the diesel generator building at elevation 762 feet 0 inches near the bulk filter assembly.
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CPS-FSAR AMENDMENT 34 JULY 1985 Sample effluent from the bulk filter assembly passes through the cooler prior to entering the noble gas pallet. Its function is to reduce the sample temperature from 180' F to approximately 120* F.
- e. Noble Gas Pallet (NGP-1; OPR07S). This assembly is located in the diesel generator building at elevation 762 feet, approximately 20 feet from the SGTS exhaust line, and accepts the sample from the cooler discharge. The functions of this assembly are to:
- 1. Move the sample through the system via the sample pump;
- 2. Monitor the noble gas concentrations of the "
sample; and
- 3. Determine when a low sample flow condition -
exists and provide a corresponding alarm.
After it leaves the noble gas pallet, the sample is returned to the SGTS exhaust line downstream of the isokinetic probe.
i f. Data Acquisition Module (DAM- 4 ; OPROSS). This assembly is located in the diesel generator building at elevation 762 feet, approximately 25 feet from the sampling assemblies described above. The '
radiation detectors on the grab sample pallet and noble gas pallet, through their interfacing ;
electronics are connected to the microprocessor in the data acquisition module. The module allows '
for communication between the field units and the radiation monitoring control ter=inals in the main control room and radiation protection office via a redundant twisted pair transmission line.
- g. Communication Line Isolator (CLI-1; OUT-PR008A and B). Redundant communication line isolators :
are located in the diesel generator building at elevation 762 feet, directly above the data acquisition module. Their function is to provide a d-c isolated interface between the safety-related data acquisition module and the'non-safety related transmission line and radiation monitoring control terminals.
One CLI-1 is furnished for each of two redundant transmission lines.
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( CPS-FSAR AMENDMENT 34 JULY 1985 The SGTS exhaust high range radiation monitoring system is a part of the integrated radiation monitor system described
[ in Subsection 7.7.1.19.
7.6.1.2.6.2 Power Sources The Class lE electrical system supplies 120 Vac power to the
! SGTS exhaust high range radiation monitoring system. The data acquisition module is powered from a Division 1 120/208 Vac distribution panel located in a control building motor control center. This same power source is distributed to both the grab sample and noble gas pallets via interconnecting wiring to the data acquisition module.
7.6.1.2.6.3 Equipment Design 7.6.1.2.6.3.1 Sample Flow Path Description The sample collected by the probe in the SGTS exhaust line passes _into the GSP-1 through an isolation valve. The length of sample line between the probe and grab sample pallet is minimized to maintain an acceptable system response time.
A small portion is extracted by an extraction nozzle placed in the' flow path. This sample passes through an isolation valve and into-the sample assembly, SA-16, which contains the particulate and iodine filters surrounded by 2 inches of lead. The sample then passes through a flow =eter and an isolation valve and then is recombined with the main sample flow.
After exiting the grab sample pallet, the sample flows through the bulk filter assembly. The filter removes radioactive particulates and iodines from the sample.
Once. leaving the bulk filter assembly, the sample is drawn through the tube side of the sample cooler and then through the noble gas pallet by the diaphragm pump. The pu=p exhausts the sample through a flowmeter and into the noble gas sampler assemblies-SA-14_and SA-15. On leaving the sampler assemblies, the sample is then exhausted back into the SGTS exhaust line above the sample extraction point.
The sample lines between the probe and grab sample pallet and between the grab sample pallet and the bulk filter assembly are heat traced (the sample lines are maintained at 180* F during both normal and postaccident conditions) to prevent sample condensation.
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i CPS-FSAR AME OME!;T 34 JULY 1985 7.6.1.2.6.3.2 circuit Description The circuit description of the applicablo SGTS exhaust high i- range radiation monitoring system subassemblies are described below:
- 1. Grab Sample Pallet '
The grab sample pallet particulate / iodine sample assembly (SA-16) is furnished with an energy com-pensated G-M detector which can be utilized to indicate the relative amount of radiation present
- in the filters. The G-M tube is interfaced with the data handling system through a device which generates the high voltage to operate the detector and.provides low voltage regulation to operate the pulse amplifier and the transmission line driver. This G-M tube assembly is not. furnished with a check source drive.
~
- 2. Noble Gas Pallet
, The noble gas pallet is furnished with two noble gas sampler assemblies, SA-14 and SA-10. The SA-14 is an intermediate level detector assembly with a chamber volume of 2.7 liters and an energy compensated G-M tube at its center. The sample chamber is surrounded by 5 inches of lead shielding.
The SA-15, a high range detector, utilizes a section of 1-inch outside diameter tubing which is viewed by an energy compensated G-M tube to make its measurement. This. sampler also employs 5 inches of lead shielding. G-M tube is placed in the SA-15 lead shield and reacts to background radiation
. in a similar manner to the sample detectors.
Its reading can be subtracted from that of the sample detectors, thus minimizing the effects 4
of fluctuating background.
These G-M tubes are interfaced with the data handling system through a device which generates the high voltage to operate the detectors and provides
! low voltage regulation to operate the pulse a=pli-fiers and the transmission line drivers.
Check source assemblies are provided to permit x evaluation of the intermediate and high range noble gas channel operation.
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CPS-FSAR AMENDMENT 34
, JULY 1985
- 3. Data Acquisition Module The G-M tubes and interface boxes (high voltage supply and pulse amplifier) described above are input to the detector input-output boards of the microcomputer located in the data acquisition module. These signals are converted to count rate by the microcomputer, which then performs all mathematical calculations and control functions.
Four active channels are recognized by the data acquisition module as follows:
Channel 1 Particulate and Iodine Filter Gamma Activity (SA-16)
Channel 2 Noble Gas Channel Background Subtraction (SA-15)
Channel 3 High Range Noble Gas (SA-15)
Channel 4 Intermediate Range Noble Gas (SA-14)
The data acquisition module provides the following features and capabilities:
- a. Converts the detector's signal to a digital signal;
- b. Converts the digital signal to engineering units;
- c. Local visual warning lights for high radiation alarm (red beacon) and fail condition (blue beacon);
- d. Local controls for the following functions:
Sample pump on/off, Initiate check source, .
Alarm acknowledge, and Initiate purge;
- e. Local digital display with values reading out in CPM or engineering units (value in 7.6-12e
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CPS-FSAR AMENDMENT 34 JULY 1985 engineering units obtained by proper selection of calibration constant). Six light-emitting diode lamps on the digital display that indicate the status of the channel being displayed as follows:
Normal Operation (green)
Maintenance (clear red)
Fail (yellow)
Trend Alarm (yellow)
Alert Alarm (yellow)
High Alarm (red)
In normal operation only one of the status ~
1 amps will be lit at any time;
- f. Transmission of radiation data, alarm infor-mation, and monitor status to the redundant central control terminals;
- g. Retention of data upon loss of Class lE 120 Vac power. A battery back-up system furnished with the data acquisition module has the capacity to supply the microprocessor system loads for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The purpose of the battery system is to retain data collected in the microcomputer memory upon loss of normal a-c power. The battery system does not have the capacity to operate the sample pump; 1
- h. Condensing, averaging, and storage of data. l
- 4. Communication Line Isolator (CLI)
The isolator provides a d-c isolated interface between the safety-related data acquisition module and the non-safety-related transmission line and radiation monitoring control terminals. Redundant isolators are provided to interface with the redun-dant transmission line.
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CPS-FSAR AMENDMENT 34 JULY 1985 In the transmit mode, the CLI optical isolator is driven by the data acquisition module and the switched output of the optical isolator in turn drives the twisted pair transmission line. In the receive mode, high power pulses are received by the current regulator in the CLI from the twisted pair transmission line. The output of the current regulator in turn drives the data acquisition module.
7.6.1.2.6.3.3 Logic and Secuencing The SGTS exhaust high range radiation monitoring system data -
acquisition system microprocessor provides the logic to initiate the various functions of the system, 7.6.1.2.6.3.4 Bypasses and Interlocks The following interlocks are provided for the SGTS exhaust high range radiation monitoring system:
- 1. Transfer from standby mode. The data acquisition module is provided with remote startup capabilities.
During normal plant operations, the SGTS exhaust high range radiation monitoring system will be placed in the standby mode. This mode of operation
. allows the system to be powered up and ready for operation while maintaining the sample pump in the n.onoperating condition (samples will not be drawn through the system in the standby mode).
The system which is in a standby mode can be caused to start up (activate sample pump) by closure of a contact external to the data acquisition module. Once in the operating mode, the system will continue to operate in this fashion until it is placed back in the standby mode through either of the redundant central control terminals.
The SGTS exhaust high range radiation monitoring system is transferred from the standby mode to the operating mode by the same signal that initiates automatic startup of the Division 1 standby gas treatment system. Testing of the Division 1 stand-by gas treatment system will not cause the standby transfer to occur.
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CPS-FSAR AMEND!!ENT 34 JULi 1985 The operator has the ability through either of the redundant central control terminals to transfer the SGTS exhaust high range radiation monitoring system from standby to normal operation or vice versa. Once the system is placed in the normal operating mode (either by external contact or operator action) the monitor will continue to run until the operator terminates it.
- 2. SGTS Exhaust High Range Radiation Monitor Cooler Shutdown Service Water Valve.
Shutdown service water is the cooling water source for the SGTS exhaust high range radiation monitor cooler. A valve is provided in the cooling water discharge piping from the cooler to allow cooling water flow during postaccident conditions. The valve requ' ires air to close and its position is controlled by two 3-way solenoid valves (one valve is powered from a Division 1 power source and the second is powered from a Division 2 source).
The valves are interlocked with the standby gas treatment system primary fan motor control center (primary f an A with the Division 1 solenoid valve; primary fan B with the Division 2 solenoid valve).
When either of the standby gas treatment system primary fans start, the respective solenoid valve will deenergize, vent the valve diaphragm, and open-the valve allowing cooling water flow. Loss of air or loss of power to either of the solenoid valvec will open the cooling water valve.
7.6.1.2.6.3.5 Redundancy and Diversity Not applicable to this subsystem.
7.6.1.2.6.3.6 Actuated Devices Actuation of devices external to this subsystem is not appli-cable.
7.6'l.2.6.3.7
. Seoaration The SGTS exhaust high range radiation monitor subsystem is electrically assigned to the Division 1 segregation code.
This subsystem is electrically isolated from the non safety-related radiation monitoring system transmission line by the communication line isolator.
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CPS-FSAR AMENDMENT 34 JULY 1985 7.6.1.2.6.3.8 Testability The testability of this subsystem is as described in Subsection 7.6.1.2.2.3.7.
7.6.1.2.6.3.9 Environmental Considerations All components of the SGTS exhaust high range radiation monitoring system are designed to be operable during normal and post-accident environments. The system is environmentally qualified in cccordance~with IEEE-323, and seismically qualified in accor-dance with IEEE-344.
7.6.1.2.6.4 operational considerations 7.6.1.2.6.4.1 General Information Each channel communicates with two radiation monitoring system central control terminals - one in the main control room and the other in the radiation protection office. In addition, the data acquisition module is equipped with a portable terminal interface which permits communication between the system and a portable terminal. This interface isolates the system from the-transmission line while the portable terminal is connected.
The portable terminal is identical in function to that of the central control terminals except CRT display and mass data storage are not provided. All operator actions require the use of a control terminal. Local controls, however, are provided on the data acquisition module to allow alarm acknow-ledgement, to initiate check, source and purge, and to allow control of the sample pump.
Each channel's safety-related functions are designed to operate without the use of any of the non-safety-related portions of the radiation monitoring system.
The operational considerations of the terminals are described in Subsection 7.7.1.9.5.
7.6.1.2.6.4.2 Reactor Ooerator Information Reactor operator information is provided by the main control l room central control terminal described in Subsection 7.7.1.9.5. !
7.6.1.2.6.4.3 Setpoints i
Setpoints will be determined based upon the emergency action l plan and action levels. l l
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CPS-FSAR AMEND. MENT 34 JULY 1985 7.6.1.2.7 Common Station HVAC Exhaust High Range Radiation Monitoring System - Instrumentation and Controls 1.6.1.2.7.1 System Identification In this subsection, the instrumentation and controls associated with the safety-related HVAC exhaust high range radiation monitoring system are discussed. (This system was procured and designed as a safety-related system in order to provide
-a monitor which meets and/or exceeds. Category 2 requirements of Regulatory Guide 1.97. This system, however, is not redun-dant and is not designed to mitigate the consequences of an accident.)
This system provides the capability for continuous accident range noble gas monitoring and sampling of HVAC stack effluent for postaccident releases of radioactive iodines and particu-lates. The HVAC exhaust high range radiation monitoring system is comprised of the following subassemblies which are identical in design to those described in Subsection 7.6.1.2.6.1.:
- a. HVAC Exhaust Isokinetic Sample Probe (OAE-PR013).
This probe is located in the common station HVAC vent stack at approximate elevation 896 feet and samples the HVAC discharge downstream of all venti-lation inputs to the stack. This probe consists of an array of samplers configured to take a repre-sentative sample of the rectangular duct.
- b. Grab Sample Pallet (GSP-1; OPR095). This assembly i is located in the diesel generator building at elevation 762 feet, approximately 15 feet from the HVAC vent stack, and receives the sample from l the isokinetic probe. The equipment design of i this subsystem is as described in Subsection 7.6.1.2.6.l(b).
- c. Bulk Filter Assembly (BFA-1; OPRlCS) . The bulk filter assembly is located in the diesel generator building at elevation 762 feet, approximately 4 feet from the grab sample pallet. The equip-l ment design of this subsystem is as described in Subsection 7.6.1.2.6 l(c).
- d. A sample cooler is not required nor furnished i for this system.
l s e. Noble' Gas Pallet (NGP-1; OPRllS). This assembly l is located in the diesel generator building at l elevation 762 feet, approximately 10 feet from 7.6-12j l
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CPS-FSAR AMENDMENT 34 JULY 1985 the HVAC vent. stack, and accepts the sample from the bulk filter assembly. The sample is returned to the HVAC vent stack.at approximate elevation 775 feet which is upstream of the isokinetic probe (the volume of sample returned is low in proportion to the volume of effluent discharged from the vent stack). The equipment designed of this sub-system is as described in Subsection 7.6.1.2.6.l(e) .
- f. Data Acquisition Module (DAM- 4 ; OPR12S). This assembly.i:s located in the diesel generator building at elevation 762 feet approximately 25 feet from the sampling subassemblies described above. The
, equipment design of this subsystem is as described in' Subsection 7.6.1.2.6.l(f).
- g. Communication Line Isolator (CLI-1; OUT-PRO 12A and B). Redundant communication line isolators are located in the diesel generator building at elevation 762 feet, directly above the data acquisition module. The equipment design of this subsystem-is as described in Subsection 7.6.1.2.6.l(g) .
The HVAC. exhaust high range radiation monitoring system is a part_of the integrated radiation monitoring syste: described in Subsection 7.7.1.19.
7.6.1.2.7.2 Power Sources
- The-class lE electrical system supplies 120 Vac power to the HVAC exhaust high range radiation monitoring system. The data acquisition module is powered from a Division 1 120/208 vac distribution panel located in a control building motor -
control center. This same power source is distributed to both the grab sample and noble gas pallets via interconnecting wiring to the data acquisition module.
7.6.1.2.7.3 Equipment Design 7.6.l'.2.7.3.1 Sample Flow Path Description
~ The system flow path is similar to that described for the SGTS exhaust high range radiation monitoring syste: (Subsection 7.6.1.2.6.3.1) except that the sample is collected by the probe in the common station EVAC' vent stack and a sample cooler is not required to cool the sample prior to it entering the noble gas pallet.
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t CPS-FSAR AMENOMENT 34 JULY 1985
.The sample lines between the probe and grab sample pallet (only the portion between the point where .the sample line exits the interior of the HVAC vent stack and the grab sample pallet) and between the grab sample pallet and the bulk filter assembly are heat traced to prevent sample condensatien.
- The sample lines are. maintained at 130* 1 during both normal and'postaccident conditions. ,
7.6.l'.'2.7.3.2 Circuit Description The circuit description of the applicable HVAC exhaust.high range radiation monitoring system assemblies is identical to that described in Subsection 7.6.1.2.6.3.2 for the SGTS exhaust high range ra'diation monitoring system.
7.6.1.2.7.3.3 Logic and Sequencing The HVAC exhaust high range radiation monitoring system data
. acquisition system microprocessor provides the logic to initiate the various functions of the system. ,
7.6.1.2.7.3.4 Bypasses and Interlocks The following interlocks are provided for the HVAC exhaust high range radiation monitoring system:
- 1. Transfer from standby mode. The data acquisition module is provided with remote startup capabilities.
During normal plant operations, the HVAC exhaust high range radiation monitoring system will be placed in the standby mode. This mode of operation allows the system to be powered up and ready for operation while maintaining the sample pump in the nonoperating condition (samples will not be drawn through the system in-the standby mode).
The system which is in a standby mode can be caused to start up (activate sample pump) by closure of a contact external to.the data acquisition module. Once in the operating mode, the system will continue to operate in this fashion until it is placed back in the standby mode through either of the redundant central control terminals.
The HVAC exhaust high range radiation monitoring system is transferred from the standby mode to the operating mode by either of the two non-safety-s related normal range HVAC exhaust radiation monitoring
. systems (OPR0lS and OPR02S). An alarm relay pro-vided at each of the normal range monitors will 7.6-121
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- l CPS-FSAR' AMENDMENT 34 JULY 1985 deenergize, closing a contact (which transfers the HVAC exhaust high range radiation monitoring-system from standby to normal operation) under the following conditions occurring at the normal
-range monitor:
- a. External failure (loss of sample flow)
- b. Low count rate failure
- c. High count rate failure
- d. High radiation alarm e'. Check source activated
- f. Loss of a-c power. (Although a battery back-up system is provided with the normal tange monitor data acquisition module,. loss of a-c power will stop the sample pump. The battery system is provided only to retain collected data in the microcomputer memory upon loss of normal a-c power. This sequence will deener-gize the alarm relay due to loss of sample flow).
The operator has the ability through either of the redundant central control terminals to transfer the HVAC exhaust high range radiation monitoring system from standby to normal operation or vice versa. Once the system is placed in the normal operating mode'(either by external contact or operator action) the monitor will continue to run until the operator terminates it.
7.6.1.2.7.3.5 Redundancy and Diversity Not applicable to this subsystem.
7.6.1.2.7.3.6 Actuated Devices .
Actuation of devices external to this subsystem is not appli-cable.
7.6.'1.2.7.3.7 Separation
-The'HVAC exhaust high range radiation monitor subsystem is electrically assigned to the Divicion 1 segregation code.
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CPS-FSAR AMENDMENT 34 JULY 1985 This subsystem is electrically isolated from the non-safety-related radiation monitoring system transmission line by the communication line isolator.
7.6.1.2.7.3.8 Testability The testability of this subsystem is as described in Subsection 7.6.1.2.2.3.7.
7.6.1.2.7.3.9 Environmental Considerations All components of the HVAC exhaust high range radiation monitoring
-system are designed to be operable during normal and post-accident environments. The system is environmentally qualified in accordance with IEEE-323, and seismically qualified in accordance with IEEE-323.
7.6.1.2.7.4 operational Considerations The operational considerations of this subsystem are as described in Subsection 7.6.1.2.6.4. .
7.6.1.3 Hich Pressure / Low Pressure Systems Interlock Protection System 7.6.1.3.1 Function Identification The low pressure systems which interface with the reactor coolant pressure boundary and the instrumentation which protects them from overpressurization are discussed in this section.
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CPS-FSAR A'E::DME:iT 34 JULY 1985
- 1. containment building exhaust
- 2. containment building fuel transfer vent plenum; and
- 3. fuel building ventilation exhaust.
o
- b. To monitor the standby gas treatment system ex-haust downstream from the filter trains, and pro-vide operating personnel with quantitative know-ledge of particulate, iodine, and noble gas radio-activity levels being released through continuous monitoring of noble gases and continuous sampling of iodines and particulates.
- c. To monitor the air in the vicinity of the control room air intake ducts; and initiate the makeup air filter train upon high radioactivity level.
I (After this initial action shutdown the operator i selects which intake will be used, based partially
, on the readings of these monitors.)
- d. To monitor the common station HVAC vent downstream of all' ventilation inputs, and provide operating personnel with quantitative knowledge of noble gas, radioactivity levels for postaccident re-leases.
The process sampling system can be used to complement the measurements made by the PRM's as outlined in Subsection 9.3.2.
All the previously described means of radioactivity detection and determination are provided to satisfy the requirements of 10 CFR 20 and 10 CFR 50, Appendix A, and, in particular, General Design Criterion 64 which requires monitoring or sampling of all potential release pathways. The SGTS HVAC high range radiation monitors'are provided to satisfy the requirements of NUREG-0737 II.F.1, Attachments 1 and 2 and Regulatory Guide
- 1. 9 7. -
11.5.1.2 Design Criteria of the Process Radiation Monitoring System and Process Sampling System
.The design criteria that have been used for the process and effluent radiation monitoring and sampling system are:
- a. To enable.the station to comply fully with the measuring, evaluating, and reporting requirements 11.5-3
l I
i l
CPS-FSAR' AMENDMENT 34 JULY 1985 of Regulatory Guide 1.21. . This compliance is accomplished by continuously monitoring the pro-cesses and effluents which could be contaminated.
These potentially contaminated streams (see Sub-section 11.5.2 for more details) are sampled in accordance with Regulatory Guide 1.21 requirements (as a minimum) and laboratory analysis is done on the samples. This analysis enables isotopic identification and quantification of the radio-activity ih the process streams and effluents.
- b. To enable compliance with 10 CFR 20 and 10 CFR 50 requirements, both as to streams that require monitoring and as to required ranges and sensitivities.
Sensitivities (minimum detectable levels) have been chosen to be as far below 10 CFR 20, Appendix B, Table II levels as commercial wa 11.5-3a
_...__,r_.. , , = ___ , - _ _ , . - - , . . --- - - - -
CPS-FSAR AMENDMENT 34 JULY 1985 state-of-the-art reliability. allows. The ranges have been chosen to encompass the minimum detectable level and the level at.which alarm and/or control action should take place. Duct monitors have been provided ranges suitable for postulated accidents.
- c. To comply with all other applicable federal regulations and guidance, and with industry codes.
This compliance includes:
- 2. Regulatory Guide 1.22*,
- 3. Regulatory Guide 1.29*,
- 4. -Regulatory Guide 1.53*,
- 7. ANSI N]3.1-1969,
- 8. ANSI N13.2-1969,
- 9. ANSI N13.10-1974,
- 10. IEEE 279*,
- 11. IEEE 323*,
- 12. IEEE 338*,
- 13. IEEE 344*,
- 14. IEEE 379*, and
- 15. NUREG-0 737, Item II.F.1.
NOTE:* For nuclear safety-related monitors only.
- d. To be reliable. This reliability is accomplished by providing state-of-the-art detectors and solid-state -
circuitry.
- e. To assist in assuring safety of plant -personnel. The system is designed to detect increasing contamination in plant streams as early as possible so as to enable early correction. This early correction in turn will assist in making radiation doses to personnel ALARA.
In addition, the system is designed for safe and low i- maintenance operation (by design for sample stream j
conditions, by its panel design, and by choice of l
components).
11.5-4 l . . - . -
CPS-FSAR AMENDMENT 34 JULY 1985
- f. To have a suitable time response to radiological events. This is accomplished by providing ,a system with adequate (and widely adjustable) time response.
- g. To provide local alarms and/or indications at key points when a substantial increase in radiation / radioactivity would be of immediate concern to personnel in the area. This feature is provided by the process radiation monitoring system design (see Subsection 11.5.2 for details) .
- h. To provide digital hard copy records of radioactivity levels at a central location. Sample analysis results will be recorded, 11.5.2 System Descriotion 11.5.2.1 Systems Recuired for Safety Information on the subsystems described in Subsections 11.5.2.1.1 through 11.5.2.1.5 is presented in Table 11.5-1 and 11.5-2.
Information on the subsystems described in Subsections 11.5.2.1.6 and 11.5.2.1.7 is presented in Tables 11.5-1, 11.5-2 and 11.5-7.
Also refer to Figure 11.5-1.
11.5.2.1.1 Main Steamline Radiation Monitorine Svster (MSLRMS)
This system monitors the gamma radiation level external to the main steamlines. The normal radiation level is produced primarily by coolant activation gases plus smaller quantities of fission gases being transported with the steam. In the event of a gross release of fission products from the core, the monitoring system provides channel trip signals to the reactor protection system and containment and reactor vessel isolation control system (CRVICS) to initiate protective action. _
The system consists of four redundant instrument channels as shown on Figure 11.5-1. Each channel consists of a local detector (gamma-sensitive ion chamber) and a control room radia-tion monitor with an auxiliary trip unit. Power for channels !
A, B, C, and D is supplied from NSPS buses A, 3, C and D, respectively. Each channel is physically and electrically independent of the other channels.
The detectors are physically located near the main steamlines ,
just downstream of the outboard main steamline isolation valves l in the space between the primary containment and secondary j containment walls. The detectors are geometrically arranged so 1 that this system is capable of detecting significant increases in radiation level with any number of main steamlines in operation.
Each channel provides HI-HI and INOP logic signals and actuation.
If any two of the four channels give either a EI-HI or INOP trip signal, the reactor protection system will generate a scram signal and the nuclear steam supply shutoff system will shut the MSIV's.
11.5-5
. ._ .. m . _. . m .. _ _ _ .__ = ... _ _.... . . . _ _ . . . . . , _ . . . _ . . . . _ ....
CPS-FSAR AXE::DMENT 34 JULY 1985 11.5.2.1.5 Control Room Air Intake Radiation Monitors Four redundant gross gamma channels are provided to monitor the control room air intakes and control the ventilation system to limit the radiation dose to personnel in the control room under normal _and accident conditions. The location of these monitors in the Control Room HVAC system is shown on Figure 9.4-1, Sheet 1. '
Each channel consists of a GM tube detector.and local monitor.
Two detectors are mounted near each of the two separated in-takes to monitor the radiation from the cloud.
Whenever the level of radioactivity exceeds a preset level, as indicated in Table 11.5-1, the monitoring systen starts ~
one of the two standby makeup air filter trains.
i.
Power for two channels (A and C) is supplied from ESF bus A and for the other two channels (B and D) from ESE bus B.
- Channels A and C are physically and electrically independent 9
of Channels B and D. A one-out-of-four logic is provided.
A monitor failure provides the same input to the trip logic as high radiation.
111.5.2.1.6 Standbv Gas Treatment System (SGTS) Ex.aust High Range Radiation Monitoring System i
One accident range noble gas monitor is provided for continuous monitoring of SGTS effluent for noble gases and continuous sampling of iodines and particulates. The syste consists of two nonredundant instrument channels as shown in Tables 11.5-1 and 11.5-2. The operational monitor extracts sacples
+
through an isokinetic probe mounted in the exhaust stack.
1 The probe is designed and installed to meet the recuirements of ANSI N13.1.
The. monitor is an offline sampling type (consisting of four separate assemblies - two skid mounted) and is furnished with particulate and iodine filters to collect radioactivity for laboratory analysis and detectors to monitor for postaccident releases of noble gas radioactivity. _
Annunciators in the main-control room and radiation protection office and local visual alarms will actuate on noble gas channel ALERT or HIGH radicactivity or on monitor failure.
The system and sample return line to the SGTS exhaust stack-
-may be purged by local controls, controls in the main control room, or controls in the radiation protection office. Ambient air is drawn through the system by the sample pump and returned to the SGTS exhaust stack.
11.5-7
. . . . - . . . . _ - - . . . . . . - - . . . - . . - . . . . - . . . - . . . . . . - . - . - - . - - . ~ - . .
l CPS-FSAR AMENDMENT 34 JULY 1985 Operational checks and calibration are as described in Sub-section 11.5.2.2.1. Local grab sample capability is also provided with the system. For a more detailed description of this system, refer to Subsection 7.6.1.2.6.
11.5.2.1.7 Common Station HVAC Exhaust High-Range Radiation Monitoring System One accident range noble gas monitor is provided for contin-uous monitoring of HVAC stack effluent for noble gases and continuous sampling of iodines and particulates. The system consists cf two nonredundant instrument channels as shown in Tables 11.5-1 and 11.5-2. The operational monitor extracts samples through an isokinetic probe (sampling array configured to the rectangular duct) mounted in the stack downstream of
.all ventilation inputs to the stack. The probe is designed and installed to meet the requirements of ANSI N13.1.
The monitor is an offline sampling type (consisting of three separate assemblies - two skid mounted) and is furnished with particulate and iodine filters to collect radioactivity for laboratory analys~is and with detectors to monitor for post-accident releases of noble gas radioactivity.
Annunciators in the main control room and radiation protection office and local visual alarms will actuate on noble gas channel ALERT or HIGH radioactivity or on monitor failure.
Purging of the system is as described in Subsection 11.5.2.1.6 except the purging medium is returned to the HVAC vent stack.
Operational checks and calibration are as described in Sub-section 11.5.2.2.1.
Local grab sample capability is also provided with the system.
For a more detailed description of this system, refer to Sub-section 7.6.1.2.7.
11.5.2.2 Systems Reauired for Plant Oceration Information on these subsystems is presented in Tables 11.5-1 through 11.5-3 and shown on Figure 11.5-1.
Power for these subsystems is from 120-Vac nondivisional instru-mentation buses, except that the monitors described in Sub-section 11.5.2.2.10 are powered from 120-Vac convenience out-lets.
ll.5-7a
- ~ .
........_._.-..........._,~...__...s.~~......_ .._.........~...-~..u__.
CPS-FSAR AMENDMENT 34 JULY 1985 Sample lines and flow rates are chosen such that a high Reynolds number is obtained to reduce plateout. Plateout is further reduced by using long radius bends upstream from particulate and mud filters.
11.5.2.2.1 Pretreatment Air Ejector Off-Gas Radiation Monitor The main condenser pretreatment air ejector off-gas radiation monitor monitors the discharge of the steam jet air ejectors (SJAE) directly at the SJAE discharge or downstream from the off-gas recombiner and cooler condenser (prior to the charcoal adsorbers). This monitor measures the radioactivity in the noncondensible gases drawn from the condenser. The monitor can be used to evaluate the extent of failed fuel rods (s) and combined with the off-gas post treatment monitor, (Sub-
-section 11.5.2.2.2), the effectiveness of the charcoal adsorber(s) in the off-gas system may be determined.
The. monitor is an offline sampling type (skid mounted) with a GM tube detector provided for monitoring gross gamma radio-activity. The monitor is calibrated to determine noble gas concentration.
e.
ll.5-7b
_ _ _ _ . . . . _ . . . _ _ . _ . _ _ _ . _ . _ _ . _ . _ . . _ . . . . . a . _ . , . . . . . . . ~ , . _ . _ l CPS-FSAR AMENDMENT 34 JULY 1985
- a. verification of the performance of the charccal adsorbers, -
- b. verification that high stack activity is or is not coming from the off-gas system, and
- c. automatic off-gas system discharge valve closure to limit the discharge of radioactivity frcm the turbine cycle to the environment.
The monitors are offline sampling type (skid mounted) with detectors to measure particulate, iodine, and noble gas radioactivity.
An ALERT noble gas channel radiation trip will close the off-gas system charcoal absorber bypass valve (a fail closed valve) and a HIGH noble gas channel radiation trip will close the off-gas system discharge valve (a fail open valve). If both of the monitors fail, the discharge valve will automatically close.
Annunciators in the main control room and radiation protection office and local visual alarms will actuate on iodine, particulate, or noble gas channel ALERT or HIGH radioactivity or on monitor failure.
Purging, monitor operational checks, and calibration, are as described in Subsection 11.5.2.2.1. Grab sample capability is provided.
11.5.2.2.3 Common Station HVAC Vent Stack Radiation Monitors Two common station HVAC vent radiation monitors are provided.
One monitor is operational and the other is an installed spare.
The operational monitor extracts samples through an isokinetic probe (different from the probe described in Subsection 11.5.2.1.6, but at approximately the same elevation) mounted in the stack down-stream of all ventilation inputs to the stack. The probe is designed and installed to meet the requirements of ANSI N13.1.
The monitors are offline sampling type (skid mounted) with detectors to measure particulate, iodine, and noble gas radioactivity.
Annunciators in the main control room and radiation p'rotection office and local visual alarms will actuate on iodine, particulate, or noble gas channel ALERT or HIGH radioactivity or on monitor failure.
Purging, operational checks, and calibration are as described in Subsection 11.5.2.2.1. Grab sample capability is provided.
11.5-9
. w -.a . ..~ -- --
_ _ . _ ~. . .x -- - . -.......~
AMENDMENT 34 CPS-FSAR JULY 1985 11.5.2.2.4 Standbv Gas Treatment Svstem 'SGTS) Exhaust Radiation Monitors Two SGTS exhaust radiation monitors are provided. One monitor is operational and the other is an installed spare. The operational monitor extracts samples through an isokinetic probe (different from the ' probe described in Subsection 11.5.2.1.6, but at approxi-mately the same elevation) mounted in the exhaust stack. The probe is designed and installed to meet the requirements of ANSI N13.1.
The monitors are offline sampling type (skid mounted) with detectors to measure particulate, iodine, and noble gas radioactivity.-
Annunciators in the main control room and radiation protection office and local visual alarms will actuate on iodine, particulate, or noble gas channel ALERT or HIGH radioactivity or on monitor failure.
Purging, operational checks, and calibration are as described in Subsection 11.5.2.2.2. Grab sample capability is provided.
11.5.2.2.5 Plant Service Water Effluent Radiation Monitor The plant service water effluent radiation monitor, located in the seal well enclosure, measures the radioactivity concentration 1.i the effluent of the plant service water (WS) system to the seal well. The sample extraction point is located in the WS discharge header downstream of all inputs to the header which may possibly contain radioactivity.
The monitor is an offline sampling type (skid mounted) with a gamma scintillator-type detector to measure gross radioactivity.
Grab sample capability is provided.
Annunciators in the main control room and radiation protection office and local visual alarms will actuate on HIGH radioactivity or on monitor failure.
Sample chamber and sampling return line flushing may be initiated b'y controls locally in the main control room or in the radiation protection office. Inlet sample line flushing may be done locally. Channel operational checks may be performed by actuation of an integrally mounted check source controlled locally, from the main control room, or from the radiation protection office. Provisions are made on the monitor for calibration with a NBS traceable source. Grab sample capability is provided.
11.5.2.2.6 Liould Radwaste Discharae Radiation Menitor The liquid radwaste discharge radiation monitor measures the radioactivity concentration of the liquid rac' waste discharge into the plant service water (WS) discharge headet. The sample extraction point is located upstream of the ctscharge isolation 11.5-10
9
. CPS-FSAR AMENDMENT 34 JULY 1985 conditions. Psrtable CAM's and other sample extraction points located throughout the plant on HVAC ducting to assist. locating areas of high radioactivity are described in Subsection 12.3.4.
11.5.2.2.11 Solid Radwaste System Radiation Monitors The exposure rate of each shipping container in the solid.
radwaste system is monitored at the container capping area during filling and at the shipment monitoring facility prior to shipment.
Each monitor consists of a GM tube detector and local indicator trip unit. Operator indications of exposure rates are provided on a local control panel in the radwaste control center.
11.5.2.3 Radiation Monitor Calibration, Maintenance, Inspection,- Decontamination, and Reclacement 11.5.2.3.1 Calibration All process and effluent. radiation monitors are initially and periodically calibrated to an NBS traceable source. Operational checks are performed by check source actuation or substitution of an-electronic pulse generator for the detector. Special
- calibration factors are determined by comparison of grab sample
- laboratory analyses data to the monitor data.
- 11.5.2.3.2 Maintenance i
Periodic preventive maintenance is performed in accordance with the equipment manufacturer's recommendations. All maintenance is performed in accordance with the manufacturer's requirements.
l Monitors are recalibrated whenever maintenance which can affect their calibration is performed.
11.5.2.3.3 Inspection Process and effluent radiation monitors are located in accessible areas. Periodic inspection and routine surveillance of the monitors is thus readily accomplished.
> 11.5.2.3.4 Decontamination and Reclacement All radiation monitors described in Subsections 11.5.2.1.6, 11.5.2.1.7, and 11.5.2.2.1 through 11.5.2.2.9 are continuous offline samoling types
! with isolation valves provided at the sample and return point anc on each monitor. The monitors may thus be decontaminated or 4
replaced without opening the process system. Flushing or purging I
capabilty is also provided. Detectors, filters, sample chambers, I
and valves on the monitors may similarly be replaced.
11.5.3 Effluent Monitorina and Samolino
, General Design Criterion 64 requirements for .onitoring all effluent discharge paths for radioactivity that may be released i +
b 4
11.5-13
- - , . < - - - , , , , - ,-,mv-- ..--,,,.n,r,-. --,.4-., --r ----..v,,--,,.,.,--.~, , . - , ,,r--, nn--,,,,,-----,w,---, -m- --- --,,--r--.
CPS-FSAR AMENDMENT 34 JULY 1985 from normal operations, anticipated operational occurrences, and from postulated accidents are met.
There are two gaseous effluent discharge paths: the common station HVAC exhaust vent and the standby gas treatment vent.
Monitors are provided for each path as described in Subsections
- 11. 5. 2. 2. 3 and 11. 5. 2.1. 7 for the HVAC exhaust vent and Subsections
- 11. 5. 2. 2. 4 and 11. 5. 2.1. 6 for the standby gas treatment vent. .
There are four liquid effluent discharge paths: the Unit 1 and Unit 2 seal well discharges and the Unit 1 and Unit 2 shutdown service water system discharges to the ultimate heat sink. The plant service water discharges to the seal well are monitored as
-described in Subsection 11.5.2.2.5. The shutdown service water discharges are monitored as described in Subsections 11.5.2.2.7 and 11.5.2.2.8.
Sample frequencies are presented in Tables 11.5-4 through 11.5-7.
11.5.4 Process Monitorino and Samoling The requirements of. General Design Criterion 60 for control of radioactive releases to the environment are met. The following sources of radioactive releases have automatic isolation valves
'as described in the referenced sections:
- a. containment ventilation exhaust (Subsections 11.5.2.1.2 and 11.5.2.1.3),
- b. fuel building exhaust (Subsection 11.5.2.1.4),
- c. post. treatment air ejector off-gas (Subsection l 11.5.2.2.2), ,
- d. liquid radwaste discharge (Subsection 11. 6. 2. 2. 6 )',
and
- e. main steamline (Subsection 11.5.2.1.1).
General Design Criterion 63 requirements for monitoring l radioactive waste process systems are met.
1 The monitors for the gaseous systems are described in Subsections 11.5.2.2.2 and 11.5.2.2.3.
i The monitor for the liquid systems are described in Subsection 11.5.2.2.5 through 11.5.2.2.9. Sampling of the liquid system is described in Subsection 9.3.2.
l The monitors for the solid radwaste system are described in Subsection 11.5.2.2.11.
f l
f
__ 11.5.14_. -
TABLE 11.5 1 PPOCESS RADIATION MONITORING SYSTEMS SAMPLE LINE UPSCALE SETPOINT MONITORED NUMBER OF DETECTOR OR DETECTok ALEkT PROCESS CHANNELS TYPE LOCATION ALARM TRIP SCALE A. SAFETY-REIATED SYSTDtS Main Steamline 4 Camma Sensi- Immediately down- Above full Technical 6 decimal tive Ioniza- stream of last main power back- specifi- log tion Chamber steamline isolation ground, cation valve below trip containment 4 Geiger-Muller Exhaust duct up- Above back- Technical Digital Building ruel Tube stream of connect- ground, specifi-Transfer ion to containment below trip cation Ventilation exhaust Plenum containment 4 Geiger-Muller Exhaust duct just Above back- Technical Digital n Building Vent Tube outside the pri- ground, specifi- .g Exhaust mary contain vent. below trip cation 4
ruel Building 4 Geiger-Muller Exhaust duct up- Above back- Technical Digital Vent Exhaust Tube stream of exhaust ground, specif1 h
[-
ventilation isola- below trip cation Y tion valve Main Control Room 4 Ceiger-Muller intake ducts up- Above back- Technical Digital Air Intake Tube stream of venti- ground, specifi-htion isolation below trip cation v.tve er-Muller Sample line Above back-gh Rang Not oggggag Monitor) ground, Applicable below trip C Sta on 2 ce er-Muller Sample line Above back- Not Digital ,
(High Range ground, Applicable Moni to r) below trip B. SYSTEM REQUIRED FOR Pratt? OPERATIOM Pretreat Air- 1 Geiger-Muller Sample line At technical Not Digital Ejector Off-Gas Tube specification Applicable report level g r*
p Post Treat Air- 4 per Geiger-Muller Sample line Above back- Technical Digital '4 1 Ejector Off-Gas monitor Tubes Beta and ground, Specifi-
$ NaI Scintil- below trip cation .$wh
, lators La N 0,, common Station 4 per Beta and Na! Sample line At quarterly Technical Digital I u HVAC Exhaust monitor scintillators technical specift-specification cation level SGTS Exhaust 6 per Geiger-Muller Sample line At quarterly Technical Digital i monitor Tube; Beta and technical specifi- '
tia a stintil- specification cation lators level
I TABLE 11.5-2 (Cont'd) l I
PRINCIPLE RADIONUCLIDES ALARMS AND CONFIGURATION TYPE SENSITIVITY RANGE MEASURED BASES FOR RANGE TRIPS f MONITOR i
' I SGTS Exhaust Off-Line !
j High Range .
Monitor * .
2.62x10# CPM Gross Gamma RG 1.97, Fail, Alert, Intermediate G-M tube 3.2x10{*.tx) per DCi/cc 3.9x10 DC1/cc NUREC-0737*** High Range Noble Gas Xe133 Xe133**
4.13x103 CPM 2.1x10 -32
.txi per uci/cc 2.5x10 pCi/cc Kr85 Kr85**
RG 1.97, Fail, Alert, High Range G-M tube 9.74 CPM per 1.8x10j .to Gross Gamma High Noble Gas DC1/cc Xe133 1.0x10 pC1/cc NUREG-0737***
Xe133 2.62 CPM per 6.7x10j .to pCi/cc Kr85 3.9x10 pCi/cc , n
- Kr85** w Y
b N Common Station Off-Line. ' $
ui HVAC Vent High 8
- d. Range Monitor
- 4 4 RG 1.97, ' Fall, Alert, Intermediate G-M tube 2.22x10 CPM 3.5x10"y .txp Gross Gamma per UC1/cc 4.6x10 pC1/cc NUREG-0737*** High Range Noble Gas , Xe133 Xe 133* *
~
3.49x103 CPM 2.4x10 2 to ~
per pCi/cc 2.9x10 pC1/cc
- Kr85 Kr85**
9.59 CPM per 2.1x10jl to Gross Gamma RG 1.97, Fail, Alert 3 High Range G-M tube ,
High pCi/cc Xe133 1.1x10 pCi/cc NUREG-0 7 37* *
- Noble Gas t Xel,33**
2.58 CPM per 7.7x10j1 to pCi/cc Kr85 4.0x10 pCi/cc .
j Kr85** I
- Continuous sampling capabilities of these monitors are listed in Table 11.5-7. Nf, Q
- Lower limit of range is based on 15 mR/hr CS-137 background radiation at the monitor and may not be applicable in c 0; @
higher background levels possible when major releases of airborno radioactivity are occurring. mg
- *
- Hofer to compliance Ituport, Regulatory Guido 1.97 (Rovision 3), Revision 1, dated November 1983 for discus'sion of noble gao nenourenwnt rango (parametor CIS). a
TABLE 11.5-7 RADIOIDGICAL ANALYSIS
SUMMARY
OF GASEOUS EFFLUENT SAMPLES .
SAMPLE SAMPLE DESCRIPTION ANALYSIS SENSITIVgTY FREQUENCY (WCi/cm ) PURPOSE Common Station HVAC Gamma Spectrum ' -10
- l. Weekly 10 Effluent Record Exhaust 7,733 3 -10 10
-6 Monthly Tritium 10 Gross Alpha 10
~11 3 -10 I-133 and 135 10
-11 Quarterly Sr-89 and -90 10 O
w 2. Standby Gas Treatment As above, As above Effluent Record Y I' System Effluent Vent when required 2 T' 1 -10 #
w 3. Standby Gas Treatment As required Gamma Spectrga '2 10 uen Record, *
'
- System Effluent Vent postaccident Iodine - 131 10
-10 Emergency Action Plan (High Range Monitor)
~
- 4. Common Station HVAC As required Gamma Spectrga ' 10_Il Effluent Record, Iodine - 131 10 Exhaust (High Range postaccident Emergency Action Plan Monitor)
{
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l g At least Ba/La-140. If quantities of radioactive material released are so low as to preclude accurate measurement,
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I 1 l CPS-FSAR AMENDMENT 34 JULY 1985 NRC ACTION PLAN (NUREG-0660 as clarified by NUREG-0737) - II.F.1 Additional Accident-Monitorina Instrumentation NRC Position The NUREG-0737 requirements evolved from three basic requirements given in NUREG-0578 (Items a through c below) and were subsequently clarified by NRC letters dated September 27, 1979 and November 9, 1979. These letters also include additional requirements resulting in Items d through f below. A summary of these items is as follows:
- a. Noble gas effluent radiological monitors;
- b. provisions for continuous sampling of plant effluents for postaccident releases of radioactive iodines and particulates, and onsite laboratory facilities;
- c. Containment high-range radiation monitor;
- d. Containment pressure monitor;
- e. Containment water level monitor; and
- f. Containment hydrogen concentration monitor.
The individual requirements for each item have been omitted from this synopsis due to their length and detail required for an adequate recitation. CPS Response
- a. Noble Gas Effluent Radiological Monitor Illinois Power Company has installed Noble Gas Effluent l Radiological Monitors as specified by Table II.F.1-1 of NUREG-0 737. The design details of this monitoring system are described in Subsections 7.6.1.2.6 and 7.6.1.2.7.
- b. Sampling and Analysis of Plant Effluents
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Illinois Power Company has provided for l continuous sampling of plant gaseous effluents for postaccident releases of radioactive iodines and particulates as,specified by Table II.F.1-2. gf D
- - - - - ~ - - - -
; 4a .n. - - x --
CPS-FSAR ' AMENDMENT 34 JULY 1985
~
NUREG-0737. The' design details of this monitoring system are described in Subsections 7. 6.1.2. 6 and 7. 6.1. 2. 7.
- c. . Containment High-Range Radiation Monitor Illinois Power Company has installed redundant Containment l High-Range Radiation Monitors and Indicators as specified by Table II.F.1-3 of NUREG-0737. Indicators are located in the MCR. .The design details of this monitoring system are described in Subsection 7.6.1.10.
- d. Containment Pressure Monitor Illinois. Power Company has provided for continuous measure-
. ment and indication of containment pressure over the range from -5 psig to three times the concrete contain- ,
ment-design pressure (10 - 60 psia) . In addition, Illinois Power Company has provided for high-range containment pressure monitoring (60 - 95 psia) as described in Sub-section 7. 5. 4. 4. 2. 2 (la) . Containment pressure is dis-played and recorded in the main control room. The design details of this monitoring system are described in Sub-section 7. 5.1. 4. 2. 4 (1) .
- e. Containment Water Level Monitor Illinois Power Company has provided for continuous indi-cation of suppression pool level over the range from the ECCS suction line inlets to more.than 5 feet above '
the normal water level. The pool level indication is provided in the main control room. The design details of this monitoring system are described in Subsecti.on 7.5.1.4.2.4 (4E5). .
- f. Containment Hydrogen Monitor Illinois Power Company has provided redundant hydrogen l indicators in the control room. The capability covers the range of 0% to 30% hydrogen concentration by volume over a pressure range of -0.5 psig to 30 psig. These monitoring units-have an accuracy of +1.0% of span, which is judged to be acceptable. The design details of this monitoring system are described in Subsection 7.6.1.10.
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